ML20077D448
| ML20077D448 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1991 |
| From: | Allen Hiser NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| NUREG-1426, NUREG-1426-V01, NUREG-1426-V1, NUDOCS 9105300222 | |
| Download: ML20077D448 (55) | |
Text
- - - -
9 w.
NUREG-1426 Vol.1 compi ation 0:: Re Jor:s ::ro:m n
Researc:a Suno:rtec ay t1e
~
Ma':eria~ s Engineering Branca, Division 0:? Engineering 1965 - 1990
~^
U.S. Nuclear Regulatory Commission Office of Nuclear Itegulatory itesearch f
+4..*
l l
l l_
9g 53 g 2 910531 1426 R PDR
l
~ -. _.
AVAILABILITY NOTICE Asanabity of Roterenco Matoncis Cited in NRC Pubhcations McLt documents citcd in NRC pubhcations wol be awaaabio from ono ci tho fo!!an:r g sourCOs; 1.
The NRC Pubhc Document Room, 2120 L Street, NW, Lower Love!, Wto.hington, DC 20555 2.
The Supenntendent of Documents, U.S. Govemment Ponting Offico, P.O. Box 37082, Washington, DC 20013-70B2 3.
The National Technical Informatien Service, Springheid. VA 22161 Although the hsting that fobWs represents the majonty of documents cited in NRC pubbca-tions, it is not Intended to be exhaustwo, Referenced documents avadable for mspection and copying for a feo from the NRC Pubhc Document Room includo NRC correspondence and internal NRC memoranda; NRC Ofhce of Inspection and Enforcement budetins, circulars, information nctices, inspection and investi-gotion not ces; Licenteo Event Reports; vendor reports and correspondence; Comrrussion papers; and epphcont and hconsoc documents end correspondence.
The following documents in the NUREG senes are avadable for purchase from the GPO Sates Program; formal NRC staff and contractor reports, NRC+ponsored conferenco proceed-ings, and NRC booklets and brochures. Also Dvailabio are Regulatory Guides, NRC reguia-tions in the Code of federal Regulations, and Nuclear Regulatory Commission issuances.
Documents avadabio from the National Technical information Servito includo NUREG sones reports and technical reports prepared by other federal agencies and reports prepared by the Atom >c Energy Commission, forerunner egency to the Nuclear Regulatory C-omm:ssion.
Documents avadablo from pubLc and special technical l<branes include all opon hterature items, such as books, jou'nal and penodical articles, end transactions. Federa! Reg: ster notrces, fnderal and state leg: station, and congressional reports can usual!y be obtained from these hbrsnes.
Documents such as theses, dessertations, foreign reports end transintions, and non-NRC conference proceedings are ava:!able for purchase from the organaation spontonng the pubhcation cited.
Sing 10 con es of NRC draf t reports are awadabio freo, to the extent of supp!y, upon wntten request to the Othee of Infctmation Resources Management. D:stnbution Section, U.S.
Nuclear Regulatory Comm ss,on, Wash ngton, DC 20555.
Cop:es of industry codes and standards used in a substantwo mannor in the NRC reguintory process are mn nta;ned at the NRC Library, 7920 Norfoy Asenuo. Bethesda Mary;and, and are awadab e there for refe'ence use by the pubhc. Codes and standMds e'o udua!!y copy-nghted and may be purchased frtm the ong;nat;ng o'ganation or, if they are Amontan NatcqDI Standmdr. from the Amer.can Nabonal St andards ins'.itute, 14'O broadway.
Nc-w York. N r 10018.
. _ = _ _ _ _ _ _ _
NUltEG-1426 Vol. I ltF, R5 Compilation of Reports from Research Supported by the Materials Engineering Branch, Division of Engineering
-1965 - 1990 Manuscript Completed: April 1991 Date Published: May 1991 Compiled by A. L lliser Meterials Engineering Branch Division of Engineering-Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commisslon Washington, DC 20555 j,.."a %,,
4
AI!STRACT Since 1965, the Matetials lingineering Branch, Divi-method development and qualification, and evalu-sion of lingineering, of the Nuclear llegulatory Corn-ation of irradiation ef fects to 1(PV stects.
mission's Office of Nuclear llegulatory f(esearch, and its predecessors dating back to the Atomic lin-
'this report provides as complete a listing as practical ergy Commission (Al!C), has sponsored research of formal technical reports submitted to the N1(C by programs concerning the integrity of the primary sys-the investigators working on these research pro-tem pressure boundary of light water reactors. 'the grams. '.his listing includes topical, final and pro-components of concern in these research programs gress reports, and is segmented by topic area. In have included the reactor pressure vessel (l(pV),
many cases a report will cos er several topics (such as steam pencrators, and the piping. 'lhese research in the case of progress reports of multi faceted pro-prograrns have covered a broad range of topics, in-grams), but is listed under only one topic. Therefore, ciuding fracture mechanics analysis and expenmental in searching for reports on a specific topic, other re-work for 1(pV and piping applications, inspection lated topic arcas should be checked also.
I iii NUl(!!G-1426
l 1
i i
Contenis Page Abstract.....................................................................................
iii Ac k n ow l e d g m e n t s..............................................................................
vii I n t rod u ct io n....................................................................................
1 Annealing.....................................................................................
2 Co r r e la t io n s....................................................................................
2 CrackArrest...................................................................................
2 Dosimetry......................................................................................
4 linvirontrentally. Assisted Cracking and 17atigue...................................................
7 Fract u re M echanics: Analysis.....................................................................
13 Frawre Mechanics: lixperimental-Component Testing.............................................
17 Fracture echanics: lixperimental-Standard Specimen Testing......................................
22 leak Detection 24 NDil-Continuous Wnitoring (Acoustic I! mission)..................................................
24 N D E - I n-S e rvice I n s} cet io n.....................................................................
26 Pi p in g: A n aly sis..............................................................................
31 Pipin g: lixperim e n t al..........................................................................
33 Press u r e Vess e l S t e e l s..........................................................................
37 Iladiation Ilmbrittlement..................
38 it e sid u al S t re sse s...............................................................................
42 S i ca m G e n e ra t o rs..............................................................................
42
'Ihermal limbrittlement (Cast Stainless Stect).....................................................
46 1
l l
v NUld!G-1426 i
ACKNOWLEDGMENTS The assistance of the project rnanagers at the laboratories currently working on research programs for the Materials lingineering Ilranch is appreciated. 'these individuals include:
S.11. Doctor l'acific Northwest 1aboratories C. V. Dodd Oak Itidge National laboratory
- 11. M. Ilackett David Taylor itesearch Center J.11. llawthorne Materials !!nginecting Associates 17.11. K. Karn Oak Itidge National laboratory it. K. Nanstad Oak Itidge National laboratory W. II. l'ennel Oak Itidge National laboratory W. J. Shack Argonne National Iaboratory G. M. Wilkowski llattelle l
vii NUltI!G-1426
INTRODUCTION Since 1965, the hiaterials F.ngineering liranch, Division 1975-1981 hietallurgy and hiaterials itescarch oflingineering of the Nuclear llegulatory Commission's liranch, Division of 1(cactor Safety 1(e-Office of Nuclear llegulatory 1(esearch, and its predeces-Search, U.S. Nuclear llegulatory Commis-sors dating back to the Atomic linergy Commission sion (AIIC), has sponsored t esearch programs concerning the integrityof the primary system pressure boundary oflight 19814986 hiaterials lingineering Ilranch, Division of water reactors. the components of concern in these re-search programs have included the reactor pressure ves-lingineering Technology, U.S. Nuclear set (ItPV), steam generators, and the piping. lhese re-P.cgulatory Comrnission scarch programs have covered a broad range of topics, including fracture mechanics analysis and experimental 1986-1990 hiaterials lingineering litanch, Division of wer k for 1(l'V and piping applications, inspection method lingineering, U.S. Nuclear llegulatory development and qualification, and evaluation of irradia-Commission, tion cifcets to itPV steels.
.Ihc branch sponsoring these research programs has had
'Ihis report provides as compleic a listing as practical of various names and affiliations oser the years, includmg formal technical reports submitted to the NitC by the in-the following:
vestigators working on these research programs. 'ihis list-ing inciedes topical, final and progress reports, and is seg-mente by op area.
semal topics (such as mln many cases a repmt wW c 1965-1973 l(cacter Vessels liranch, Division of f(cac-the case of progress reports of tor Development and Technology, U.S.
Atomic linergy Commission muhMiceted programs), but is listed under only one topic.,lherefore, m searchmg for reports on a specific 1973-1975 hictallurgy and hiaterials itesearch topic, other related topic areas should be checked also.
liranch, Division of f(cactor Safety lle-scarch, U.S. Atomic linergy Commission
'this document will be updated periodically as necessary.
1 N Ult!!G-1426
____._m Compilation of Reports-1965-1990 Anrieniing Correlations Cullen, W. II. and IIiser, A. L "llehavior of Subentical Conen. Hy and quh, R H, "RdadonWp pelweyn and Irans@ition Iemperature 1ests,g,,p!& AM li nI chp oughnq %n ure Whames and Slow Stable Crack Growth 17ollowing a Postirradia-tion Thermal Anneal Cycle," USNRC Report NUR110/
Univenity of Ilhnois, Urbana,11. August 1971.
CR-3833 U.S. Nuclear Regulatory Commission, Wash.
ington, D.C., August 1984.
Dougan, J R., " Relationships lietween Charpy V Notch Impact linergy and Fracture Toughness," USNRC Re.
Ilaw thorne, J. R.. " Survey of Postirradiation Ileat Treat-port NURiiG/CR-2362, U.S. Nuclear Reputatory Com-ment as a Means to hiitigate Radiation limbrittlement of mission, Washington, D.C., Atarch 1982.
Reactor Vessel Steels" USNRC Report NURl!GI CR-0486. U.S. Nuclear Regulatory Commission, Wash.
liason, II. D. and Nelson, !!. II.,
- Improved Model for ington, D.C., I ebruary 1979, Predicting J-R Curves 1 rom Charpy Data, Phase i Final Report " USNitC Report NURl!G/CR-5356, U.S. Nu.
r Regulatory Commission, Washington, D.C., April llawthorne, J. R., *IIxploratory Assessment of Postirra-diation lleat Treatment Variables in Notch Ductility Re-covery of A 533-11 Steel." USN11C Report NURl!G/
i CR-3229, U.S.
Nuclear Regulatory Commission, Crack Arrest Washington, D.C., April 1983.
liarker. D,11. et al.,"A Report on the Round Robin Pro-E** Conducted to livaluate the Proposed ASTM Stan-llawthorne, J. R., " Steel impurity filement liffects on dard.lest Method for Determmmg the Plane Stram Postirradiation Properties Recovery lly Annealing-Final Report," USNRC Report NURl!G/CR-5388, U.S.
Crack Arrest I ractureToughnesspi.,of Petritic Materi-j Regulatory Commission, %jG/(R-4996, U.S. Nu als, USNRC Report,NURi Nuc! car Regulatory Comrnission, Washington, D.C.,
ashington, D.L., January August 1989.
1988.
Itawthorne, J.
R.,
" Irradiation Anneal.Reirradiation Crosley, P.11. and Ripling,11. J.,
Toughness of A533 Grade 11 Class 1 Pressure Vessel j
USNRC Report NURl!G/CR-5469, U.S. Nuclear Regu-Steel." MRI. Report iISSTP-TR-8, Materials Research latory Commission, Washington, D.C., November 1959.
I aboratory, Inc., Glenwoal,11 March 1970.
4 C'"S$7'E'N'8" Ripling,11.J.," Crack Arrest in an In-creaung Mdd,Y, M RL Report ilSSTP-TR-27, Ma Ilawthorne, J. R. and Iliser, A. l... " Phase 2 Investiga-tions of Irradiation Anneal Reirradiation (I AR) Proper.
als Research laboratory, Inc., Glenwood,11., January ties Trends of RPV Welds: Final Report," USNRC U 3-Report NURl!G/CR-5492 U.S. Nuclear Regulatory Commission, Washington, D.C., January 1990.
Crosley, P. II. and Ripling, ii. J.," Development of a Stan-dard Test for Measuring Kiwith a Modified Compact Serser, W. L. "livaluation of System Requirements and Specimen," USNRC Report NURl!G/CR-2294, U.S.
Standards Requirements for Thermal Annealing of Re.
Nuclear Regulatory Comrri On, Washington, D.C.,
actor Pressure Vessels, Progress Report March-Sep-August 1981.
tember iW2." USNiiC R@i NUREG/CR-2780 U.S.
Nuclear Regulatory Commission, Washington, D.C-,
Crosley, P. II. et al.," Cooperative Test Program on Crack March 1983.
Arrest Toughness Measurements," USNRC Report NURl!G/CR-3261, U.S. Nuclear Regulatory Commis-Server, W. L. "Postirradiation Annealing Recovery of sion, Washington, D.C. April 1983.
1jigh Copper Reactor Pressure Vessel Weld Metal HA R T et al.," Critical lixperiments, Measurements :
,I oughness I roperties, USNRC Report NURiiGI and Analyses to listablish a Crack Arrest Methodology
( R-3582, I?GO-MS-63SS, U.S. Nuclear Regulatory h kl P
Vessel Steels, Second Quarterly
( ommission, W ashington, DL, December 1983.
p
, p gg
_gg j9g,' HWdle Ro port ilMI-1934, llattelle Columbus, Columbus, OH, Server, W. L,"In Place Thermal Annealing of Nuclear May 1975.
Reactor Pressure Vessels," USNRC Report NURl!GI CR-4212, U.S. Nuclear Regulatory Commission, Wash-Ilahn, G.T. et al.," Critical lixperiments Measurements ington, D.C.. April 1985.
and Analyses to listablish a Crack Arrest Methodology
- NURiiG-1426 2
- l Compdation of Reports-1965-1990 r
j for Nuclear Pressure Vessel Steels, l'ind Annual Pro-NURl!G/CR-3179, U.S. Nuclear Regulatory Commis-gress Repirt for October 1974-September 1975 " llat-sion, Washingtim, D.C., May 1978.
telle Report ilMI-1937, llattelle Columbus, Columbus, 011. August 1975.
llahn, G. T. et al.,
- Critical lixperiments, Mea urements and Analyses to listablish a Crack Arrest Methodology llahn, G.T. et al.," Critical lixperiments, Measurements for Nuclear Pressure Venel Steels, lileventh Quarterly and Analyses to listablish a Crack Arrest MethoJology Progress Report for April-June 1977," USNRC Report for Nuclear Preuure Venel Steels, l'ourth Quarterly NURl!G/CR420 U.S. Nuclear Regulatory Commio Progren Report for July-September 1975."llattelle He.
sion, Washington, D.C., May 1978.
I port IIMI-1939,llattelle Columbus, Coh.mbus,011 No-vember 1975.
Ilahn, G. T. et al.,
- Critical lixperiments, Measuremer.ts and Analyses to !!stablish a Crack Arrest Methodology L
Ilahn, G.T. et al.. " Critical lixperiments, Measurements for Nuclear Pressure Vessel Steels, Thirteenth Quarterly and Analyses to listablish a Crack Arrest Methahilogy Progress Regyrt for October-December 1977." USNRC for Nuclear Pressure Vessel Steels, lifth Quarterly Pro.
Repart NURI:G/CR-05)H. U.S. Nuclear Regulatory press Report for October-Decernber 1975,"llatte!!c Re.
Commission Washington, D.C., December 1978.
port llMI-1944, llattelle Columbus, Columbub Oll, March 1976.
I lahn, G. T. et al., " Critical lixperiments, M easur ements and Analyses to listablish a Crack Arrest Methodology llahn, G. T. ct al.,
- Critical 11xperiments, Measurements for Nuclear Pressure Vessel Steels, Quarterly Progress and Analyses to listablish a Crack Arrest Methodology Report for January-March - 1978," USNitC Report
- for Nuclear Pressure Vessel Steels, Sixth Quarterly Pro.
NURiiG/CR-0583, U S. Nuclear Regulatory Commis-gress heport for January-June 1976," lhttelle lleport don, Washington, D.C., January 1979.
llMI-1951, llattelle Columbus, Columbus, Oil, July Ilahn, G.1. et al., *L. itical lixperiments, Measurements r
1976'
]
and Analyses to !!stablish a Crack Arrest Methodology llahn, G.T. et al.," Critical lixperiments, Measurements for Nuclear Pressure Vessel Steels, Quarterly Progress and Analyses to listablish a Crack Arrest Methodology Repon for April-June 1978,_ USNRL Report NURl!G/
ington, DA(J.S. Nuclear Regulatory L ommission, W CR %52, for Nuclear Pressure Vessel Steels, Second Annual Pro,
, Mruay WE gress Report for October 1975-September 1976," llat-telle Report IIMI-NURiiG-1959, llattelle Columbus, llahn,0,T. et al.. "Ciitical lixperiments, Measurements C olumbus, Oll, October 1976.
and Analyses to listablish a Crack Arrest Methodology I"' "' "' W * "
b
"' 9"USNRC Report
"" Y
'"E "
llahn,0 T. et al.," Critical lIxperiments, Measurements pon for o mDwember 1978, and Analyses to listablish a Crack Arrest Methodology for Nuclear Pressure Vessel Steels, Eighth Quarterly
' "[ "" ""' " EUI"I"N,"* * *
"U""'
"Y Progress Repirt for July-September 1976," llattelle Re-poit ilMI-NURl!G-1966, llattelle Columbus, Colum-Ilahn, G. T. et al., " Critical lixperiments, Measurements bus,011, February 1977' and Analyses to listablish a Crack Arrest Methodology for Nuc! car Pressure Vessel Steels, Fourth Annual Pro-Ilahn,0.T. et al.. " Critical lixperiments, Measurements press Report for October 1977-September 1978,"
and Analyses to listablish a Crack Arrest Methodology USNRC Report NURiiG/CR-0825, U.S. Nuclear Regu-l for Nuclear Pressure Venel Stects, Ninth Quarterly Pro' laton Commission, Washington, D.C., May 1979.
gress Repirt for October-December 1976," llattelle Re-nort NURl!G-0289, llattelle Columbus, Columbus,011, Iloagland, R. G. et al.," Rectangular 1 CII Specimens for July 1977, Fast Fracture and Crack Arrett Measurements,"llattelle Report !!MI-1933, llattelle Columbus Columbus,011, 11ahn, G. T. et al., " Critical lixperiments, Measurements December 1974, and Analyses to listablish a Crack Arrest Methodology
-- for Nuclear Pressure Venel Steels, Third Annual Pro-Rosenfield, A. R. et al.," Critical lixperiments, Measure-gress Report for October 1976-September 1977,"
ments and Analyses to listablish a Crack Arrest Method-USNRC iteport NURl!G/CR-0057, U.S. Nuclear Regu-ology for Nuclear Pressure Vessel Stects, Progress latory Commission, Washington, D.C., May 1978.
Report for January-June 1979," USNRC Report NURiiG/CR-0991, U.S. Nuclear Regulatory Commis-1 Ilahn, G. T. et al..
- Critical !!xperiments, Measurements sion, Washington, D C., September 1979.
l and Analyses to listablish a Crack Arrest Methxlology i
fot Nucl, ar Pressure Vessel Steels, Tenth Ouarterly Pro-Rosenfield, A. R. et al., " Critical lixperiments, Meas-gress Report for January-March 1977 " USNRC Report urements and Analyses to listablish a Crack Arrest l
1 3
NURl!G-1426
Cornpilation of iteports-1965-1990 4
hiethodology for Nuclear Pressure Vessel Steels, Pro-gineering hiockup " USNitC itep>rt NURiiG/ Cit-4827, gr ess Repirt for J une-December 1979," USNitC Report U.S. Nuclear Regulatory Cornmission Washington, NURl!G/CR-1555 U.S. Nuclear Regulatory Cornmis-D.C., January 1987, sion Washington, D.C., June 1980.
Guthrie, G. L et al., eds.,"I.WR Pressure VesselItradia.
Rosenfield, A. R. et al.,
- Critical lixperiments, hicasure.
tion Suncillance Dosimetry Quarterly Progress Report mentsand Analyses tolistablish a Crack Arrest hiethod.
January-hfarch 1978," USNRC Report NURl!G/
ology for Nuclear Picssure Vessel Stects, Progress CR-0285, U.S. Nuclear Regulatory Commission Wash.
Report for January-htarch 1980," USNitC Report ington. January 1978.
NURiiG/CR-1601 U.S. Nuclear Regulatory Commis-sion, Washington, D.C., July 1980.
Guthrie, G. L and L, ppm. cutt, ii. P., eds.. "1.WR Pres-i sure Vessel itradiation Surveillance Dosime Quarterly Rosenfield, A. R. et al., " Critical lixperiments, hicasure.
Progress Report October 1977-Decemt 1977 "
ments and Analyses to listaMish a Crack Arrest Method.
USNRC Report NUREG/CR-0127, U.S. Nuc e Ogu-ology for Nuclear Pressure Vessel Steels (Final R eport),"
latory Comrnission, Washington, D.C., June h,
j USNRC Report NURiiG/CR-1887. U.S. Nuclear Regu-latory t ornmission. Washmgton, D.C., January 1981, Guthrie, G. L et al., eds.," LWR Press re Vesselirradia.
i tion Surveillance Dosimetry Quarterl) s'rogress Report Shukla, A.. l'ourney, W. L, and Irwin, G. R., " Study of July-September 1977," USNRC Report NURiiG/
linergy loss and its hicchanisms in Ilomalite 100 During CR-0038. U.S. Nuclear Regulatory Commission, Wash.
Crack Propagation and Arrest," USNRC Report ington, Di., November 1976.
NUREG/CR-2150, U.S. Nuclear Regulatory Commis-sion, W ashington, D.C., August 198L Gut hrie, G. L et al., eds., " LWR Pressure Vessel Irradia-tion Surveillance Dosimetry Quarterly Progress Report July-September 1978," USNRC Report NURl!G/
Dosintelry CR-0551 U.S. Nuclear Regulatory Commission Wash-ington, D.C., December 1978.
Asgari, M., Williams, ht. L, and Kam, F.11. K.,"Determi-nation of the Neutron and Gamma Flux Distribution in Guthrie, G. L et al., eds.,"1.WR Pressure Vessellrradia, the Pressure Vessel and Cavity of a iloiling Water Reae, tion Surveillance Dosimetry Quarterly Progress Report tor," USNRC Report NURl!G/CR-5449, U.S. Nuclear April-June 1978," USNRC Report NURl!G/CR-0550, Regulatory Commission Washington, D.C., June 1990.
U.S. Nuclear Regulatory Commission, Washington, D.C., June 1979.
Italdwin, C A., "Two-and 'lhree. Dimensional Diffusion Theory Calculations for the Pool Critical Assembly Pres-Guthrie, G. L and hiclitroy, W. N., eds.," LWR Pressure sure Vessel Wall llenchmark Fucihty," USNRC Report VemunaWaton Survedlance Dosimetry Quart erly Pro-
- NURiiG/CR-2579, U.S. Nuclear Regulatory Commis-press Report October-December 1978," USNRC Report.
sion, Washington, D.C., July 1982.
NURiiG/CR-0720, U.S. Nuclear Regulatory Commis.
sion, Washmpton, D.C., July 1980, llaldwin, C. A., "Two. Dimensional Discrete TranWI Theory Calculations for the Pool C itical Assembly Pres-G uthrie, G. L and Mclilroy, W. N., eds., " LWR Pressure sure vessel Wall llenchmark Facihty," ORNI. Report Vessel Itradiation Surveillance Dosimetry Quarterly Pro-ORN1JCF-84/57 Oak Ridge Nationallaboratory, Oak gress Report January-Maren 1979," USNRC Report Ridge, TN, March 1984.
NURl!G/CR-1240, Vol. L U.S. Nuclear Regulatory Commission, Washington, D.C., December 1480.
tirackenbush, L W., Reece, W. D. and Tanner, J. I!..
r
" Neutron Dosimetry at Commercial Nuctcar Plants, Fi-Guthrie, G. L and Melilroy, W. N., eds. " LWR Pressure nal Report of Subtask C: 311e Neutron Spectrometer,"
Vessel Irradiation Surveillance Dosimetry Quarterly Pro-USNRC Report NURl!G/CR-3610, U.S. Nuclear Regu-gress Report July-September 1979," USNRC Report latory Commission, Washington, D.C., September 1984.
NURl!G/CR-1240, Vol.111, U.S. Nuclear Regulatory Commission, Washington, D.C., December 1980.
Chowdhury, P., Williams, M. L, und Ham, F,11. K., De-Guthrie, G. L and Mcliiroy, W, N., eds., " LWR Pressure velopment of a Three-Dimensional Flux Synthesis Pro-Vessel Irradiation Surveillance Do.simetry Quart erly Pro-gram and Comparison with 3-D Transport Theory Re-press Report October-December 1979," USNRC Heport suits", USNRC Report NURl!G/CR-4984, U.S. Nuclear NURl!G/CR-1240, Vol. IV, U.S. Nuclear Regulatory Commission, Washington, D.C., January 1988.
Cornmission, Washington, D.C., December 1980, Fero. A. I1., -Westinghouse Class 3, Neutron and Guthrie, G. L and Mclilroy, W. N, eds.,"I WR Pressure Gamma. Ray flux Calculations for the VliNUS PWR iin-Vessel Irradiation Sunci!!ance Dosimetry Quarterly i
i i
-. - - - -. ~. - - -
m___
Compilation of Reports-1965-1990 s
Progress Itepirt January-hlarch 1980," USNltC Report Thi-7128, Oak Ridge Nanonal laboratory, Oak Itidge, i
NUlti:O/CR-1241, Vol. I, U.S. Nuclear Regulator)
TN, hiay 1981, i
Commission, Washington, D.C., December 1980.
Kam, it. II. K., ed., "Paiceedings of the l'ourth ASTM.
Outhrie,0. I, and hici!!roy, W. N., eds., *1.WH Pressure I URATOh! Symposium on Reactor Dosunetry, Hrsdia-1 VenelIrradiation Surveillance Dosirnetty Quarterly l* o.
tion hietrology Techniques, Data liases and Standardi/a-i gress Report April-June 1979," USNRC lleport tion, h1 arch 22-26.1982, Gaithersburg, h1D," USNRC NURl!O/CR-1240, Vol.11. U.S. Nuclear itepulatory Conference Proceedmps NURI O/CI'-0329, Vols. l and Commission, Washington, D.C., January 1981,
- 2. U.S. Nuclear Regulatory Comtninion Washington, D.C., July 148..
1 Outhrie, O.1. and hititiroy, W. N., eds.,"1.WR Preuure Venellrradiation Surveillance Dosimetry Quarterly Pro.
Kam, F,11. K. et al., "Preuvre Vessel Fluence Analysis i
press Report April-June 1980," USNRC W yrt and Neutron Dosimetry," USNitC iteport NURliG/
l NURI:O/CR-1241, Vol. II, U.S. Nuclear McNatory CH-5049 U. S. Nuclear Itcrulatory Comminion, Wash.
Commission, Washington, D.C., May 1981, ington D.C., Dee:mber 1987.
ljppincott,11. P. and hici!Iroy, W N. cds., *l WR Pres-L Guthrie,0.1. and hici!!roy, W, N., cds., *l.WH Pre;.sure l
Vessellreadiation Surveillance Dosimetry Quarterly l to, sure Veml SunvHance Dounieuy improvement Pro-gress Iteport January "'l-htarch 1981," USNRC Re.
gram Quarterly Progress Report October 1982-Decem-port NURl!O/CR-234J., Vol.1. U.S. Nuclear Regulatory ber 1982," USNRC Repon NURI:O/CR-2805 Vol. 4 Comenission, Wa hington D.C., October 1981.
U.S. Nuclear llegulatory Commission, Washington, D.C., July 1983.
Guthrie, G.1.and hiclihoy, W. N.. (ds. "I.WR Pressure Vessel Irradiation Surveillance Dosimetry Quarterly Pr o-Uppincott, !!. P. and hiclitroy, W. N., eds., "1 %,H Pres-
' tress Report October 1980 December 1980," USNRC sure Vesel SunmHanw Dodmeuy improvernent Pro-heport NURiiO/CR-1241. Vol. 4, U.S. Nuclear Regula-F"* Ouanerly Propeu Repon,Januay 1983-Marop tg Commission, Washington, D.C., November 1981, 1983,,, USNRC Report NURI!G/L R-3391. Vol.1, U.S.
Nuclear Regulatory Commission, W ashmgton, D.C., No-vember 1983.
Outbrie, G. I. and Mclilroy W. N., eds.,"1.WR Pressure Y essel Irradiation Surveillance Dosimetry Quarterly Pro nress Report October 1481-December 1981, USNRC; ljppincon, P.. P. and Mciiltoy, W. N., eds., "1.WR Pres-1 Report NUREG/t R-2345, Vol. 4, U.S. Nuclear Regula.
sure Vessel Surveillance Dosimetry improvement Pro.
tory Commission, % ashmgton, D.C., October 1982.
gram Quarterly Propess Report April 1983-June 1983,"
USNRC Repor t NURl!G/CR-3391. Vol. 2. U.S. Nuc! car Outhrie,0 l.and hici!!roy, W. N., cds., al.WR Preuure Regulatoy ComnMon, WaWnpon, E, Apd M.
l Vessel Irradiation Surveillance Dosimetry Quarterly Pro' Ijppincott, !!. P. and Mci!!roy, W, N., eds., "I.WR Pres-gress Report April 1981-June 1981," USNRC Report sure Vessel Surveillance Dosimetry improvement Pro-NUldiG/CR-2345. Vol. 2. U.S. Nuclear llegulatory pram Quarterly Progress Report October 1983-Decem-Commission, Washm, gton, D.C., December 1982, ber 1983." USNRC Repon NURl!O/CR-3391, Vol. 4, U.S. Nuclear Regulatory Comminion, Washington, Guthrie,0,l and Mclitroy, W. N., eds., *l.WR Pressure D.C., May 1984.
Venel Surveillance Dosimetry improvement Program Quarterly Progress Report January 1982-March 1982,"
1Jppincott,11. P. and Mclitroy, W. N., eds.,"Ij ht Water g
USNRC Rc;mit NURl!G/CR-2805, Vol.1. U.S. N uclear Reactor Prenure Venel Surveillance Dosimetry Im4
- Regulatory Commission, Washington, D.C., January provement Program Semiannual Progren Report Octo.
- 1983, her 1983-March 1984," USNRC Report NUREG/
CR-3746, Vol.1. U.S. Nuclear Regulatory Commission.
G uthrie,0.1. and Mclitroy, W. N., eds., *l.WR Preuure Washinson, D.C., November 1984.
Vessel Surveillance Dosimetry improvement Program Quarterly Progress Report - April - 1982-June 1982,"
IJppincott, !!. P, and Mci!!roy, W. N., eds., "Ij ht Water g
USNRC Report NURiiG/CR-2805, Vol. 2, U.S. Nuclear Reactor Presure Vessci Suncillance Dosimetry Im-Regulatory Commission, Washington, D.C., January provement Program Semiannual Progress Report April 1983.
1984-September 1984," USNRC Report NURl!G/
CR-3746 Vol. 2, U.S. Nuclear Regulatory Commission,
.-Johnson, J. O.,
Miller, L F., and Kam, it 11.
K.,
Washington, D.C., April 1985.
"Neutronics Model of the llulk Shieldmg Reactor (llSR):
- Validation by Comparison of Calculations mth the I!x.
Ijppincott, ii. P. et al., "livaluation of Surveillance Cap-perimental Measurements." ORNI, Report ORNl>
sute and Reactor Cavity Dosimetry from II.11. Robinson 5
NURl!G-1426
Compilation el Repor ts-1965-1990 tIrut 2 Ople 9," tISNitC lleport NUltl'(i/CR-4576, Mel:Iroy, W. N. et al., eds., "1.Wil Pressure Vessel Sur-ll.S. Nucicar llerulatory Comrmssion, Washington, scillance 1)osimetry impunement Prortam 1984 Annual D.C., l'elsruary 1987, Iteport October 1,19S3-September 30,1984," USNitC 11eport NURI G/ Cit-3746,Vol. 3,(f.S. Nuclear iterula-Maciter,11.11., *l 1 PillCON Analysis of I'ressure h' U"D""*i""' Wa' hington, D.C., Apnl 1955.
Vesul Suncillante Dosunctry Interted into 11. II.
Robinson-2 during Cycle 9," liSNRC Report Nt!RI~O/
rey, %,, N.. ed.,"1.%,11 Pressure Vessel S.urveillante
( 11-4439, U.S. Nuclear Herulatory Corntmwion, Wash.
Dosundn Imptovement Pairmrn: IM Power Reactor inrton, D'C.* August 1986.
SunuHanee PhysiemDmundry Data Rase Compen-dmm," USNRC Report N111ti!G/CR-3319, t.S. Nu-dear Rerulatory Commission,Wastunrton. D.C, August Maerker,it.1; "Analysisof the NI SDlP2 and NI SDlP3 p;g3, Itadial Shield and Cavity lipenments " USNRC Report NURI:G/CRJSS6, U.S. Nuclear 1(crolatory Comenn-hkl:Iroy, W. N. and I ippincott, !!. P., eds., "1.WR Pro.
sion Wastungton, D.C. May 1%7.
sure Vessel Suneillance 1)osunctry Iraprovement Pro-pram 1955 Annual iteport, October 1984-Sept (mber Maciter, R. IL " Analysis of the VI NUS-3 I Aperi-14h5." USNI(C lleintt NtfRl:U/ Cit-4307. Vol.1 U.S.
menti.," llSNltC Report Nt!RlWER-5338, U.S. No.
Nudear Regulatory Commiwion Washington, D.C.,
dear itef ulatory Commiwon, Wastungton, D.C., August January 1956.
1989 hk 1: troy, W. N., ed.,"1.WR Pressur e Vewel Surveillanee Dosimetry improvement Program: l'Sl' lspenments Mtlitroy, W. N., cd,"1.WR Prewure Vewel Surveill.uite Summary and Illind Test Results" USNRC Report Dosimetry Irnpnnement Prograrn 1979 Annual Report,"
NURIM'R-3320 Vol.1. U.S. Nudear Regulatory llSNitC iteport NURlWCR-1291,l!.S. Nuclear Repu.
Comnuwon, Welunrton, D.C., July 1986.
latory Commission, Washington, D.C,1 ebt uary 19x0.
Mel!!roy, W. N., ed., "1.WR Pr coure Vessel Sun cillance Melilroy, W. N. et al., edw "I. Wit Prewure Vewel Sur.
Doumetry imprmement Program 1986 Annual Report stillance Dosimetry improvement Prortam 1980 Annual (October 1985-September 1986)," USNRC lleport Report (Ostober 1,1979-September 30,1%0)," llSNRC NtIRI.G'OR-4307. Vol. 3. U.S. Nudear Iterulatory iteport NilRiitiTR-!747, ll.S. Nudear Rerulatory Comnnwion, Washinrton, D.C.. Apul 1987.
Comminion, Washmrton,1).U., Apnl 1981.
hklittoy, W. N. and Gold,11., ed.,"1.WR Prc9ute Vessel Surveillance Dosunetry improvement Program: PSl' hk Fh oy, W. N., ed.,").WR Pr euure Veuel S.urveillance P
Do'ametry Program "lISNRC iteport Nt!RI G/
Doumctry imprmement Propram: P( A lipenments CR-3320, Vol. 3, U.S. Nuclear kerulatory Commiwion, and lilind Test " USNRC lteport NUltl:G/CR-lShl',
We nrton, D.C., October 1987.
U. S,. Nudcar Herulatory Comunwion, Wadunrton D.C, J uly 1%1.
Mel.lr oy, W. N. and Gold, R., ed.,"1 Wit Pressure Vevel Suncillance Dosimetry improvement Program: PSF hklitroy, W. N. et al., edt. "1.WR Prewure Vewel Sur-Metallurry Program," USNRC Report NURl:G/
veillance 1)osimetry imprmement Program 1982 Annual CR-332u, Vol. 4, U.S. Nudcar Regulatory Commiwion, Report (October 1,1%1-Septembe r 30,1%2)," t ISN RC Washmrton, D.C, Nmember 1987.
Report NURIWCR-2805, Vol. 3, t !.S. Nuclear Rerula-1ory Commimon, WashinyIon, Dr, January 1983.
Miller, I _1. and Williana, M.1-,
- Computational Meth-odolory for the Oak Ridre Research Reactor (ORIG and Nki Iroy, W. N. et al., edt, *1.WR Pr essure Vessel Sur-Ilulk Shieldmr Reactor (llSIO: CrossSection Generation veillante Dosunctry Imprmement Program 19S3 Annual and Va%uon, Volume 1," USNRC Report NURl:G/
3U ' M I' t hS. Nuclear Regulatory Comnussion.
@% acington, DI,., Manh 1986.
Report (October 1,1982-Septernber 30.19S3)." USN RC Report NU R1iGCR-3391. Vol. 3, I f.S. Nucicar Rerula-tory Commiwion, Wdmrton, Dr, June 1984.
Morakinyo. P. O., Wilh.uns, M. l _, and Kam, l'.11. K.,
"Analysn of the VI Nt S PWR lingmeeting MoeLup 11-Mel;lroy, W. N., ed,"1.WR Pressure Vewel Surveillance penm' nt-Phasc 1: Source Distobution " USNitC Re-e Doumetry imprmement Program: 14 'A ISpenments, port Nt1Rl:(iCR-3NE l!.S. Nuclear Regulatory Com-libnd Test, and Physics-Dosimetry Support for the PSl~
misuon. Washington, l)r. Aurust 1984, 1 Aperiments,"l1SNRC Report NtIRidiCR-331x, U.S.
Nudear Regulatory ( 'om m iwon. Washmrton, Dr.
Stallmann, I. W.,1:astham, J.11, and Kam, IL 11. K.,
September IW.
" WIND ()WS-A Propram for the Analysn of Spectral Nt IRI (i-1426 6
Corupilation of Rc;vns-1965-1990 Data l' oil Activation Measurements," OltNI. Report Nuclear Regulatory Commission Washington, D.C.,
ORNIMM-6656, Oak Ridge National 1aboratory, Oak i ebruary 1985.
Ridge,'IN, December 1978, Atteridge, D. G., liruemmer, S. hi., and Page, R. li.,
Stallmann, F. W. et al., " Reactor Calculation 'llench-
"livaluation of Welded and Repair Welded Stainless mark' PCA lilind Test Results " USNRC Report Steel for 1.WR Senice Annual Report for 1984,"
NURl!G/CR-1872 U.S. Nuclear Regulatory Commis-USNRC Report NURl:G/CR-3613 Vol. 2, U.S. Nuclear tion, Washington, D C., January 1981.
Itegulatory Commission Washington, D.C., June 1985.
Stallmann, F. W., "1.SleM2: A Computer Program for Atteridge, D. G. et al., " Evaluation of Welded and I. cast Squarcslegarithmic Adjustment oINeutron Spec.
Repair Welded Stainless Steel for LWR Senice, Semi-tra," USNRC lleport NURiiG/CR-434), U.S. Nuclear annual Report for October 1984-March 1985." USNRC Regulatory Commission, Washmgton D.C.. March 19S6.
RCPort NURl!G/CR-3613 Vol. 3 No.1. U.S. Nuclear Regulatory Commission Washington, D.C., September Williams, M. l and Miller, L. P., " Computational Meth-I985*
odology for the Oak Ridge Research Reactor (ORR)and llulk Shielding Reactor (llSRh "Ihe VTIURR Input Atteridge, D. G. and liruemmer, S. M., "lisaluation of Processmg Code for the llDLD VI!NTURl! System, Vol, Wek!cd and Rep.dr. Welded Stainless Steel for 1.WR ume 11" USNRC Report NURl!G/CR-3064. Vol. 2.
Service Annual Report for October 1984-September U.S. Nuclear Regulatory Commission, Washington, 1985 " USNRC Report NUlt!!G/CR-3613 Vol. 3 No. 2, D.C., April 1986.
U.S. Nuclear Regulatory Commission, Washington, D.C., October 1986.
Williams, M, !_, l.andesman. M. and Kam F.11. li" Cal-culation of the Power Distnbution in the VliNUS PW R llamford, W. I1., "A Summary of linvironmentally As.
Mock Up llenchmark usmg t wo. Group Diffusion lhe' sisted Crack. Growth Studies I erformed at Westinghouse ory, USNRC Report NUR110/CR-4647, U.S. Nuclear lilectric Corporation Under 1 unding from the licasy-Rerulatory Commission, % ashington, DI., August Section Steel Technology Program," USNRC Report Nk NURl!G/CR-5020 U.S. Nuclear Regulatory Commis.
sion, Washington, D.C., May 1988.
Williams,M L.,Childs, R. L and Asgari, M.," Analysis of litothers, A. J. and Woalford D. A., "Ihe liffect of Cy-
- 11. R. Robinson PWR Vessel l'luence for Cycle 10 Utili/-
clic Strain Aging on the !!mbrittlement of a Plain Cmhon irg Partial Ixngth Shield Assemblics," USNRC Report Steel Plate," Gli Report GilAP-10140, General Electric NUREGICR-5530, U.S. Nuclear Regulatory Commis-Corporation. San Jose, CA, January 1970.
sion, Washington, D.C., September 1990.
Ilrown, H. F, O' Dell, C. S., and Foley, R. T., "An fix-
'7 S'"d # """" "
P "!"* Cracking in Sensitized.9"IF"""I"d'#',',
I EnvironmentallpAssisted trucking atul 7
rosion Ivpc 304 Stainless Steel, Fntigue USNRC Report NURI:G/CR-0754, U.S. Nucicar Repu-latory Commission, Washington, D.C., April 1979.
Atteridge, D. G., liruemmer, S. M., and Page, R. l!.,
"livaluation and Acceptance of Welded and Repair-Uniemmer, S. M., Charlot, l A., and Atteridge, D. G.,
Welded Stainless Steel for 1.WR Senice, Annual Report "livaluation of Welded and Repair Welded Stamless for 1983," USNRC Report NURiiG/CR-3613, U.S. Nu-Steel for 1.ight Water Reactor (1.WR) Senice, Composi-clear Regulatory Comn.ission, Washington, D.C., June tional liffects on the Sensiti/ation of Austenitic Stainless 1984-5teels," USNRC Report NUldiG/CR-3918, U.S. Nu-clear Regulatory Commission, Washington, D.C., De-Atteridge, D. G., llruemmer, S. M., and Page, k. ii.,
cember 1984.
"livaluation of Welded and Repair. Welded Stainless Steel for LWR Service, Quarterly Report for January-Clarke, W. G., Romen, V. M., and Danko, J. C., "Detec-March 1984," USNRC Report NUREGeCR-3911 Vol.1, tion of Sensituation iri Stainless Stect Using lilectro-U.S. Nuclear Regulatory Commission, Washington, chemical Techniques," Gli Report GliAP-21382, Gen-D.C., November 1984.
eral lilectric Corporation, San Jose, CA, August 1976.
Atteridge, D. G., Uruemmer, S. M., and Page, R. II.,
Clarke, W. G., " Reactor Primary Coolant System Pipe "livaluation of Welded and Repair Welded Stainless Rupture Study Method for Detect;an of Sensitization in Steel for LWR Senice, Quarterly Report for Apol-June Stainless Steel, Progress Report No. 42, October-1984," USNRC Report NURl!G/CR-3911 Voh 2, U.S.
December 1977," USNRC Report NURl!G/CR-0155, 7
~
Compilation of iteports-1965-1990 U.S. Nuclear Iteputatory Commission, Washington, Cullen, W,11., Tortonen, K., and Kemppamen, h1., "lif.
D.C., January 1978.
fccts of Temperature on l'aligue Crack Growth of A 50S-2 Steel in 1..WR linvironment," USNRC Report Clarke. W. G. and Itomero, V. M.. " Detection of Sensiti-NURl:G/ Cit-3230, U.S. Nuclear llegstatory Commis.
/ation in Stainless Steel: 11.1 PR hiethat for Nondest.
sion, Washmpton, D.C., April 1983.
ructive lield Tests " Gli lleport Gl!AP-12697, General I?lectric Cortwration, San Jose, CA, l'ebruary 1978.
Cullen, W.11., ed., "Proseedmgs of the International Atomic linergy Agency Specialists' Meetmg on Suberit.
Clarke, W. G., " Reactor Primary Coolant Ssstem Pipe ical Crack Growth,1 reiburg,1-ederal Republic of Get-llupture Study Method for Detection of Senbti/ation in many, May 11-15,1981," USNitC Conf erence Proceed.
Stainless Stee'l, Progress iteport No. 43, January-March ings NURl:G/CI'-0044, Vols.1 and 2. U.S. Nuclear 1978," USNRC Report NUlti G/ Cit 4006, U.S. Nuclear Refulatory Commission, Washington, D.C., May 1983.
Regul:. tory Commission Washington, D.C., September 1978' Cuhn, L, De Tatipue C. rack b,rowth Rates of A $084 Steel in Picssuri/eJ, liigh-Temperature Water "
USNRC Report NUlti G/CH-3294, U.S. Nuclear Itepu.
Clarke, %,. G,,,.lleactor i,rimary ( oolant Systern Pipe latory Comme.sion, Washington, D.C., June 1983.
Itupture Study Method for Detection of Sensituation m Stamless Steel, Progress Report No. 44, Apol-June Cullen, W. II. et al., "The Temperature Dependence of 1978," USN'tC Report N Ulti G/ Cit-0567, U.S. Nuclear 1-atigue Crack Growth Itates of A 351 CI'8A Cast Stain-Regulatory Commisuon, Washington, D.C., October less Steel in 1.WR linvironment," USNRC Report 1978.
NURl:G/CR-3546, U.S. Nuclear llegulatory Commis-Clarke, W. G., " Reactor Primary Coolant System Pipe Rupture Study Method for Detection of Senuti/ation in Cullen W.11., "I alipue Crack Grow th Itates of I ow-Stamless Steel, Progress iteport No. 45. July-September Cathon and Stamless Piping Steels in 1. Wit linviron-1978," USN RC Report N UR l:G/ Cit-0541, U.S. N uclear ments," USNRC Report NURlWCit-3945, U.S. Nu-Regulatory Commission, Washington. DL, January clear llegulatory Ocmmission, Washington, D.C.,
1979 l'ebruary 1985.
Clarke, W. G., " Reactor Primary Coolant System Pipe Cullen, W.11., "The liffects of Sulfur Chemistry and Ruptute Study Method for Detection of Senutuation m I low Rate on I atipue Crack Growth Rates in 1.WR'linvi-Stamless Steel, l' regress Report No. 46, October-ronments." USNRC Report NURl!G/CR-4121, U.S.
December 1978," USNRC lteport NURl;G/CR-0834, Nuclear lleputatory Cornnssion, Washington, D.C,
U.S. Nuclear Regulatory Commission. Washington, 17ebruary 1985.
D.C., August 1979, Cullen, W. II., Gabetta, G., and llannmen,11., " A Ite.
Clarke, W. G., "The 1 PR Method for the Detection of view of the MoJels and Mechanisms for linvironmen-Sensiti/ation in Stainless St eels," USNRC Report tally Assisted Crack Growth of Pressure Vessel and Pip-NURI:G/CR-1095, U.S. Nuclear Regulatory Commis.
ing Steels in PWR linvironments," USNRC Report sion, Washington, D.C., Aprd 1981.
NURI G/CR-4422, U.S. Nuclear Reputatory Commis-sion, Washington, D.C., December 1985.
Crapnolino, G., C/ajkowski, C., and Shack, W. J., "Rei, Cullen, W. II., ed., "Proceedmps of the Second l All A view of I tosion Corrosion in Single Phase I' lows' Sp i. dish' Meeting on Subentical Crack Growth, Sen-USNRC Report NURiiG /CR-5156, U.S. Nuclear Repu' dai, Japan, May 15-17, 1985," USNRC Conference Pro-latory ( onunission, % astunpton, D.(., August 1988 ecedmps NURl!G/CP-0067, Vols. I and 2, U.S. Nuclear Cullen, W,11. et al., "l atigue Crack Growth of A 50x Steel in Iliph/lemperature, Pressuri/ed Reactor-Grade Cullen, W. II.,"l:atigue Crack Grow th Rates in Pressure Water," USNRC Report NURI G:CR-0969, U.S. Nu-Vessel and Pipmg Steels m 1 WR linvironments,"
c! car Regulatory Commission, Washmpton, D.C., ScP-USNRC Report NURl!G/CR-4724, U.S. Nuclear Regu-tember 1979 latory Commission, Washington, D.C, March 1987.
Cullen, W. I1. anJ Torronen, li, " A Reuew of l'aligue Cullen W.11. and llrock. D. R.. "1 he tilfect of Vanable Crack Growth of Pressure Wssel and P:pmp Steels m Amphtude loading on A 533-11 Steel m liigh.
Iligh21 ernperature, Pressurved,lteacto. UraJe Water,"
'lemperature Air and Reactor Water linnronments,"
USNRC Report NURI:G'OR--1576, U S. Nuclear Repu-USNRC Repo't NURIGUR-4429, U.S. NutIcar Itepu-latory Commisuon, Wastungton, Dr. September 19s0.
latory Commisuon, Was.hmpton, Dr April 1988 NURil b 1426 x
Compilation of Reports-1965-1990 l
]
Cullen W.11. and Jolles, ht. it.,
- Fatigue Crack Growth llate, D. A., Yuen, J.1, and Gerber T. I., *l aligue of Part 'through Cracks in Pressure Vessel and Piping Growth in Piping and itPV Steels in Simulated llWR r
Steels: Air linvironment Results," USNitC lleport Water litivironment." USNRC lleport NUlt!!G/
l NUREG/CR4828. U.S. Nuclear Hegulatory Commis-C1h0390, U.S. Nuclear Regulatory Commission, Wash.
sion, Washington, D.C., October 1988.
ington, D.C., March 1979.
l t
Cullen, W.11., ed., "Proceedmgs of the ' third Interna.
llanninen,11. I!.. Vulli, M., and Cullen. W. Il., "Sur face l
tional Atornie linergy Agency Specialists' Meeting on Spectroscopy of Pressure Vessel Steel Fatigue Fracture j
Subcritical Crack Growth, lleld at Moscow, USSit, Surface Films Formed in PWR Envir<mments," USNitC May 14-17,1990," USNRC Conference Proceedmgs Report NURl!G/ Cit-4863, U.S. Nuclear Regulatory NUlti!G/CP-Oll2, Vols. I and 2. U.S. Nuclear Regula.
Commission, Washirgton, D.C., July 1987, tory Commission August 1990.
James, I., A. and Williams, J. A., "licavy Section Steel Crajkowski, C. J., "l'esting of Nuclear Grade 1.ubricants Technology Program Technical Report No. 21,'lhe lif-t and'lheir liffect on A5401124 and A193117 llolting Ma.
feet of,Iemperature and Neutron irradiation upon the terials" USNitC Report NUREGICR-3766, U.S. Nu.
Fatigue Crack Propagation lichavior of AS'thi A533 clear Regulatory Commission, Washington, D.C., March Grade 11. Class 1 Steel,",IlliDI. Report lil!Dl/lhill
- 1934, 72-132, llanford !!nginecnng Development laboratory, Richland, WA, September 1972.
Diercks. D. R., "Chernical Decontamination and Chemi-James, l A., "A Survey of the Effect of Ileat-To lleat
- cal Cleaning of 1.WR Components and Possible Interac-Variations Upon the I aligue. Crack Propagation lichav.
tions with Metallurgical Aging liffects," USNRC Report for of'lypes 304 and 316 Stainless Steels," lilIDL lleport NUREG/CR-5180, U.S. Nuclear Regulato.y Commis-lillDl/lh1E 75 37,llanford I!ngineering Development sion, Washington, D.C., November 1988.
laoratory, Richland, WA. May 1975.
Fox, M. J., " Uniqueness of Iloiting Water Reactor Jonas. O., *litosion. Corrosion of PWR Feedwater Piping Prirnary Water Chemistry, Final Report October Survey of lixperience. Design, Water Chemistry and Ma-1985-March 1986," USNRC Report NURiiG/CR-4602, terials," USNRC Report NURiiG/CR-5149. U.S. Nu.
i U.S. Nuclear Regulatory Commission, Washington, clear Regulatory Commission, Washington, D.C., March D.C., May 1986.
1988.
l'ox, M. J., *A Review of Iloiting Water Reactor Water Kassner.T. F. et al., *linvironmentally Assisted Cracking Chemistry, Science, Technology and Performance "
in 1.ight Water Reactors Semiannual Report October 7
USNRC Report NUREG/CR-5115, U.S. Nuclear Regu.
1988-March 1989," USNRC Report NUltEG/CR-4667 latory Commission, Washington, D.C., February 1989.
Vol. 8 U.S. Nuclear Regulatory Commission, Washing.
I ton, D.C., June 1990.
Gabetta, G. and Cullen, W. II., " Application of a Two.
Mechanisms Model for Environmentally-Assisted Crack Keck, R G.and Griffith, P.,* Prediction and Mitigadon of Growth," USNRC Report NUREG/CR 4723, U.S. Nu.
!!rosion. Corrosive Wear in Secondary Piping Systems of 3
clear Regulatory Commission, Washington, D.C., Octo-Nuclear Power Plants," U3NRC Report NURiiG/
- ber 1986.
CR-5007, U.S. Nuclear Regulatory Commission, Wash-ington, D.C., September 1987.
Gerber, T. l, "Fffect of Constraint and loading Mode on low Cycle Fatigue Crack initiation-Compan, son Kiss, E., lleald, J. D. and llale, D. A., " low-Cycle Fa-with Code Design Rules," Gli Report GEAP-20662, tigue of Prototypic Piping," GE Report Gl!AP-10135, General Elcetric Corporation, San Jose, CA, October General lilectric Corporation, San Jose, CA, January 1970.
1974.
Krempt,11.," low Cycle Fatigue Strength Reduction in Gorman, J.,
- Survey of PWR Water Chemistry," USNRC Notched Flat Plates," GE Report GliAP-5410, General Report NUREG/CR-Sil6, U.S. Nuclear Regulatory Electric Corporation, San Jose, CA, January 1967.
Commission, Washington, D.C., February 1989.
Krempl, !!., " Influence of Stress / Strain Concentration I
Itale D. A.," low Cycle Fatigue livaluation of Primary and Mean Stress on low-Cycle Fatigue llehavior of Piping Materials in a llWR linvironment," Gl! Report Three Structural Steels at Room Temperature," Gil Re.
Gli AP-20244, General Illectric Company, San Jose, CA, port GliAP-5726, General Electric Corporation, San September 1977.
Jose, CA, September 1968.
9 NURiiG-1426
~.
Curtpdation of lleports-1965-1990 Krempt. I!., " Notched liigh-Strain l'aligue lichavior of terly Prorress Report Apnl 1 Im m, P)S1," USNRC Three t w Strength Strutiutal Steels ' Gb Report Report NUlt! G/ Cit ':331 Vol. I No. I and 2. U.S. Nu-Gl: Al'5714, General 1 lectric Corpoiation, San Jose, clear Reputator) Commission, Washington, D.C., Janu.
CA, January 1969.
ary 198?.
Krernpl.11., "~lhe 550T Notthed ibgh-Stt,un lichavior Romano, A. J., ed., " Safety Research Programs Spon, of Three low Strength Structural Steels," Gli Report sored by Office of Nuclear Reputatory itescarch, Quar-Gl! AP-10090, General filectric Corporation, San Jose, terly Progress lleport Jul) 1-September 30, 1981,"
CA, Augutt 1969 USNRC Report NURiiG/CR-2331 Vol.1 No. 3 U.S.
Nuclear itepulatory Commission, Washington, D.C.,
Krempl, !!. "'lhe I:ffect of Str un Concentration on the hiatch 1982.
I ow-Cycle l'aligue of ihree Structural Steels at Room Temperature and 550*1'," Gli Report GEAl'10170.
Rornano, A. J," Safety Research Programs Sponsored by General 1;lectric Corporation, San Jose, CA, h1arth Office of Nuclear Reputatory Research, Quarterly Pro-1970.
rren Report October 1-Decernber 30,1981," USNRC Report NURl!G/( R-2331 Vol.1 No. 4, U.S. Nuclear Ku/ay, T, bl.,1lalle,11, J. anJ Kava, K. I!.,"Prehminary Regulatog Comniinion, Washington, D.C., July 19S2.
Review of hiaw Transfer and 110w Visuah/ation StuJies and Techniques Relevant to the Study of 11rosion.
Shack, W. J. et al., "I.ight Water Safety Research I ro.
Corrosion of Reactor Piping Syttems," USNRC Report fram: Quannly Proprm Report Apol-June 1981,"
NURI G/CR-5131 U.S. Nuclear Regulatory Commis-USNRC Report NURI:G/CR-2437 Vol.II U.S.Nuticar sion, Washmpton, D.C., June 1988.
Reputatory Commission, Washington, Dr November
- 1981, h1 aper, T. R. and h1cloughhn, V. J., "The i Ifect of an Shad W. J. et aL 1j M WaMaky Rmard Pro.
p linvirontnent of liigh Temperature Primary Grade Nu-(lear Reactor Water or the l'atigue Crack Growth Chat-ff"* U.uaunty horrew Repon July &pternbn 19%,
USNR( deport NURiiG/CR-2437 Vol. Ill, U.S. Nu.
acteristics of A533 Grade !! Class 1 Plate and Weldment hiaterial," Westinghouse Iteport WCAP-7776, Westing-clear Reputatory Commisuon, Washington, D.t,I thru-
"7 #'
house filectrie Corporation PWR Systems Division, Pittsburgh, PA, October 1971.
,y g
1 ipht Water Reactors: Critical issues and Recommended the I atigue t tack G,rowth ((ffect of l ow 1:requencies on h1 aper,.I. R. et al... lhe 1 Research," USNRC Report NURI G/CR-2541, U.S.
haracteristiesof A533 Grade Nuclear Repulatory Commission, Washincton, Uf.,
11 ( lass 11 late in an I nvironment of Iligh I emperature I.'
""U 3
Primary Grade Nuclear Reactor Water," Westmphouse Report WCAlth256, Westinghouse lilectric Corpora-gg g,
..htcasurement of Throuphwall Residual tion, Pittsburgh, PA, December 1973.
Stresses in largediameter Type 304 Stamless Steel Pip-ing llutt Weldments," ANI. Report ANI.-82-15, Ar-Nichols,1. A.,"hiechanistic A(pects of Stress-Corrosion ponne National Iahorato:y, Argonne,11, h1 arch 1982.
( rackmp of 'lype 304 Stainless Steel in 1 WH Systems,"
USNRC Report NURl:G/CR-3220, U.S. Nuclear Regu-Shack, W. J. et al., "hlaterials Science Division 1.ipht-latory Commiwion Washington, D.C., l>chruary 1983.
Water Safety Research Prograrn: Quarterly Progress Report October-December 1981," USNRC Report Par k, J. Y, and Shack, W.J., *lntergranular Crack Propa-NURI:G/CR-2437 Vel. IV, U.S. Nuclear lleputator) ration Rates in Sensitized Type 304 Stamlew Fteelin an Conmunion, Waslungton, D.C., h1ay 1982.
(hypenated Water linvironment," Argonne Report ANI A3-93. Argonne National laboratory, Argonne, Shack W. J, et al., "htaterials Science Division 1.ight-II, December 19S3-Water Safety Research Program: Quarterly Progress Report January-hiarch 1982,"
USNRC Report Park J. Y.and Kupperman, D. S.," Ultrasonic and hietal-NURI:G/CR-2970 Vol. I, U.S. Nuclear Regulaton lurgical lixamination of a Cracked 'lype 304 Stainless Commission, Washington, D C., October 1982, Steel llWR Pipe Weldment," Arronne Report ANI 1, Argonne National 1 aboratory, Arronne,11, Shack,W.J.et al.,"1 nvironmentally Assisted Crackmpin January 1954.
lapht Water Reactors: Annual Report October 19st-September 1952," USNRr Report NURI:Gl Romano, A. J., ed., " Safety Research Propiams Spon-CR-M42, U.S. Nuclear Regulatory Commiwon, Wash-sored by Ofhce of Nuclear Regulatory Research, Quar-ington, D.C, l'ebruary 1983.
NURIG-lo, 10
Cornpilatbn of 1(eports-1965-1990 i
Shack, W. J. et ah, " Materials Science and Technology Shack, W. J, et al.,"IJght4 Vater Iteactor Safety hiateri-Division 1Jght Water Reactor Safety itesearch Program:
als lingineering Research Programs: Quattetly Progress i
Quarterly Progren Report Apnl June 19S2 " USNRC llelvst Apni-June 1984," USNRC Report NURI:G/
Report NU Rl:GiCR-29'/0 Vol. II, U.S. Nuclear llegula-CR-3998 Vol. II, U.S. Nuclear Regulatory Commission, tory Commission, Washington, D.C., h1ay 1983.
Washington, D.C., l'ebruary 1985.
Shack, W, J. et al., "htaterials Science and Technology Shack,W J.etal.."linvironmentally Assisted Crackingin Ij ht Water Reactors Annual Report October Dn'ision 1Jght Water Iteactor Safety 1(esearch Program:
p
~ Progress Relvrt July-September 1982,"
1983-September 1984 " USNRC Report NURIIG/
Quartetly USNRC Report NURIIG/CR -2970 Vol.111. U.S. Nu.
CH-4287, U.S. Nuclear Regulatory Commission, Wash.
elcar llegulatory Commission, Washington, D.C., August inpton, D.C., June 1985.
- 1983, Shack, W. J. et al., "IJght Water 4cactor Safety hiateri-Shack, W. J. et al., " Materials Science and Technology als lingineermg Research Programs: Quarterly Progress "7mbu M.1,,
W K Repon Division 1Jght Water Rewtor Safety Research Program:
I""
8 oh IR, Nudm ReNatmy Quarterly l'rogress Report October-Decernber 1982
- Cmnnu. on, % aWngton, Df, Noba M5.
USNitC Report NURiiG/CR-2970 Vol. IV, U.S. Nu.
clear Regulatory Commission, Washington, D.C., No.
Shack, W. J. et al.,"IJght Water Reactor Safety hiateri-vember M3' als lingineering Research Programs: Quarterly Progress Report January-hiarch 1985 " USNRC lleport Shack, W. J. et al., " Materials Science and TechnolofJ NURl!G/ Cit-4490 Vol.1. U.S. Nuclear Regulatory Division ij ht Water Reactor Safety Research Program:
Commission, Washington, D.C., March 1986.
g Quarterly Progress Report January-March 1983 "
USNRC Repor t NUlt!!G/CR-3689 Vol.1. U.S. Nudcar Shack, W.J. et al.. "linvironmentally Assisted Crackingin Regulatory Commission, Washington, D.C., April 1984<
tj ht Water Reactors Semiannual Report April-Sep-g tember 1985 " USNRC Report NURl!G/CR-1667 Vol.
Shack. W. J. et al., " Materials Science and Technology
- 1. U.S, Nuclear Regulatory Commission Washington, Division 1.ight Water Reactor Safety Research Program:
D.C., June 1986.
Quarterly Progress lleport April-June 1983 " USNRC Report NURI!G/CR-3689 Vol. II, U.S. Nuclear Regula.
Shack,W,J.et al.,"linvironmentally Assisted Crackingin tony Commission Washington, D.C., June 1984.
1.ight Water Reactors Semiannual Report October 1985-March 1986," USNRC Report NURI!G/CR-4667 Shack,W.J.et al.,*linvironmentally Assisted Crackingin Vol.11. U.S. Nuclear Regulatory Commission. Washing.
lj ht Water Reactors: Annual Report October ton, D.C., July 1986.
g 1982-September '1983," USNRC Report NURl!GI CR-3806, U.S. Nuc! car Regulatory Commission, Wash.
Shack,W.J.et al.,"!!nvironroentally Assisted Crackingin lj ht Water Reactors Semiannual Report April-Sep-g ington, D.C., June 1984.
tember 1986," USNitC Report NURIIG/CR-4667 Vol.
Shack, W. J. et al., " Materials Science and Technology 111. U.S. Nuclear Regulatory Commission, Washington, Division Light Water. Reactor Safety Research Program:
D.C., September 1987.
Quarterly Progress Report July-September 1983,"
Shack, W.J. et al., *linvirontnentally Assisted Cracking in USNRC Report NURl!G/CR-3689 Vol. III, U.S. Nu-Ij ht Water Reactors Semiannual Report October g
clear Regulatory Commission, Washington, D.L. July 1986-March 1987 " USNRC Report NURl!G/CR-4667 i
Vol. IV, U.S. Nuclear Regulatory Commission, Washing-l ton, D.C., December 1987.
Shack W. J. et al., " Materials Science and Technology l
Division I ight-Water Reactor Safety Research Program:
Shack, W. J, et al.,"linviroruaentally Assisted Cracking in Quarterly Progress Report October-December 1983 "
1.ight Water Reactors Semiannual Report April-Sep-USNRC Report NURl!G/ Cit-3689 Vol. IV, U.S. Nu-tember 1987," USNRC Report NURI!G/CR-4667 Vol.
c! car Regulatory Commission, Washington, D.C., August V U.S. Nuclear Regulatory Commission, Washington, 1984-D.C., June 1988.
~
Shack, W. J. et al.,"I Jght Water Reactor Safety Materi.
Shack,W.J.et al.,"linvironmentally Assisted Crackingin i
als IIngineering Research Prograrns: Quar 1erly Progress lj ht Water Reactors Semiannual Report October g
Report, January-March 1984,"
USNRC Report 19S7-March 1988," USNRC Report NURiiG/CR-4667 NURIIG/CH-3998 Vol. I, U.S. Nuclear Regulatory Vol. 6, U.S. Nuclear Regulatory Commission, Washing-Commission, Washington, D.C., September 1984, ton, D.C., August 1989, i1 NURl!G-1426
Compilation of Reports-1965-1990 Shack, W. J. et al., "linvironmentally Assisted Cracking in Progress Report April 1-June 30,1983." USNRC Report lj ht Water Reactors Semiannual Report April NURl!G/CR-2331 Vol. 3 No. 2. U.S. Nuclear Regula.
g 1988-September 1988," USNRC Report NURiiG/
tory Commission, Washington, D.C., h1 arch 1984.
CR-4667 Vol. 7, U.S. Nuclear Regulatory Commission, Washington, D.C., h1 arch 1990.
Weiss, A. J., ed.," Safety Research Programs Sponsored by Office of Nuclear Regulatory Research, Quarterly Terrell, J.11., " Fatigue Strength Characterization of Progress Report July 1-September 30,1983," USNRC Smooth and Notched Piping Steel Specimens in 288'c Report NUREG/CR-2331 Vol. 3 No. 3, U.S. Nuclear Air Environments," USNRC Report NUREG/CR-5013, Regulatory Commission. Washington, D.C., July 1984.
U.S. Nuclear Regulatory Commission, Washington, D.C., April 1988.
Weiss, A. J., ed., " Safety Research Programs Sponsored by Office of Nuclear Regulatory Research, Quarterly Terrell, J. II., " Fatigue Strength of Smooth and Notched Progress Report October 1-December 31, 1983,"
Specimens of AShiU SA 106-11 Steelin PWR Environ.
USNRC Report NURIIG'CR-2331 Vol. 3 No. 4 U.S.
i ments," USNRC Report NURilG/CR-5136, U.S. Nu.
Nuclear Regulatory Commission, Washington, D.C.,
J clear Regulatory Commission, Washington. D.C., Sep.
September 1984.
tember 1988.
Weiss, A. J., ed., " Safety Research Programs Sponsored Terrell, J. II., " Fatigue Strength of ash 11! SA 106-11 by Office of Nuclear Regulatory Research, Quarterly Welded Steel Pipes in 288'C Air linvironments,-
Progress Report January 1-hiarch 31,1984," USNRC USNRC Report NUREG/CR-5195, U.S. Nuclear Regu.
Report NUREG/CR -2331 Vol. 4 No.1. U.S. Nuclear latory Commission, Washington, D.C., December 1988.
Regulatory Commission, Washington, D.C., November 1984.
Weiss, A. J., ed., " Safety Research Programs Sponsored by Office of Nuclear Regulatory Research, Quarterly
,eiss, A. J., ed., Safety Research Programs Sponsored Progress Report January 1-hiarch 31,1982 " USNRC by Office of Nuclear Regulatory Research, Quarterly Report NUREG/CR-2331 Vol. 2 No.1. U.S. Nuclear Pmgress Report April 1-June 30,1984," USNRC Report Regulatory Commission, Washington, D.C., October NUREG/CR-2331 Vol. 4 No. 2. U.S. Nuclear Regula.
- 1982, toty Commission, Washington, D.C., February 1985.
e ss. A. J., ed., " Safety Research Programs Sponsored Weiss, A. J., ed., " Safety Research Programs Sponsored by Office of Nuclear Regulatory Research, Quarterly by Office of Nuc! car Regulatory Research, QuartertY I rogress Report July 1-September 30,1984,, USNRL Progress Report April 1-June 30,1982.,, USNRC Report Report NURl!G/CR-2331 Vol. 4 No. 3, U.S. Nuclear NUREG/CR-2331 Vol. 2 No. 2. U.S. Nuclear Regula.
Regulatory Commission, Washington, D.C., hiay 1935.
tory Commission, Washington, D.C., h1 arch 1983.
Weiss, A. J., ed., " Safety Research Programs Sponsored Weiss. A. J., ed.," Safety Research Programs Sponsored by Office of Nuclear Regulatory Research, Quarterly by Office of Nuclear Regulatory Research, Quarterly Progress Report October 1-December 31, 1984,"
Progress Report July 1-September 30,1982," USNRC USNRC Report NUREG/CR-2331 Vol. 4 No. 4, U.S.
Report NUREG/CR-2331 Vol. 2 No. 3, U.S. Nuclear Nuclear Regulatory Commission, Washington, D.C.,
Regulatory Commission. Washington, D.C., April 1983.
hiay 1985.
Weiss, A. J., ed., " Safety Research Programs Sptmsored Weiss, A. J., ed., " Safety Research Programs Sponsored by Office of Nuclear Regulatory Research, Quarterly by Office of Nuclear Regulatory Research, Quarterly Progress Report October 1-December 31, 1982."
Progress Report January 1-htarch 31,1985," USNRC i
USNRC Report NUREG/CR-2331 Vol. 2 No. 4. U.S.
Report NUREG/CR-2331 Vol. 5 No.1. U.S. Nuclear Nuclear Regulatory Commission, Washington, D.C., J uly Hegulatory Commission, Washington, D.C.,
August 19S3.
1985.
i
' Weiss, A. J., ed., " Safety Research Programs Sponsored Weiss, A. J., ed., " Safety Resea ch Programs Sponsored i
l-by Office of Nuclear Regulatory Research, Quarterly by Office of Nuclear Regulatory Research, Quarterly Progress Report January 1-htarch 31,1983 " USNRC Progress Report April 1-June 30,1985," USNRC Report Report NUREG/CR-2331 Vol. 3 No. I, U.S. Nuclear NUREG/CR-2331 Vol. 5 No. 2, U.S. Nuclear Regula.
Regulatory Commission, Washington, D.C., December tory Commission, Washington, D.C., December 1985.
I 1983.
Weiss, A. J., ed., " Safety Research Programs Sponsored Weiss, A. J., ed., " Safety Research Programs Sponsored by Office of Nuclear Regulatory Research, Quarterly by Office of Nuclear Regulatory Research, Quarterly Progress Report July 1-September 30,1985." USNRC NURiiG-1426 12
. - ~
Compilation of Reports-1965-1990 Report NURl!G/CR-2331 Vol. 5 No. 3, U.S. Nuclear port January 1-June 30, 1988," USNRC Report Regulatory Commission Washington, D.C., hiarch 1986.
NURl!G/CR-2331 Vol. 8 No. I and 2. U.S. Nuclear llegulatory Commission, Washington, D.C., December Weiss, A. J., ed., " Safety Research Programs Spmsored 1988.
j by Office of Nuclear Regulatory Research, Quarterly Progress Report October 1-December 31, 1985,"
Weiss, A. J., ed.," Safety Research Programs Spmsored USNRC Report NURiiG/CR-2331 Vol. 5 No. 4, U.S.
by Office of Nuclear llegulatory Research, Quarterly Nuclear ReSulatory "o miAn. " nhington, D.C.,
Progress Report July 1-Septernber 30,1988," USNRC June 1986.
Report NURl!G/CR-2331 Vol. 8 No. 3 U.S. Nuclear Regulatory Cornmission, Washington, D.C., February "gmsored 1989.
Weiss, A. J., ed., "a by Offic of Nuch r
.Juarterly s..
ISNRC Weiss, A. J., ed.," Safety Research Programs Spmsored Progress Report ;,e Report NURiiGICl J. '
Nuclear by Office of Nuclear Regulatory Research, Quarterly
+mber Progress Report October 1-December 31, 1988,"
Regulatory Comnd r+
1986.
USNRC Reimrt NURl!G/CR-2331 Vol. 8 No. 4. U.S.
Nuclear Regulatory Cornmission, Washington, D.C., July I989' Weiss A. J., ed.,
- Safety
$. r.. Pr a..
gonsored by Office of Nuclear lu
- itm,
't.
- Qu9tterly Progress Report April 1-June 30, ho6,)USNilt ReportWeiss, A. J., ed., " Safety Research Programs S xmsored I
i NURl!G/CR-2331 Vol. 6 No. 2 U.S. Nuclear Regula.
by Oke of Nuclear Regulatory Research., Quarterly tory Commission, Washington, D.C., New mber 1986.
I,rgess %w anuary 1-blarch 31, 1989, USNRC Reput NURl!G/CR-2331 Vol. 9 No.1. U.S. Nuclear Weiss, A. J., ed., " Safety Research Programs Spmsored f979' "I
" " N "'
" August by Office of Nuclear Regulatory Research, Quarterly l
Progress Report July 1-September 30,1986," USNRC We ss, A. J., ed., " Safety Research Programs Spmsored i
Report NURiiG/CR-2331 Vol. 6 No. 3 U.S. Nuclear Regulatory Commissmn, Washmgton, D.C., h1 arch 1987.
by Office of Nuclear Regulatory Research, Quarterly Progress Report April 1-June 30,1989," USNRC Report NURl!G/CR-2331 Vol. 9 No. 2, U.S. Nuclear Regula.
Weiss, A. J., ed., " Safety Research Programs Sponsored tory Commission, Washington, D.C., December 1989.
by Office of Nuclear Regulatory Research, Quarterly Progress Report October 1-December 31, 1986."
Weiss. A. J., ed., " Safety Research Programs Simnsored USNRC Report NURiiG/CR-2331 Vol. 6 No. 4 U.S.
by Office of Nuclear Regulatory Research, Quarterly Nuclear Regulatory Commission Washington, D.C.,
Progress Report July 1-September 30,1989," USNRC htay 1987.
Report NURl!G/CR-2331 Vol. 9 No. 3, U.S. Nu-lear Reculatory Commission, Washington, D.C., February Weiss, A. J., cd., " Safety Research Programs S mnsored 1990.
i by Office of Nuclear Regulatory Research, Quarterly Progress Report January 1-htarch 31,1987," USNRC Weiss, A. J., ed., " Safety Research Programs Sponsered l
Report NURl!G/CR-2331 Vol. 7 No.1. U.S. Nuclear by Office of Nuclear Regulatory Research, Quarterly Regulatory Commission, Washington, D.C., July 1987.
Progress Report October 1-December 31, 1989,"
USNRC Report NUREG/CR-2331 Vol. 9 No. 4. U.S.
Weiss, A. J., ed., " Safety Research Programs Sponsored Nuclear Regulatory Commission, Washington, D.C.,
by Office of Nuclear Regulatory Research, Progress Re.
J une 1990.
port April 1-September 30, 1987," USNRC Report NURl!G/CR-2331 Vol. 7 No. 2 and 3, U.S. Nuclear Regulatory C ommission, Washington, D.C., June 1988.
Fracittre Mechanics: Analysis Atluri, S. N. et al.,"NO' 41.AW: A Finite filement Pro-
/
Weiss, A. J., ed., " Safety Research Programs Sponsored gram for Direct Evaluation of Sttess intensity Factors for by Office of Nuclear Regulatory Research, Quarterly Pressure Vessel Noute. Corner Flaws," USNRC Report Progress Report October 1-December 31, 1987 "
NURl!G/CR-1843, U.S. Nuclear Regulatory Comrnis.
USNRC Report NURiiG/CR-2331 Vol. 7 No. 4. U.S.
sion, Washington, D.C., hiarch 1981.
Nuclear Regulatory Commission, Washington, D.C.,
September 1988.
Atluri, S. N. et al., *OR-Fl.AW: A Fmite filement Pro; gram for Direct !! valuation of R-Factors for User.
Weiss, A. J., ed., Safety Research Programs Sponsored Defined Flaws in Plates, Cylinders and Pressure-Vessel by Office of Nuclear Regulatory Research, Progress Re.
Nonle Corner," USNRC Report NURl!G/CH-2494, 13 NURiiG-1426
..~. -
Corapitation of Reports-1965-1990 1
U.S. Nuclear Repulatory Commission. Washington, llry son, J. W. and Swinson, W, l'., "St ress Analyses of Flat D.C., April 1982.
Plates with Attached Nouless. Volume 3 I!xperimental Stress Analyses of a flat Plate with Two Closely Spaced llall, D. O, et al., *OCA-ll A Caje for Calculating lie.
Nonles of !! qual Diameter Attached," OltNI. Report havior of 2.D and 3 D Surface llaws in a Pressure Vessel ORNie5044 Vol. 3, Oak Ridge National laboratory, Subjected to Temperature and Pressure Transients,"
Oak Ridge,TN, December 1975.
USNRC Report NURiiG/CR-3491, U.S. Nuclear Repu-latory Commission, Washington, D.C., l'ebruary 1984.
Ilrywn, J. W., Johnstm, W. G., and llass,11. R.,
- Stresses in Reinforced Nonle-C)linder Attachments under Inter-flall, D. O. ct al.. "St ress intensity Factor influence Coef.
nal Pressure loadmg Analyzed by the Finite-lilement fielents for Surface llaws in Pressure Vessels," USNRC hiethod-A Parameter Study" ORNI Report ORN1/
Report NURl!G/CR-3723, U.S. Nuclear Regulatory NURIIG-4, Oak Ridge National laboratory, Oak Ridge, Commission, Washington, D.C., February 1985.
TN, October 1977.
lityson, J. W., Johnson, W. G., and llass,11 it.," Stresses o
I A 1,' a I r bi is e ur [Me han in Reinforced Nonle-Cylinder Attachments under lix-
, to omendyadmgs Analyzed by the Finite Illement mna Personal Compulcr," USNRC Report.
Method-A NURIIG/
1 arameter Study, USNRL Report
(,R-4468. U.S. Nuclear Regulatory Commission, W, ash-ington, Di., January 1986, NURiiG/CR-0506, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., August 1979.
Ilass,11. R.andIhyson,J.W.,"ORMGl N-3D: A Finite lityson, J. W., "ORVIRT.PC: A 2 D Finite lilement Element Mesh Generator for 3 Diment.ional Crack Ge-Fracture Analysis Program for a Microcomputer,"
ometries," USNRC Report NUREG/CR-2997, Vol.1.
USNRC Report NURl!G/CR-4367, U.S. Nuclear Regu-U.S. Nuclear Regulatory Commission, Washington, latory Commission, Washington, D.C., October 1985.
D.C., December 1982.
Ilryson, J. W. and llass,11. R., "ORMGliN.PC: A Micro, llass,11. R. and lityson, J. W., "ORVIRT: A Finite lile-computer Program for Automatic Mesh Generation of ment Program for I!nergy Release Rate Calculations for 2.D Crack Geometries," USNRC Report NURl!G/
2-Dimensional and 3. Dimensional Crack Models,"
CR-4475, U.S. Nuclear Regulatory Commission, Wash-USN R C R eport N U Rl!G /CR-2997, Vol. 2, U.S. Nuclear ington, D.C., March 1986.
Regulatory Commission, Washington, D.C., February 1983.
Callahan. J. P., and Greenstreet, W. l. "lixperimental and Analytical Investigations of the Structural llehavior llattiste, R L et al.," Stress Analyses of Flat Plates with of Noule to-Shell Attachments," ORNI. Report Attached Nonless, Volume 2 Experimental Analyses of a ORNI/fM-4163, Oak Ridge National I ahoratory, Oak Flat Plate with One Nonle Attached," ORNI. Report Ridge, TN, August 1973.
ORNI.-5044 Vol. 2. Oak Ridge Nanonal laboratory, Ook Ridge, IN. July 1975 Cheverton, R. D., Iskander, S. K., and 11011, S. I!.,"Appli-cability of I liFM to the Analysis of PWR Vessels Under I
licitch, L and North,11. l,
- PAPA-The Digital Com-1.OCA-l!CC Thermal Shock Conditions," USNRC Re-puter Program for the Static Analysis of Structures Made port NURiiG/L R-0107, U.S. Nuclear Regulatory (,om.
l mission, ashmpton, D.C., October 197h.
Up of Plate and Panet lilements," Gli Report GliAP-5553, General Illectric Corporation, San Jose, Cheverton, R. D., Iskander, S. K., and llall, D. G. "PWR
( A, October 1967.
Pressure Vessel Integrity During Overcooling Accidents:
A Parametric Analysis," USNRC Report NURl!G/
llellucci, H.J.. "Three Dimensional IIlastic-Plastic Stress CR-2895, U.S. Nuclear Regulatory Commission, Wash-and Strain Analyses for Fracture Mechanics: ( omplex ington, D.C., February 1983.
' Geomet rics," M ARC Report No.09177 (FR 75), M ARC, Palo Alto, CA, November 1975.
Cheverton, R. D. and Itall D. G.. "OCA-P A Determi-nistic and Probabilistic Fracture Mechanics Code for llryson, J. W., Callahan, J. P., und Gwaltney, R. C.,
Application to Pressure Vessels," USNRC Report
" Stress Analyses of Flat Plates with Attached Nonles.
NURliGK R-3618, U.S. Nuclear Regulatory Commis-Volume 1 Comparistm of Stresses in a One-Nonle to-sion. Washington, D.C., May 1984.
Flat Plate Configuration and in a Two-Noule Configura-tion with Theoretical Predictions," ORNI Report Dickson T. L. Cheverton, R. D., and Shum, D. R.,"in-ORNI.-5044 Vol.1. Oak Ridge National laboratory, clusion of Unstable Ductile Tearing and litrapolated Oak Ridge.TN, July 1975.
Crack Arrest Toughnew Data in PWR Vessel Integrity NURiiG-1426 14
Compilation of Reports-1965-1990 l
Assessment," USNRC Report NURl!G/CR-5473 U.S.
I racture-Safe Design," NR1, Report 6913, Naval Re.
Nuclear Regulatory Commission, Washington, D.C.,
search laboratory, Washington, D.C., April 1969.
hiay 1990.
I ass, F J., llawthorne, J. R., and Serpan, Jr., C. Z., " A Grav R. A. and loss, F. J., " Fracture Safety Considera.
Reassessment of Fracture-Safe Operating Criteria for tion's for HanfordN Reactor Coolant Piping," NRI. Re.
Reactor Yessel Steels llesed on Charpy-V Perform-port 7439, Naval Research laboratory, Washington, ance," NRI. Report 7152, Naval Research laboratory, D.C., August 1972.
Washington, D.C., September 1970.
n nec ng cana c4 pa%al and Inversini, C, and lin' son, J.
W., "ORPLOT.PC: A mpe" u
n uc ctum Manies Wu$nen Graphic Utility for O'Rh1GIIN.PC and ORVIRT.PC,.
metuM* Anumny,,, M.
1353, Nas.al Research laboratory, W ashington,Q.C.,
t
"* on USNRC Report NUREG/CR 4633, U.S. Nucicar ReEu-D latory Commission, %,ashington, D.C., June 1( bo.
December 1971.
Irwm, G. R. et al., "llasic Aspects of Crack Gru,. nd Loss, F. J., Ilawthorne, J. R., and Pelhni, W. S., "Gener-Fracture," NRL Report 6598, Naval Research Iabora-alized Procedures for the Use of Plane Strain and Elastic tory, Washington, D.C., November 1967.
Plastic I racture hicchanics Options in the blodernization of Nuclear Standards," NRI. Report 7603, Naval Re-Iskander, S. K., "Two Finite Element Techniques for scarch laboratory, Washington, D.C., September 1973.
Cemputing hiode i Stress Intensity Factors m Two-or Three-Dimensional Problems " USNRC Report l oss, F. J., Gray, J r., R. A., and llawthorne, J. R., "Sig-NUR!!G/CR-1499, U.S. Nuclear Regulatory Commis.
nificance of Warm Prestress to Crack initiation Durmg sion, Washington, D.C., February 1981.
Thermal Shock," NRL Report 8165, Naval Research laboratory, Washington, D.C., h1 arch 1977.
Iskander, S. K., Cheverton, R.
D., and llall, D. G"
- OCA-l. A Code for Calculating the llehavior of Flaws I oss, F, J., " Concepts of Fracture hicchan es and Struc-
,' NRL RW 8085 Naval Research on the Inner Surface of a i ressare Vessel Subjected to lh Washington, D.C., h1 arch 1977.
femperature and Pressure fransients, USNRC Report NURl!G/CR-2113, August 1981.
hierkle, J. G., Kooistra, L F., and Derby, R. W., " Inter-pretations of the Drop Weight Test in Terms of Strain Joyce, J. A. and Ilackett, I!. hl., " Development of an En-Tolerance (Gross Strain) and Fracture hicchanies,"
gineering Definition of the lixtent of J Singularity Con-USAEC Report ORNL-Tht-3247, Oak Ridge National trolled Crack Growth," USNRC Report N U Rl! G /
1 aboratory, Oak Ridge, TN, June 1971.
CR-5238, U.S.
Nuclear Regulatory Commission, Washington, D.C., hiay 1989.
hierkle, J. G.,"A Review of Some of the Existing Stress Intensity Factor Solutions for Part-Through Surface Krishnamurthy, N.,"Three Dimcnsional Finite Element Cracks," USAliC Report ORNL-Thl. 3983, Oak Ridge Analysis of ThickWalled Vessel-Nozzle Junctions With National laboratory, Oak Ridge, TN, January 1973.
Curved Transitions," US AEC Report ORNL-Tst-3315.
Oak Rid e National laboratory, Oak Ridge, TN, July hierkle, J. G., "An Elastic-Plastic Thick-Walled llollow b
1971.
Cylinder Analogy for Analyzing the Strains in the Plastic Zone Just Ahead of a Notch Tip," USAEC Report Levy, N. and h1arcal, P. V., "Three-Dimensional Elastic.
ORNL-Tht-4071, Oak Ridge National !ahoratory, Oak Plastic Sttess and Stram Analysis for Fracture hicchanies, Ridge, TN, January 1973.
Phase I: Simple Flawed Specimens," llrown Report HSSTP-TR-1., llrown University, Providence, RI, hierkle, J. G., " Analytical Relations lletween Elastic-p p
g ORNL Report ORNI)
December 1970.
NUREG/fht-27, Oak Ridge National laboratory, Oak Ridge, TN, July 1976.
Levy, N. and h1arcal, P, V., "Three-Dimensional lilastie-Plastic Stress and Strain Analysis for Fracture hicchanics, hierkle, J. G.,"An Approximate hiethod of Elastic-Plas-Phase II: Improved N1odelling "Ilrown Report HSSTP-tic Fracture Analysis for Nonle Corner Cracks " USNRC TR-17, llrown University, Providence, R1, November Report NUREd/CR-0472. U.S. Nuclear Regulatory 1971-Commission, Washington, D.C., December 1978.
l oss. F. J. and Pellini, W. S., " Coupling of Fracture N1e-hierkle, J. G, "An Overview of the inw-Upper-Shelf chanics and Transition Temperature Approaches to Toughness Safety hlargin issue," USNRC Report 1
15 NUREG-1426
Compilation of Reports-1965-1990 NUREG/CR-5552 U.S. Nuclear Regulatory Commis.
Simonen, E. P., Johnson, K. I., and Simonen, F. A., "Ves.
sion, Washington, D.C., August 1990.
selIntegrity Simulation Analysis (VISA) Code Sensitivity Study," USNRC Report NUREG/CR-4267, U.S. Nu-North, E. L,
- PAPA-Structural Analysis of Plates and clear Regulatory Commission, Washington, D.C., De-Shells Using Trapezoidal and Triangular Plate lile-cember 1985, ments," GE Report GEAP-5471, General lilectric Cor-poration, San Jose, CA, March 1967.
Simonen, E. P. et al., " VISA-II Sensitivity Study of Code Calculations: Input and Analytical blodel Parameters,"
Pedersen, L T, et al.,"PNLTechnical Review of Pressur-USNRC Report NUREG/CR-4614, U.S. Nuclear Regu-ized Thermal. Shock issues (PWR)," USNRC Report latory Commission Washington, D.C., November 1986.
NUREG/CR-2837, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., July 1982.
Simonen, F. A.,"The impact of Nondestructive Examina-tion Unreliability on Pressure Vessel Fracture Predie-Pedersen, L T. et al., *PNLTechnical Review of Pressur-tions,"USNRC Report NUREG/CR-3743 U.S. Nuclear ized The: mal-Shock issues, Supplement 1: Technical Regulatory Commission, Washington, D.C., May 1984.
Critique of the NRC Near Term Screening Criteria,"
USNRC Report NUREG/CR-2837, Supplement 1, U.S.
Simonen, F. A. and Woo,11. H.," Analyses of the Impact Nuclear Regulatory Commission, Washington, D.C.,
of Inservice Inspecion Using Piping Reliability Model,"
May 1983.
USNRC Report NUREG/CR-3869, U.S. Nuclear Regu.
latory Commission. Washington, D.C., August 1984.
Pellini, W. S. and less, F. J., " Integration of Metallurgi-cat and Fracture Mechanics Concepts of Transition Tem.
Simonen, F. A. et al.," Reactor Pressure Vessel Failure perature Factors Relating to Fracture Safe Design for Probability F_ ollowingThrough Wall C racks Due to Pres-Structural Steels," NRL Report.6900, Naval Research surized Thermal Shock ' hvents,_ USNRC Report laboratory, Washington, D.C., April 1969.
NUREG/CR-4483, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., April 1986.
Purak, P. P. and less, F. J., " Metallurgical and Mechani-Simonen, F. A. et al., VISA-II: A C,omputer Code for cal Considerations in Selection of a Fracture-Safe Exp'o-sives Containment Vessel,"NRL Report 7354, Naval Re-Predicting the Probability of Reactor Pressure Vessel search laboratory, Washington, D.C., January 1972.
Failure, USNRC Report NUREG/CR-4486, U.S. Nu-clear Regulatory Commission, Washington, D.C., March Ritze, G, O.," Restart for the PAPA Program," GE Re.
port GEAP-10007, General Electric Corporation, San Smith, C. W., Jolles, M., and Peters, W. I1., " Stress Inten -
Jose., CA, March 1969, sities for Nozzle Cracks it. Reactor Vessels," VPl Repor t Rodabargh, E. C., O'Hara, F. M. and Moore, S. E.,
VPI-E-76-25 (ORNJJSUH/7015-1), Virginia Polytech-i' nic Institute and State University, Blacksburg. VA, No-
" FLANGE: A Computer Program for the Analysis of vember 1976.
Flanged Joints with Ring-Type Gaskets," ORNL Report ORNL-5035, Oak Ridge National Laboratory, Oak Smith, C, W. et al., " Stress Intensity Distributions in Noz-
- Ridge, TN, January 1976.
zie Corner Cracks of Complex Geometry " USNRC l
Report NUREG/CR-0640, Washington, D.C., January Rodabaugh, E. C and Moore, S. E " Flexibility Factors 1979.
for Small (d/D < 1/3) Branch Connections with External Loadino,s," ORNL Report GRNIJSub/2913-6, Oak Stevens, D. L et al.,"VIS A: A Computer Code for Pre-Ridge Nationallaboratory, Oak Ridge,TN, March 1977, dicting the Probability of Reactor Pressure-Vessel Fail.
ure," USNRC Report NUREG/CR-3384 U.S. Nuclear Sauter, A., Cheverton, R. D., and Iskander, S. K.," Modi-Regulatory Commission, Washington, D.C., September fication of OCA-1 for App.lication to a Reactor Pressure 1983.
Vessel with Cladding on the Inner Surface," USNRC Re-port NURLIG/CR-3155, U.S. Nuclear Regulatory Com-Stonesifer, R. IL, Rybicki, E. F., and McCabe, D. E.,"De-mission, Washington. D.C., M:iy 1983.
velopment of Models for Warm Prestressing," USNRC -
Report NUREG/CR-4491 U.S. Nuclear Regulatory Schwartz, C. W. et al., "SAMCR: A Two-Dimensional Commission, Washington, D.C., January 1987, Dynamic Finite Element Code for the Stress Analysis of Moving Cracks," USNRC Report NUREG/CR-3891, Stonesifer, R.11., Rybicki, E. F., and McCabe, D. E.,
U.S. Nuclear Regulatory Commission, Washington,
" Warm Prestress Modeling: Comparison of Models and D.C., November 1984.
Experimental Results," USNRC Report NURiiG/
NUREG-1426 16
~
Compilation of 11eports-1965-1990 C11-5208, U.S. Nuclear llegulatory Commission, Wash-Ilryan,it i1. et al.," Test of 6 in.Jihick Pressure Vessels.
ington, D.C., April 1989 Series 3: Intermediate Test Vessel V-7H " USNRC lle-port NUltliG/ Cit-0309 U.S. Nuclear llegulatory Com-Tso, P. K. W. et al.," Stress Analysis of Cyhndrical Pics.
mission, Washington, ItC., October 1978.
sure Vessels with Closely Spaced Nonles by the 1:inite-Bryan,11. I1. et al.,"'I.est of (s.n.-Ihick Pressure Vessels, I!!cment hiethod, Volume i Stress Analysis of Vessels Ser es 3: Intermediat e Test Vessel V-8," USNitC ileport with Two Closely Spaced Nonles Under internal Pres-NUltl!G/ Cit 0675, U.S. Nuclear llegulatory Commis-sure, OltNI. lleport OltNIJNUlt!!G-18/VI, Oak Mon, Washington, D.C., December 1979.
Itidge National laborato.y, Oak Itidg?, TN, November g.an, R. II. et al.," Pressurized / thermal. Shock Test of 1977.
g 6 in. 'lhick Pressure Vessels. PIS!!-1: Investigation of Tso, l'. K. W. and Weed,11. A.," Stress Analysis of Cylm-Warm Prestressing and Upper-Shelf Arrest," USNitC drical Pressure Vessels with Closely Spaced Noutes by iteport NUlti:G/Cib4106, U.S. Nuclear Regulatory the Hnite-l!!cment hiethod, Volume 2 Vessels with Two Commission, Washington, D.C., April 1985.
Closely Spaced Nonles Under lixternal 1 orce and hio-ment Icadmgs," USNitC Report NUltliG/ Cit-0132, liryan, R. I1. et al.," Test of 6 in. Thick Pressure Vessels.
U.S. Nuclear Regulatory Commission. Washington, Series 3: Intermediate Test Vessel V-8A-Tearmg Ile-D.C., August 1978, havior of low Upper Shelf N1aterial," USNitC lleport NURiiG/CR-4760, U.S. Nuclear llegulatory Commis-Tso,l'. K.W. and Weed,it. A.," Stress Analysis of Cylin, sion, Washington, D.C., hiay 1987, drical Pressure Vessels with Closely Spaced Noules by llrvan, it.11. et al., " Pressurized. Thermal-Shock Test of the l'inite lilement hiethod, Volume 3 Vessels with 6-in.-Thick Pressure Vessels. l'i'Sli-2: Inve::tigation of ihree Noules Under Internal Pressme and lixternal I w Teanng flesistance and Warm Prestressing,"
l oadmgs, USNRC Report NUltl!GICR-0507 Vol. 3, USN11C iteport NUlti!G/ Cit-4888, U.S. Nuclear Regu-U.S. Nuclear Regulatory Commission, W ashington, la Co io WW ton, ILC, DmM 1987.
ILC., hiay 1979.
Cheverton, R. D.. " Pressure Vessel tiracture Studies Per-Visser, C., Gabrielse, S. li, and Vanlluren W.,"ATwo-taining to a PWR 1,0CA -liCC 'lhermal Shock: lixperi-Dimmsional lilastic-Plastic Analysis of Uracture Test ments TSli--I and TSli-2," OltNI. Iteport ORNil Specimens," Westinghouse Report WCAP-7368. Wes-NURiiG/I'ht-31. Oak Ridge National laboratory, Oak tinghouse lilectric Corporation, PWR Systems Division, Ridge, TN., September 1976.
Pittsburgh, PA, October 1969.
Cheverton, R. D. and flolt, S. li, " Pressure Vessel lirac-ture Studies Pertaining to a PWR 1.OCA-l!CC'lhermal Yukawa, S., "livaluation of Periodic Proof Testing and Shock: lixperiments TSliy and TSli-4 arid Update of Warm Prestressing Procedures for Nuclear Reactor Ves-I'Sli-1 and TSli-2 Analysis," ORNI. Repon OltNIJ sets," Gli Report ilSSTP-TR-1, General !!!cctric Com-NURliG-22, Oak Ridge Nanonal laboratory, Oak pany, Schenectady, NY, July 1,1969.
Ridge, l'N, December 1977.
Cheverton, R. D. and 1skander, S. K., " Application of I,racture Mechan,ics: la, pen. mental-Static and Dynamic Crack Arrest ' theory to TSli-4,"
Component l'estmg USNRC Report NURl!G/CR-0767, U.S. Nuclear Regu-latory Commission, Washington, D.C., June 1979, Abbatiello, A. A. and Derby, R. W.," Notch Sharpening in a large Tensile Specimen by I ceal Fatigue," US AliC Cheverton, R. D. et al., " Pressure Vessel Fracture Stud-Report OltNIcThi-3925, Oak Ridge National Iabora-ies Pertaining to the PWR Thermal-Shock Issue: Experi-tory, Oak Ridge, TN, November 1972.
ments TSli-5, TSli-5A and TS!!-6," USNRC Report NURiiG/CR-4249, U.S. Nuclear Regulatory Commis-Mon, Washington, D.C., June 1985.
Ilryan, R. I1. et al., "l'est of 6-inch /lhick Pressure Ves-sets. Series 2: Intermediate Test Vessels V-3, V-4, and Cheverton. R. D et al., " Pressure Vessel 1;racture Stud-V-6," ORNI. Re!7 ort ORN1c5059, Oak Ridge Natl' ies Pertaining to the PWIClhermal-Shock issue: lixperi-lab., Oak Ridge, I enn., November 1975, ment TSli-7," USNRC Report NUltliG/Cib4304, U.S.
Nuclear Regulatory Commission, Washington, D.C.,
Hryan, it I1. et al.," Test of 6-in..'lhick Pressure Vessels-August 1985.
Series 3: Intermediate Test Vessel V-7A Under Sus-tained I cading," OR N I. Report OR N I /N U R1!G -9, Oa k Cheverton, R. D. and llall, D. G., " A l'arametric Study of Ridge Nati. I ab., Oak Ridge, Tenn., February 1978.
PWR Pressure Vesselintegrity During Overcooling Acci-17 N1IRl!G-1426
Compilation of Reports-1965-1990 dents, Considering floth 2-D and 3 D l' laws," USNRC llSSTP-TR-18, Southwest Research Institute, San An-Report NURl!G/CR-4325, U.S. Nuclear Regulatory tonio, TX, June 1972.
]
Commission, Washington, D.C., August 1985.
Grigory, S. C., " Tests of 6-Inch /lhick Flawed Tensile Corwin, W. R. et al., "liffects of Stainless Steel Weld Specimens, Second Technical Summary lleport, Trans-Overlay CladJing on the Structural Integrity of Ilawed verse Specimens Numbers 8 Through 10, Welded Speci-Steel Plates in llending, Series 1," USNRC Report mens Numbers il 'lhrough 13 " SWRI Report ilSSTP-NURl G/CR-4015, U.S. Nuclear Regulatory Commis-TR-20, Southwest Research Institute. San Antonio,TX, sion, Washington, D.C., April 1985.
June 1972.
]
Corwin, W. R., "licaspSection Stect Technology Pro-Grigory, S. C., " Tests of 6-Inch /ihick Flawed Tensile gram Semiannual Progress Report for April-September Specimens,' third Technical Summary Report, Ixmgitu-1987," USNRC Report NURiiG/CR-4219, Vol 4, No. 2, dmal Specimens Numbers 14 Through 16, Unflawed U.S. Nuclear Regulatory Commission, Washington, Pjecimen Number 17," SWRI Report llSSTP-TR-22, D.C., April 1988-Southwest Research Institute, San Antonio,TX, October 1972.
Corwin, W. R., "llcavy-Section Steel Technology Pro-gram Semiannual Progress Report for October Grigory S. C.,
- Tests of 6-InchJihick Tensile Specimens, 1987-March 1988," USNRC Report NURiiG/CR-4219, Fourth Technical Summary Report, Tests of 1-inch.
Vol 5, No.1, U.S. Nuclear Regulatory Commission,
'ih ck Flawed Tensile Specimens for Size liffect livalu-Washington, D.C., August 1988.
ation " SWRI Report ilSSTP-TR-23, Southwest Re-Corwin, W. R., "lleavy-Section Steel Technology Pro-gram Semiannual Progress Report for Apnt-September 1988," USNRC Report NURl!G/CR-4219. Vol 5, No. 2, Grigory, S. C., "Heasy Section Steel Program Tests of
- 6. Inch-Thick Tensile Specimens, Sixth Technical Sum-U.S. Nuclear Regulatory Commission, Washington, D.C., April 1989' mary Report," SwRI Project 03-2520, Southwest Re-search Institute, San Antonio, TX, April 19,1974.
Corwin, W. R., "llcavy-Section Steel Technology Pro-gram Semiannual I rogress Report for October Holz, P. I'. and Wismer, S. W.,"Ilalf Ilead (l'emper) Re-1988-March 1959," USNRC Report NURl!G/CR-4219, pair %,elding for iISS'l, Vessels,,, USNRC Report Vol 6, No.1. U.S. Nuclear Regulatory Commission, NURl!G/CR-Oll3, U.S. Nuclear llegulatory Commis-mn, a
gton, M, June M Washington, D.C., August 1989.
Derby, R. W, et al., " Test of 6-Inchilhick Pressure Ves-I loli, P. P., " Flaw Preparations for i ISST Program Vessel sels. ' Series 1: Intermediate Test Vessel; V-1 and V-2 "
Fracture Mechames l'estmg; Mechanical Cyclic Pumping ORNI. Report ORNL-4895, Oak RiJge National taba_
and lilectron-lleam Weld-llydrogen Charge Crackmg ratory, Oak Ridge, TN, February 1974.
Schemes," USNRC Report N URl!G/CR-1274, U.S. Nu-clear Regulatory Commission, Washington, D.C., May 1980.
Domian, H. A., " Vessel V-8 Repair and Preparation of I ow Upper Shelf WelJment," USNRC Report NURiiG/
CR-2676, U.S. Nuclear Regulatory Commission, Wash.
Mager, T. R., Yanichko, S. ii., and Singer, I., R., " Frac-ington, D.C., June 1982.
ture Toughness Characterization of IISST Intermediate Pressure Vessel Material," Westinghouse Report Domian,11. A., " Vessel V-7 and V-8 Repair and Charac.
WCAP-8456, Westinghouse Electric Corporation, Pitts-terization ofInsert Material," USNRC Report NURl!G/
burgh, PA, December 1974.
CR-3771, U.S. Nuclear Regulatory Commission, Wash-ington, D.C., May 1984.
Merkle, J. G., Whitman, G. D., and Bryan, R. II., "An livaluation of the llSST Program Intermediate Pressure Dorr ian, H. A., "Inw Upper-Shelf Toughness, liigh Vessel Tests in Terms of i.ight-Water-Reactor Pressure Transition Temperature Test insert in llSST ITSl!-2 Vessel Safety," ORNI. Report ORN1/l'M-5090, Oak Vessel and Wide Plate Test Specimens," USNRC Report Ridge National Iahoratory, Oak Ridge, TN, November NUREGiCR-4711. U.S. Nuclear Regulatory Commis.
1975.
sion, Washington, D.C., February 1987.
Merkle,J. G. et al.," I est of 6-In.-Thick Pressure Vessels.
Grigory, S. C., " Tests of 6-in./lhick Flawed Tensile Series 3: Intermediate Test Vessel V-7," ORNI. Report Specimens, First Technical Summary Report, l.ongitudi-ORNIJNUREG-1, Oak Ridge National laboratory, nal Specimens Numbers 1 Through 7 " SWR! Report Oak Ridge, TN, August 1976.
NURiiG-1426 18
Compilation of Reports-1965-1990 hierkle,J. 0, et al.," Test of 6.In. 'lhick Pressure Vessels.
Nuclear Regulatory Commission. Washington, D.C.,
Series 4: Intermediate Test Vessels V-5 and V 9 with In-June 1984.
side Nonle Corner Cracks," Ol(NI Report ORNil NUR110-7, Oak Ridge National I ahoratory, Oak Ridge, Pugh, C.11., *lleavy-Section Steel Technology Program Semiannual Progress Report for April-September 1984,"
TN, August 1977.
USNRC Report NU Rl!G/CR-3744, Vol. 2, U.S. N uclear Naus, D. J. et al.," Crack Ariest llehavior in SliN Wide Regulatory Commission, Washington, D.C., December 1984-Plates of Quenched and Tempered A 533 Grade 11 Steel Tested Under Nonisothermal Conditions," USNRC Re-Pugh, C.11., *lleasy-Section Steel Technology Program port NURl!G/CR-4930, U.S. Nuclear Regulatory Com.
Semiannual Progress Report for October 1984-hlarch mission Washington, D.C., August 1987.
1985," USNRC Report NURI:G/CR-4219, Voi.1, U.S.
Nuclear Regulatory Commission, Washington, D.C.,
Naus, D. J., Keency Walker, J., and llass,11. R., *1bgh-June 1985.
Temperature Crack Arrest llehasior in 152-mm-Tinck Sl!N Wide Plates of Quenched and Tempered A 533 Pugh, C.11 *licasy-Section Steel Technology I'rogram Grade H Class 1 Steel," USNRC Report NUREG/
Semiannual Progress Report for April-September 1985,"
CR-5330 U.S. Nuclear Regulatory Comnussion, Wash-USNRC Report NURIIG / Cit-4219, Vol. 2, U.S. N uclear ington, D.C., April 1989.
Regulatory Commission Washington, D.C., January Naus, D. J. et al., "SliN Wide Plate Crack-Arrest Tests Using A 533 Grade 11 Class 1 Material: WP-CliTest Se-Pugh, C. li., "llcavy-Section Steel Technology Program rics," USNRC Report NURl!GlCR-5408, U.S. Nuclear Semiannual Progress Report for October 1985-March Regulatory Commission, Washington, D.C., November 1986," USNRC Report N URl!G/CR-4219, Vol. 3, No.1, 1959.
U.S. Nuclear Regulatory Commission, Washington, D.C., June 1986.
Naus, D.J. et al.,"1ligh-Temperature Crack-ArrestTests Using 152 mm-Thick S!!N Wide Plates of low-Upper-Pugh, C.11., "llcavy Section Steel Technology Program Shelf liase Material: Tests WP-2.2 and WP-2.6,"
Semiannual Progress Report for April-September 1986,"
USNRC Report NUREGICR-5450, U.S. Nuclear Regu-USNRC Report NURl!G/CR-4219, Vol 3, No. 2, U.S.
latory Commission, Washington, D.C., l'ebruary 1990.
Nuclear Regulatory Commission, Washington, D.C., De-cember 1986.
Pugh, C. li," Quarterly Progress Report on the llcavy-Pugh, C. !!., " Heavy-Section Steel Technology Program Section Steel Technology Program for January-March 1983," USNRC Report NUREG/CR-3334, Vol.1. U.S.
Semiannual Progress Report for October 1986-March Nuclear Regulatory Commission, Washington, D.C.,
1987," USNRC Report NU R EG/CR-4219, Vol 4, No.1, U.S. Nuclear Regulatory Commission, Washington, September 1983.
D.C., August 1987.
Pugh, C.11.," Quarterly Progress Report on the Heavy-Robinson, G. t,.,, Discussion of SwRI Model Parametric Section Stee Technology Program for April-June 1983,"
.l'ests," USAEC Report ORN!-TM-3313, Oak Ridge USNRC Report NURiiG/CR-3334, Vol. 2, U.S. Nuclear National l aboratory, Oak Ridge, l'N, June 1971.
Regulatory Commission, Washington. D.C., December I983' Segaser, C.1-," System Design Description of the Inter-mediate Vessel Tests for the !! cavy Section Steel Tech-Pugh, C.11.," Quarterly Progress Report on the lleavy-nology Program," USAEC Report ORNieTM-2849, Section Steel Technology Program for July-September Revised, Oak Ridge National laboratory, Oak Ridge, 1983," USNRC Report NURl!G/CR-3334, Vol. 3, U.S.
TN, July 1973.
Nuclear Regulatory Commission, Washington, D.C.,
March 1984.
Smith, G. C., Ilotz, P. P., and Stelzman, W. J., " Crack lix-tension and Arrest Tests of Axially Flawed Steel Model Pugh, C.11. et al., "lleavy-Section Steel Technology Pro-Pressure Vessels," USNRC Report NURiiG/CR-0126, gram-Five-Year Plan FY 1983-1987," USNRC Report U.S. Nuclear Regulatory Commission, Washington, NUREG/CR-3595, U.S. Nuclear Regulatory Commis-D.C., October 1978.
sion, Washington, D.C., Apri! 1984.
Whitman, G. D. and Witt, F. J., "licavy Section Stect Pugh, C. E, " Heavy-Section Steel Technology Program Technology Program," USAEC Report ORNic Semiannual Progress Report for October 1983-March TM-3055, Oak Ridge National laboratory, Oak Ridge, j
1984," USNRC Report NURl!G/CR-3744, Vol.1, U.S.
TN, November 1970.
19 NURl!G-1426
Compilation of Reports-1965-1990 i
Whitman, G D.,"licasy-Section Steel Technology Pro-Whitman, G. D., " Quarterly Progress Report on the
- gram Semiannual Progress Report for Period finding Ileasy Section SteelTechnology Program fot April-June August 31, 1973," USAEC Report ORNL-4971, Oak 1976," ORNL Report ORN!/NUREG/FM-49, Oak Ridge National laboratory, Oak Ridge, TN, July 1974.
Ridge National laboratory.- Oak Ridge, TN, October 1976.
Whitman, G. D.," Quarterly Progress Report on Reactor Safety Programs Sponsored by the Division of Reactor Whitman, G. D., " Quarterly Progress Report on the Safety Research for April-June 1974, 'lleavy-Section licavy-Section Steel Technology Program for July-Steel Technology Program',' ORNL Report ORNL-.
September 1976," ORNL Report ORNIJNUREG/
TM-4655, Vol. 2. Oak Ridge National Iaboratory, Oak TM44. Oak Ridge National laboratory, Oak Ridge, TN, Ridge, TN, A" gust 1974.
January 1977.
Whitman, G D.. " Quarterly Progress Report on Reactor Whitm n, G. D., " Quarterly Progress Report on the Safety Programs Sponsored by the Division of Reactor Heapectmn Ste,el rechnology Program for October-December 1976, ORNL Report ORN!JNUREG/
Safety Research' for July-September 1974, 'lleavy-Section Steel Technology Program *," ORNL Report ak Ridge National laboratory, Oak Ridge, IN, ORNL-TM-4729 Vol. 2 Oak Ridge National labora-P tory, Oak Ridge,TN, November 1974.
Whitman, G. D., " Quarterly Progress Report on the Whitman, G. D.," Quarterly Progress Report on Reactor licavy-Section Sicel Technology Program for January-Safety Programs Sponsored by the NRC Division of Reac.
March 1977," ORNL Report ORN1JNUREG/FM-120, Oak Ridge National Iahoratory, Oak Ridge, TN, Sep-tor Safety Research for October-December 1974, tember 1977,
'licavy-Section Steel Technology Program'," ORNL Re-port ORNL-TM-4805, Vol. 2, Oak Ridge National l abo-Whitman, G. D., " Quarterly Progress Report on the ratory, Oak Ridge, TN, March 1975.
Ileavy Section SteelTechnology Program for April-June 1977," ORNL Report ORNIJNUREG/FM-147, Oak Whitman, G. D.," Quarterly Progress Regwrt on Reactor Ridge National laboratory, Oak Ridge, TN, December Safety Programs Sponsored by the NRC Division of Reac-
- 1977, tor Safety Rascarch for January 41 arch 1975, 'lleavy-Section Steel Technology Program'," ORNL Report Whitman, G. D. and Ilryan, R.11., " Quarterly Progress ORNL-TM-4914, Vol. 2 Oak Ridge National Iahora-Report on the ficavy-Section Steel Technology Program 4
tory, Oak Ridge, TN, June 1975, for -July-September 19777 ORNL Report ORNtJ NUREG/FM-166, Oak Ridge National Iaboratory, Oak Whitman, G D.," Quarterly Progress Report on Reactor Ridge, TN, April _1978.
Safety Programs Sponsored by the NRC Division of Reae-tor Safety Research for April-June 1975,'lleavy-Section Whitman, G. D. and llryan, R. II., " Quarterly Progress Steel Technology Program',"
ORNL Report Report on the ficavy-Section SteelTechnology Program ORNic5021, Vol. 2, Oak Ridge National laboratory, for October-December 1977," ORNL Report ORNI)
Oak RiJge, FN, September 1975.
NUREG/l M-194, Oak Ridge National laboratory, O.
Ridge, TN, May 1978.
Whitman, G. D., " Quarterly Progress Report on the licavy-Section atcel I,echnology Program for July-Whitm:m, G. D, and liryan, R.11., " Quarterly Progress September 1975 " ORNL Report ORNLJI M-5170, Oak Report on the Heavy-Section SteelTechnology Program I
e National laboratory, Oak Ridge, FN, January for January-March 1978,".USNRC Report NUREG/
CR-0106, U.S. Nuclear Regulatory Commission, Wash.
ington, D.C., Jt.ly 1978, I
l' Whitman, G, D., " Quarterly Progress Report on the Whitman, G. D. and firyan, R. II., " Quarterly Progress licavy-Section Steel Technology Program for October-Report on the lleavy-Section Steel Technolog's Program l-l December 1975," ORNL Report ORNIJNUREG/
for April-June 1978," USNRC Report NUREG/
TM-3. Oak Ridge National I aboratory, Oak Ridge, TN.
CR-0310, U.S. Nuclear Regulatory Commission, Wash-April 1976.
ington, D.C., October 1978.
Whitman, G, D., " Quarterly Progress Report on the Whitman, G. D and liryan, R. II., " Quarterly Progress lleavy-Section Steel Technology Program for January-Report on the Heavy-Section Steel Technology Program March 1976 " ORNL Report ORNIJNUREG/FM-28.
for July-September 1978," USNRC Report NUREq/
Oak Ridge National laboratory, Oak Ridge, TN, July CR-0476 U.S. Nuc! car Regulatory Commission, Wash-1976.
ington, D.C., January 1979
-NUREG-1426 20
Compilation of Reports--1965-1990 Whitman, G. D. and liryan,11.11., " Quarterly Progress Cit-2141/VI, U.S. Nuclear itet.alatory Commission, lleport on the Ileavy-Section Steel Technology Program Washington, D.C, June 1981.
for October-December 1978,"
USNRC Report NUltliG/CR-0656, U.S. Nuclear Regulatory Commis.
Whitman, G. D. and llryan,11.11., " Quarterly Progress sion, Washington, D.C., April 1979 Iteport on the lleavy-Section Steel Technology Program for April-June 1981," USNitC Report NUlti!G/
Whitman, G. D. and firyan, R.11., " Quarterly Progress CR-2141, Vol. 2, U.S. Nuclear Regulatory Commission, itep>rt on the ileavy-Section Steel Technology Program Washington, D.C., October 1981.
for January-htarch 1979," USNitC Report NUltlIG/
Whitman, G. D. and lityan,11. I1., " Quarterly Progress Cit-0818, U.S. Nuclear Regulatory Commission, % ash-Iteport on the lleavy Section Steel Technology Program ington, D.C., August 1979.
for %-S(pb 198L" USNRC lleport NURl!G/
CR -2141, Vol. 3, U.S. Nuclear Regulatory Commission, Whitman, G. D. and liryan,11.11., " Quarterly Progress Washington, D.C., l'ebruary 1982.
Report on the ileavy-Section Steel Technology Program for Apnt-June 1979," USNRC Report NUlti!G/
Whitman, G. D. and liryan, it 11., " Quarterly Piogress CR-0980, U.S. Nuclear llegulatory Commission, Wash-Report on the licavy-Section Steel Technology Program ington, D.C., October 1979.
for October-December 1981,"
USNltC lleport NURl!G/CR-2141, Vol. 4, U.S. Nuclear llegulatory Whitman, G. D. and llryan, R.11., " Quarterly Progress Commission, Washington, D.C., April 1982.
Iteport on the Ileasy-Section Steel Technology Program for July-September 1979," USNitC Report NURl!G/
Whitman, G. D. and firyan,11. II., " Quarterly Progress Cit-l197, U.S. Nuclear Regulatory Commission, Wash.
Iteport on the lleavy-Section Steel Technology Program ington, D.C., Apnl 1980.
for January-htarch 1982," USNitC lleport NURiiG/
CR-2751, Vol.1, U.S. Nuclear Regulatory Commission, Whitman. G. D. and liryan, R. II., " Quarterly Progress Washington, D.C., August 1982.
Report on the !!eavy-Section Steel Technology Program Whitman, G. D. and 11')an, it 11., " Quarterly Progress for October-December 1979, USNRL Report NURiiG/CR-1305, U.S. Nuclear Reculatory Commis-Repon on the lleavy.Section Steel.rechnology Program sion Washington, D.C., hiay 1980. '
for April-June 1982, USNRC lleport NUlti!G/
CR-2751, Vol. 2, U.S. Nuclear Regulatory Commission,
" " E ""'
""** I Whitman, G. D. and !!ryan, R. I1., " Quarterly Progress Report on the IIcavy-Section Steel Technolopy Program Whitman, G. D. and liryan, R. II., " Quarterly Progress for January-htarch 1980," USNRC Report NURl!G/
Report on the ticavy-Section Steel Technotory Program CR-1477, U.S. Nuclear Regulatory Commission, Wash-for July-September 1982," USNRC Report NURiiG/
ington, D.C., July 1980-CR-2751, Vol. 3, U.S. Nuclear Regulatory Commission, Whitman, G. D. and liryan, R. II., " Quarterly Progress Report on the ileavy-Section Steel Technology Program Whitman, G. D., Pugh, C 11., and firyan, R. I1., " Quar-for April-June 1980 " USNRC Report NURl!G/
terly Progress Report on the lleavy-Section Steel Tech-CR-1627, U.S. Nuclear Regulatory Commission, Wash-nology Program for October-December 1982," USNRC ington, D.C.,0ctober 1980.
Repor t NURiiG/ Cit-2751, Vol. 4, U.S. Nuclear Regula-tory Commission, Washington, D.C., h1ay 1983.
Whitman, G. D. and llryan, R.11., " Quarterly Progress Report on the licavy-Section Steel Technology Prograrn Whitman, G. D., "llistorical Summary of the licavy-for July-September 1980," USNRC Report NURI!G/
Section Steel Technology Program and Some Related CR-1806, U.S. Nuc! car Regulatory Commission, Wash.
Activities in 1.ight-Water Reactor Pressure Vessel Safety ington, D.C., December 1980.
Research " USNRC Report NURl!G/CR-44d9, U.S.
Nuclear Regulatory Commission, Washington, D.L.
March N Whitman, G. D. and llryan, R. H., " Quarterly Progress Report on the lleavy-Section Steel Technology Program Witt,17. J., "licavy-Section Steel Technology Program for October-Decc mher 1980,"
USNRC Report Semiannual Progress Report for Period !!nding NURIiG/CR-1941, U.S. Nuclear Regulatory Commis-August 31, 1967," USAliC Report ORNic4175, Oak sion, Washington, D.C., March 1981.
Ridge National laboratory, Oak Ridge, TN, January 1968.
Whitrnan, G. D. and liryan, R. I1., " Quarterly Progress Report on the lleavy Section Steel Technology Program Witt, l'. J., "licavy Section Steel Technology Program for Janua'y-N1 arch 1981," USNRC Report NURiiG/
Semiannual Progress Report for Period !!nding 21 NURl!G-1426
Compilation of Reports-1965-1990 February 29,1968," USAEC Report ORNie4315, Oak Ying, S. P.and Grigory, S. C.," Tests of 6 inch Thick Ten-Ridj;e National laboratory, Oak Ridge, TN, October site Specimens, Fif th Technical Summary Report Acous-1968.
tie Emission Monitoring of One Inch and Six-inch. Thick Tensile Specimens," SWRI Report ilSSTP-TR-24, Witt, F. J,1icavy-Section Steel Techralogy Program Southwest Research Institute, San Antonio,TX, Novem-Semiannual Progress Report for Period linding ber 1972, August 31,1968," USAEC Report ORNir4377, Oak Ridge National laboratory, Oak Ridge, TN, April 1969.
Fracture Mechanics: Experimental-Standard Specimen Testing Witt, F. J., "lican-Section Steel Technology Program Semiannual Progress Report for Period finding Febru*
Carlson, K. W. and Williams, J. A., "The liffect of Crack ary 28,1969," USAEC Report ORNI A463, Oak Ridge 1.cngth and Side Grooves on the Ductile FractureTough-National Iaboratory, Oak Ridge, TN, January 1970.
ness Properties of ASTM A533 Steel," USNRC Report NUREG/CR-1171, U.S. Nuclear Regulatory Commis-Witt, F. J., "lleavy Section Steel Technology Program sion, Washington, D.C., October 1979.
Semiannual Progress Report for Period Ending August 31,1969," USAEC Report ORN!A512, Oak Davis, D. A., Vassilaros, M. G., and Gudas, J. P.,"Speci-Ridge National laboratory, Oak Ridge,TN, March 1970-men Geometry and Extended Crack Growth liffects on Ji-R Curve Characteristics for llY-130 and ASTM Witt, F J. and llerggren, R. G., " Size Effects and Energy A53311 Steels," USNRC Report NURI!G/CR-30S9, Disposition in Impact Specimen Testing of ASTM A 533 U.S. Nuclear Regulatory Commission, Washington, Grade Il Stect," US AliC Report ORNI.-TM -3030, Oak D.C., November 1982.
Ridge National laboratory, Oak Ridge, TN, August 1970.
Dodge, W. G. and Smith, J. II., " A Diagnostic Procedure Witt, F. J., " Heavy-Section Steel Technology Program for the !! valuation of Strain Data From A 1.inear lilastic Semiannual Progress Report for Period Endmg. Febru-Test," ORNL Report ORNI.-TM-3415, Oak Ridge Na-ary 28,1970," USAliC Report ORNI A590, Oak Ridge tional laboratory, Oak Ridge, TN, November 1972.
National laboratory, Oak Ridge, TN, October 1970.
Gudas, J, P. et al.,"A Summary of Recent investigations Witt, F. J., "llcasy-Section Steel Technology Program of Compact Specimen Geometry liffects on the JI-R Semiannual Progress Report for Period finding Curve of High Strength Slects," USNRC Report August 31,1970," USAEC Report ORNIA653, Oak NUREG/CR-1813, U.S. Nuclear Regulatory Commis-Ridge National Laboratory, Oak Ridge, TN, April 1971.
sion Washington, D.C., October 1980.
llackett,11. M., Kirk, M.T., and Hays, R. A.,"An livalu.
Witt, F. J., " Heavy Section Steel Technology Program ation of J-R Curve Testmg of Nuclear Piping Matenals Semiannual Progress Report for Period Ending Febru.
Using the Direct Current Potential Drop Technique,'
ary 28,1971," USAEC Report ORNIA681, Oak Ridge USN RC Report NUREG/CR-4540, U.S. Nuclear Regu-National laboratory, Oak Ridge. TN, December 1971.
latory Commission, Washington, D.C., June 1986.
Witt, F. J., "lleavy-Section Steel Technohygy Program lliser, A.1. and less, F. J., " Alternative Procedures for Semiannual Progress Report for Peraxl Endmg J-R Curve Determination," USNRC Report NUREG/
~ August 31,1971," USAEC Report ORNIA764, Oak CR-3402, U.S. Nuclear Regulatory Commission Wash.
Ridge National Laboratory, Oak Ridge, FN, April 1972.
ngton, D.C., July 1983.
Witt, F. J., "IIcavy-Section Steel Technology Program Hiser, A. l and Terrell, J. II., "Si/c Effects on J-R Semiannual Progress Report for Penod lindmg Febru-Curves for A 302-11 Plate," USNRC Report NUREG/
ary 29,1972," USAEC Report ORNIA816, Oak Ridge CR-5265, U.S. Nuclear Regulatory Commission, Wash.
National laboratory, Oak Ridge, TN, October 1972.
ington, D.C., January 1989.
Witt, F. J., "licavy-Section Steel Technology Program Joyce, J. A., " Application of the Key Curve Method to Semiannual Progress Report for Period Ending Determining J-R Curves for A53311 Steel," USNRC Re-August 31,1972," USAl!C Report ORNIA855, Oak port NURiiG/CR-1290, U.S. Nuclear Regulatory Com-Ridge National laboratory, Oak Ridge, TN, April 1973.
mission, Washington, D.C., January 1980.
I Witt, F. J., " Heavy-Section Steel Technology Program Joyce, J. A., " Static and Dynamic J-R Curve Testing of l
Semiannual Progress Report for Period Ending Febru-A53311 Stect Using the Key Curve Analysis Technique,"
(
ary 28,1973," US Ai!C Reoort ORNIc4918, Oak Ridge USNRC Report NUREG/CR-2274. U.S. Nuclear Regu.
National laboratory, Oak Ridge, TN, February 1974.
latory Commission, Washington, D.C., July 1981.
NURl!G-1426 22 l
Compilation of Reports-1965-1990 Joyce, Jc A;, " Instability Testing of Compact and Pipe port MCR-69-189, Martin Marietta Corporation, Den.
Speciraens Utilizing a Test System Made Compliant by ver, CO, November 20,1969.
Computer Control " USNRC Report NURl!G/
CR-2257, U.S. Nuclear Regulatory Commission, Wash.
loss, l', J., Gray, Jr., R. A., and Ilawthorne, J. R.,"Inves-ington, D.C., March 1982, tigations of Warm Prestress for the Case of Small T Dur-ing a Heactor loss-of. Coolant Accident," NRI. Report Joyce,J. A. " Development and Verification of Conditions 8198, Naval Research Iaboratory, Washington, D.C.,
for Ductile Tearing Instability and Arrest," USNRC Re-March 1978, port NUREG/CR-4528, U.S. Nuclear Regulatory Com-mission, % ashington, D.C., Fcbruary 1986.
loss, F. J., ed., " Structural Intcgrity of Water Reactor Pressure lloundary Compments," USNRC Report NURl!G/CR-3228, Vol.1. U.S. Nuclear Regulatory Joyce, J. A. and llackett,11. M., " Application of the h.ey Commission, Washington, D.C., April 1983.
Curve and Multi. Specimen l'echniques to Dynamic J-R Curve Testing of Alloy Steel," USNRC Report NURiiG/
Inss, F. J., ed., " Structural Integrity of Water Reactor CR-4579, U.S. Nuclear Regulatory Commission, Wash-Pressure lloundary Components, Annual Report for ington, D.C., March 1986.
1983," NURl!G/CR-3228, Vol. 2 U.S. Nuclear Regula.
Joyce, J. A. and Schneider, C. S.," Application of Alter-nating Current Potential Difference to Drop Tower J-R Ioss, F.J., ed.,"Structurallntegrity of Light Water Reac-Curve Measurement," USNRC Report NUREG/
tor Pressure lloundary Components-Four-Year Plan, CR-4699, U.S. Nuclear Regulatory Commission, Wash-1984-1988," USNRC Report NUREG/CR@n U.S.
ington, D.C., August 1986..
Nuclear Regulatory Commission, Washington, D.C.,
September 1984.
- Joyce,J. A.andllackett,1!.M.,"Developmentof an Ana-lytic Key Curve Approach to Drop Tower J-R Curve Inss, F. J., ed., " Structural Integrity of Water Reactor Measurement," USNRC Report NUREG/CR-4782, Pressure lloundary Components, Annual Report for U.S. Nuclear Regulatory Commission, Washington, 1984," USNRC Report NUREG/CR-3228, Vol. 3, U.S.
D.C., December 1986.
Nuc! car Regulatory Comm,ssion, Washmgton, D.C.,
i June 1985.
Joyce, J. A. and Hackett,11. M.," Transition Range Drop loss, F. J,, ed., " Structural Integrity of Water Reactor Tower J-R Curve Testing of A106 Stect," USNRC Re-Pressure lloundary Components, Annual Report for port NUREG/CR-4818, U.S. Nuclear Regulatory Com-1985," USNRC/CR-3228, Vol. 4, U.S. Nuclear Regula-mtssion, Washington, D.C., December 1986.
tory Commission, Washington, D.C., June 1986.
Joyce, J. A., " Ductile to lirittle Toughness Transition loss, F. J., ed., " Structural Integrity of Water Reactor Characterization of A53311," USNRC Report NURl!G/
Pressure lloundary Components, Annual Report for CR-5142, U.S. Nuclear Regulatory Commission, Wash-1986," USNRC Report NUREG/CR-3228, Vol. 5, U.S.
ington, D.C, April 1988.
Nuclear ReguRteg Commission, Washington, D.C., July 1987.
Joyce, J. A. et al., " Application of the J. Integral and the Modified J-Integral to Cases of large Crack lixtension,"
loss, F. J., ed., " Proceedings of the Second CSNI Work.
USNRC Report NUREG/CR-5143, U.S. Nuclear Regu.
shop on Ductile Fracture Test Methods, Paris, France, latory Commission, Washington, D.C., June 1988.
' April 17-19,1985," USNRC Confe:ence Proceedings, NURl!G/CP-0064, U.S. Nuclear Regulatory Commis-Legge, S. A.," Effects on Fracture Mechanics Parameters sion, Washington, D.C., August 1988.
of Displacement Measurement Geometry for Varying Specimen Sizes,_ Westinghouse Report WCAI-7926, Mager, T, R., " Notch Preparation in Compact Tension
,, Wi R
WCAP-7579 Wes-Westin use Electric Corporation, Pittsburgh,- 1 A, tinghouse Electric Corporation, PWR Systems Division, Pittsburgh, PA, November 1970.
- 1. ink, R. E. and llays, R. A.," Investigation of Tearing in-Marcal, P. V., Stuart, P M., and llettes, R. S., " Elastic-stability Phenomena in ASTM A106 Steel," USNRC Re-Plastic lichavior of a I ongitudinal Semi-lilliptic Crack in port NUREG/CR-4539, U.S. Nuclear Regulatory Com-a Thick Pressure Vessel,"llrown Report ilSSTP-TR-28, mission, Washington, D.C., February 1986.
Ilrown University, Providence, RI, June 1973.
leechel, L W., *The Effect of Testing Variables on the McCabe, D. II., " Plan for Experimental Characterization Transition Temperature in Steel," Martin Marietta Re-of Vessel Steel After Irradiation," USNRC Report 23 NURiiG-1426
.a
--mo e
m
_me-
+----r=w--
v+-*-o-w a+.v--
-i-w eww r-m-w-M
Compilation of Reports-1965-1990 i
NUREG/CR-4636 U.S. Nuclear Regulatory Commis-Nuclear Regulatory Commission, Washington, D.C.,
sion, Washington, D.C., October 1986.
June 1985.
McCabe, D. E., " Fracture livaluation of Surface Cracks Theiss, T. J., "Recommendc.tions for the Shallow-Crack Embedded in Reactor Vessel Cladding, Unirradiated Fracture Toughness Testing Task -Within the ilSST Hend Specimen Results," USNRC Report NUREGl Program," USNRC Report NUREG/CR-5554, U.S.
CR-4841, U.S. Nuclear Regulatory Commission, Wash.
Nuclear Regulatory Commission, Washington, D.C.,-
ington, D.C., May 1987.
September 1990.
McCabe, D. E.," Fracture !! valuation of Surface Cracks Vassilaros, M. G., G udas, J. P., and Joyce, J. A., "Experi-Embedded in Reactor Vessel Cladding, Material Prop-mental Investigation of Tearing Instability Phenomena crty Evaluations," USNRC Report NUREG/CR-5207, for Structural Materials," USNRC Report NUREG/
U.S. Nuclear Regulatory Commission, Washington, CR-2570 Rev.1, U.S. Nuclect Regulatory Commission, D.C., September 1988.
Washington, D.C., August 1982.
McCabe, D. E.," Fracture !! valuation of Surface Cracks Wilsim, W. K. and Begley, J. A., " Variable Thickness limbedded in Reactor Vessel Cladding," USNRC Report Study of the Edge Cracked Hend Specimen," Westing.
NUREG/CR-5326, U.S. Nuclear Regulatory Commis-house Report WCAP-8237, Westinghouse Electric sion, Washington, D.C., March 1989.
Corp., Pittsburgh, PA, November 1973.
McEnerney, J, W., " Assessment of Iamejlar Tearing,"
Witt, F. J. and Mager, T. R., " A Procedure for Determin.
ORNL Report ORNL/NUREG/FM-171, Oak Ridge ing Rounding Values on Fracture Toughness Kw at Any National laboratory, Oak Ridge, TN, March 1978.
Temperature," USAEC Report ORNL-TM-3894, Oak Ridge National laboratory, Oak Ridge, TN, October Merkle. J. G., "An Examination of the Size Effects and 1972.
Data Scatter Observed in Small Specimen Cleavage Frac.
ture Toughness Testing" USNRC Report NUREG/
Leak Detection CR-3672, U.S. Nuclear Regulatory Commission, Wash-ington, D.C., April 1984.
Kupperman, D. S.," Assessment of Leak Detection Sys-tems for LWRs: Revision 1 " USNRC Report NUREG/
Papaspyropoulos V., Marschall, C. W., and Umdow, M.,
CR-4813 Revs !, U.S. Nuclear Regulatory Commission,
" Predictions of J-R Curves with Large Crack Growth Washington, D.C., October 1988.
from Small Specimen Data," USNRC Report NUREG/
CR-4575, U.S. Nuclear Regulatory Commission, Wash-Kupperman, D. S., Prine, D., and Mathieson, T.,"Appli-mgton, D.C., September 1986.
cation of Acoustic Leak Detection Technology for the Detection and location of Leaks in Light Water Reac-Pa ris, P. C., ed., " Proceed.mgs of the US Nuclear Regula-tors," USNRC Report NUREG/CR-5134, U.S. Nuclear tory Commission CSNI Specialists Meeting on Plastic Regulatory Commission Washington D.C., October
- l' earing Instability, USNRC Conference Proceedings 3933' NUREG/CP-0010, U.S. Nuclear Regulatory Commis-sion, Washington, D.C.,,,anuary 1980.
~
NDE-Continuous Monitoring (Acoustic Riccardella, P. C. and Swedlow, J. l, "A Combined Emission)
Analytical Experimental Fracture Study of the Two Leadmg Theories of Elastic-Plastic Fracture (J-Integral Doctor, P. G., llarrington, T. P., and f lutton, P.11 " Pat-1 and Equivalent Energy)," Westinghouse Report WCAP-tern Recognition Methods for Acoustic Emission Analy 8224, Westinghouse Eleet-" Corporation, Pittsburgh, sis," USNRC Report NUREG/CR-0910, U.S. Nuclear PA, October 1973.
Regulatory Commission, Washington, D.C., July 1979.
Sanford, R. J. et a!., "A Photoelastic Study of the Influ-Ilutton, P.11.," Detection of incipient Failure in Nuclear ence of Non-Singular Stresses in Fracture Test Speci-Reactor Pressure Systems Using Acoustic Emission,"
mens," USNRC Report NUREG/CR-2179, U.S. Nu-PNL Report HNWL-997, Pacific Northwest laboratory, clear Regulatory Commission, Washington, D.C., August Richland, WA, April 1969.
198 L 1lutton, P.11., " Acoustic Emission Moniti> ring fo Con-Sutton, G. E. and Vassitaros, M. G 'Studyof thc liffects tinuous Crack Detection in Nuclear Reactor Pressure of Elastic Unioadmgs on the Ji-R Curves From Compact Houndaries " PNL Report HNWI -1597, Pacif:c North.
Specimens," USNRC Report NUREG/CR-4283 U.S.
west laboratory, Richland. W A, November 1971.
NLIREG-1426 24
Compilation of Reports--1965-1990 llutton, P. I1.and Schwenk,I!. II.," Program to Develop Nuclear llegulatory Cornmission, Washington, D.C.,
Acoustic limission-Irlaw itelationship for Insen ice Moni.
March 1985.
toring of Nuclear Pressure Vessels, Progress lleport No.1. July 1,1976-Ir bruary 1,1977," USNitC Report liutton, P.11. et al., " Acoustic I!ndssion itesults Ob-e N UltliG-0250-1, U.S. Nuclear llegulatory Commission, tained I rom Testing the Zil-1 Intermediate Scale Pres-Washington, D.C., March 1977, sure Vessel," USNRC lleport NUlti!G/ Cit-3915, U.S.
Nuclear Regulatory Commission, Washington, D.C.,
Ilutton, P. I1. and Schwenk, I!.11.," Program to Develop September 1985.
Accustic limissionirlaw Relationship for Inservice Moni-toring of Nuclear Pressure Vessels, Progress Report, Ilutton, P. I1. and Kurt/, R. J., " Acoustic limission/I' law li hruary 1-July 1,1977," USNRC lleport NUlt!!G-llelationship tor in-service Monitormg of Nuclear Pres-c 0250-2, U.S. Nuclear Regulatory Commission, Washing.
sure Vessels, Progress Iteport October 1984-March ton,11C., November 1977.
1985," USNitC Report NURiiG/CR-43(W), Vol.1. U.S.
Nuclear Regulatory Commission, Washington, D.C.,
August 1985.
Ilutton, P. I1. et al.," Program to Develop Acoustic limis-sion-l' law Relationship for Inservice Monitoring of Nu' Ilutton, P. I1. and Kurt/, R. J., " Acoustic limission/l law clear Pressure \\ essels, Annual lleport, July 1976-Octo' ltelationship for in-service Monitoring of Nuclear Pres-ber 1977, USNRC Report NURl!G/CR-0123, U.S.
sure Vessels, Progress Report, April-September 1985,"
Nuclear Regulatory Commission. W ashington, D.C.,
USN RC Report N Ult!!G/ Cit-4300, Vol. 2, U.S. Nuclear 3""C
- 0' Regulatory Commission, Washington, D.C., January 1986.
Ilutton, P. I1. et al.," Program to Develop Acoustic limis-sion-1 law itelationship for Insenice Monitoring of Nu-llutton, P. II. and Kurtz, R. J., " Acoustic limission/Irlaw clear Pressure Vessels, Progress Report, October 1977-llelationship for In.scrvice Monitoring of Nuclear Pres-January 1978," USNRC Report NURl!G/CR-0124, U.S.
sure Vessels, Progress lleport, October 1985-March Nuclear llegulatory Commission, Washington, D.C.,
1986," USNRC Report N URl!G/CR-4300, Vol. 3, No.1.
June 1978.
U.S. Nuclear Regulatory Commission, Washington, D.C., July 1986.
Ilutton, P.11., Schw enk,11.11., and Kurti,11. J., "listimate of I;easibility to Develop Acoustic limission 1 law itela-llutton, P. ll., " Acoustic limission/l law itelationship for tionships for Inservice Monitoring of Nuclear Pressure in-service Monitoring of Nuclear Pressure Vessels, Pro-Vessels," USNRC Report NURiiG/CR-0800, U.S. Nu-gress Iteport, April 1986-September 1986." USNRC lle-clear Itegulatory Commission, Washington, D.C., April port NUREG/CR-4300, Vol. 3, No. 2, U.S. Nuclear 1979.
Regulatory Commission, Washington, D.C., January 1987.
Ilutton, P.11. et al., " Acoustic limission Monitoring of ASMli Section ill llydrostatic Test," USNRC Report llutton, P. li.,"Acouetic limission/l law Relationship for NUllEGICR-2880, U.S. Nuclear Regulatory Commis.
Ir.-service Monitoring of Nuclear Pressure Vessels, Pro-sion, Washington, D.C., October 1982.
gress Report, October 1956-March 1987," USNRC lle-port NURI!G/CR-4300, Vol. 4, No.1. U.S. Nuclear Ryulatory Commission, Washington, D.C., June 1987.
ilutton, P. I1. et al., " Acoustic limission Monitoring of CR-36lunctional Testing " USNRC Report Ilot 1 N U R I:G /
1lutton, P. I1. et al., " Acoustic limission System Calibra.
93, U.S. Nuclear Regulatory C,ommission, % ash-tion at Watts liar Unit i Nuclear Itcactor," USNitC Re-ington, D.C., June 1984' port NURl!G/CR-5144, U.S. Nuclear Regulatory Com.
Ilutton, P.11. and Kurtz, R. J., " Acoustic limission/ Flaw Itelationship for in service Monitoring of Nuclear Pres-Polhick, A. A. and Wadin,J. it.." Application of Acoustic sure Vessels, Quarterly lleport October 1983-March limission as an On.l.ine Monitoring System for Nuclear 1984," USNRC Report NURiiG/CR-3825, Vols. I and Reactors, Iliannual Progress Report for July 1,1975-De-2, U.S. Nuclear Regulatory Commission, Washington, cember 31,1975," USNRC Report NUlti!G-0159, U.S.
D.C., June 1984.
Nuclear Regulatory Commission, Washington, D.C.,
1976.
Hutton, P. I1. and Kurtz, R. J., " Acoustic limission/ Flaw Relationship for in-service Monitodng of Nuclear Pres-Polhick, A. A. and Wadin,J. R.," Application of Acoustic sure Vessels, Quarterly RcW, April-September 19S4,"
limission as an On.l.ine Monitoring System for Nuclear USN:tC Report NURt.G/CR-3S25, Vols. 3 and 4, U.S.
Reactors, l'inal Progress Report January 1,1976-Sep-25 NURl!G-1426
.. _ - - - - - -. - _ ~. -. -. - -
Compilation of Reports-1965-1990 terrher 30,1976," USNRC Report NURIIG/CR-0605, CR-2264, U.S. Nuclear Regulatory Commission, Wash.
U.S. Nuclear Regulatory Commission, Washington, ington, D.C., July 1982.
D.C., January 1979.
i llusse, L J., Collins,11. D., and Doctor, S. R., " Review i
Prine, D. W, and Clark, R. N.," Inspection of Nuclear Re-and Discussion of the Development of Synthetic Aper.
actor Welding by Acoustic Emission, Final Report Phase ture Focusing Technique for Ultrasonic Testing (SAIT-1.- November 1974-November 1975," G ARD Report UT)," USNRC Report NUREG/CR-3625, U.S. Nuclear NUREG-0035-1, G ARD, Inc., Niles, IL February 1976.
Regulatory Commission, Washington, D.C., March 1984.
Prine, D. W. " Inspection of Nuclear Reactor Welding by Collins, i1, D. and Gribble, R. P., " Siamese imaging Acoustic Emission, Data Report November 1975-May Technique for QuasiVertical Type (OVI') Defects in 1976," GARD Report NUREG-0035-2, GARD, Inc.,
Nuclear Reactor Piping," USNRC Report NUREG/
Niles,11 September 1976.
CR-4472, U.S. Nuclear Regulatory Commission, Wash-ington, D.C.,1986.
Prine, D, W. and Mathieson, T, A., " inspection of Nu-elear Reactor Welding by Acoustic Emission, May Cook, K. V. et al., " Ultrasonic Ileam Spread Measure-1976-March 1977," G ARD Report NUREG-0035-3, ments in Thick Pressure Vessel Typc Steel," USNRC Re-G ARD, Inc., Niles,11, June 1977.
port NUREG/CR-2485, U.S. Nuclear Regulatory Com-mission, Washington, D.C., February 1982.
Prine, D. W. and Mathieson, T. A.,
Inspection of Nu-clear Reactor Welding by Acoustic E," mission,1 mal Re-Cook, K. V., I atimer, P, J., and McClung, R. W., " Flaw Measurement Using UVasonics in Thick Pressure Ves-port November 1974-November 1977, USNRC Report sel Steel," USNRC Repor. NURl!G-2661, U.S. Nuclear NURl!G/CR-0461, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., November 1978.
Ifge ulatory Commission, i.,ashington, D.C.,
August t'rine, D. W. and Mathieson, T. A., " Inspection of Nu-Cook, K. V., l.atimer, P. J., and McClung, R. W., *Influ-clear Reactor Welding by Acoustic hmission, Progress ence of Scanniag Variables on Ultrasonic R(.sponse,"
Report November 1977-November 1978, USNRL Re-USNRC Report NUREG/CR-2967 U.S. Nuclear Regu-port NUREG/CR-0703, U.S. Nuclear Regulatory C,om' latory Commission, Washington, D.C., December 1982, mission, Washington, D.C., March 1979.
Crawford, S. L et al., " Detection of Small. Sized Near.
Prine, D. W., Mathieson, T A., and Filar,11. S., "Inspec-Surface Under-Clad Cracks for Reactor Pressure Ves-tion of Nuclear Reactor Welding by Acoustic Emission,"
seis " USNRC Report NURiiG/CR-2878, U.S. Nuclear USNRC Report NUREG/CR-1441, U.S. Nuclear Regu-Regulatory Commission, Washington, D.C., February latory Commission, Washington, D.C., May 1980.
- 1933, Deeds, W. E. and Dodd, C. V., "A Two-Dimensional Re-NDE-In Service inspection laxation Program for Systems with inhomogeneous Per-meability," ORNL Report ORN111 M-5333, Oak Ridge 11ates, D. J., Doctor, S. R., and licaster, P. G.," Stainless National 1aboratory, Oak Ridge, TN, June 1976.
Stee! Round Robin Test Centrifugally Cast Stainless Steel Screening Phase," USNRC Report NUREG/
Deeds, W. Es Dodd, C, V., and Scott, G. W.. " Computer-CR-4970, PISC 3 Report No. 5, U.S. Nuclear Regulatory Aided Design of Multifrequency Eddy-Current Tests for Commission, Washington, D.C., October 1987, 12yered Conductors with Multiple Property Variations,"
ORNL Report ORN111'M-6858, Oak Ridge National llecker, F, L et al.," Integration of NDE Reliability and -
- 12bomtory, Oak Ridge, TN, October 1979.
Fracture Mechanics, Phase 1 Report," USNRC Report N UR EG /CR-1696-1, U.S. Nuclear Regulatory Commis-Deeds, Wa E. and Dodd, C. V., " Multiple Property Vari-sion, Washington, D.C., March 1981.
ations in Coaxial Cylindrical Conductors Determined with Multiple-Frequency Eddy Currents," USNRC Re-Ilush, S. II., " Reliability of Nondestructive Examination, port NUREG/CR-0967 U.S. Nuclear Regulatory Com-Volumes I,11, and III," USNRC Report NUREG/
mission, Washington, D.C., November 1979.
CR-3110-1, -2, and -3, U.S. Nuclear Regulatory Com-mission, Washington, D.C., October 1983.
Doctor, S. R. et al., " Integration of Nondestructive Exa-mination (NDE) Reliability and Fracture Mechanics, Ilusse, L J. et al.," Characterization Methods for Ultra-Semi-Annual Report, April 1984-September 1984,"
sonic Test Systems " USNRC Report NUREG!
USN RC R eport N UR EG /CR-4469, Vol.1. U.S. Nuclear NUREG-1426 26
Compilation of iteports--1965-1990 llegulatory Commission, Washmgton, D.C., January lhttor, S. R. et al.," Nondestructive lhaminatior (NDl!)
19S6.
Iteliability for Insenice Inspection of 1j ht Water iteac.
g tors, Semi-Annual lieport, April 1987-September 19S7,"
Doctor, S. R. et al., " Development and Validation of a USNRC Report N URlT i/CR-4469, Vol. 7, U.S. N uclear llegulatory Comrmss,on, Washington, D.C., November i
ItcalJhme S AI T-UT System for the inspection of 1.ight 19h8-WaterIteactor Components, Semi Annualiteport, April 1984 to Septernber 1984," USNltC Report NURiiG/
CR-4583 Vol. l., U.S. Nuclear llegulatory Commission, I httor, S. R. et al.," Nondestructive lixamination (NDii)
Washington, D.C., N1ay 1986.
Itchabihty for Inservice inspection of 1.ight Water Reac-tors, Semi-Annual Report, October 19S7-hiarch 1985 "
USNilC Report NURl!O/CR-4469, Vol. 8, U.S. Nuclear Doctor, S.11. et al., "livaluation and improvement of.
Regulatory Commission, Washingmn, D.C., October NDl! Rehability for Inservice Inspection of 1.ight Water g 939' lleactors, Semi Annual Report. October 1984-h1 arch 1985 " USNRC Report NURliG/CR-4469, Vol. 2, U.S.
o r, et at,.NonhunNe b.anunagon @ @
Nuclear Regulatory Commission, Washington, ILC., Oc-Reliability for Inservice Inspection of 1j ht W ater Reac-g tober 19S6.
tors, Semi. Annuallieport, Apnl 198S-September 1988,"
USN RC Report N U Rl!O /CR-4469, Vol. 9, U.S. Nuclear Doctor, S. R. et al.," Nondestructive !!xamination (NDli)
Regulatory Commission, Washington, D.C., November Rehability for Insemce inspection of 1.ight Water Reac-19S9.
tors Semi-Annual Report, April 1985-September 1955 "
USNRC Report NURI:G/CR-44b9, Vol 3, U.S. Nuclear Doctor, S. R et al.," Nondestructive 1aamination (N Dli)
Regulatory Commission, Washington, D.C., October Reliability for Inservice inspection of 1.ight Water Reae.
19S6-ters, Sem'i-Annual Report, October 198S-htarch 19S9,"
USNRC Report NURl!G/CR-4469, Vol.10. U.S. Nu-Doctor, S. R. et al., " Development arid Validation of a clear Regulatory Commission, Washington, D.C., Sep-Real-Time sal?tiUT System for the Inspection of 1.ight tember 1990.
Water Reactor Components, Annual Report, October 1984 to September 19S5 " USNHC Report NURl!GI Dodd, C. V, and NicClung. R. W., "17uel lilement Cool-CR-4583, Vol. 2 U.S. Nuclear Reputatory Commission, ant Channel and Other Spacing hicasurements by lidJy-Washington, D.C., June 1987.
Current Techniques," OltNI. Report ORNicTh1-129, Oak Ridge National laboratory, Oak Ridge, TN, N1 arch I962-Doctor, S. R. et al., " Nondestructive iixamination (ND1i)
Reliability for inservwe inspection of 1.ight Water Reac-tors, Semi-Annual Report, October 1985-hiarch 1986,"
Dodd, C. V., " Design and Construction of liddy-Current Coolant Channel Spacing Probes," ORNI. Report USN RC Report N U Rl!G /CR-4469, Vol. 4, U.S. N uclear Regula ory Commission, Washington, D.C., h1 arch 1987.
ORN1 3580, Oak Ridge National iahoratory, Oak Ridge, TN, April 1964.
Doctor, S. R. et al., " Development and Validation of a lhxld, C. V. and Deeds, W. li "lilectromagnetic Forces Real-Time SAFluUT System for the Inspection of 1.ight in Conductors," ORNI. Report ORN1cTht-1835 Oak Water Reactor Components, Annual Report, October Ridge National laboratory, Oak Ridge, TN, Ntay 1967.
1985 to September 1986," USNRC Report NURiiG/
CR-4583, Vol. 3, U.S. Nuclear Regulatory Commission, lh id, C. V. and Deeds, W, I!., " Analytical Solutions to Washington, D C., July 19S7' My-Current Coil Problems," ORNI Report ORNic Tht-1987, Oak Ridge National laboratory, Oak Ridge, lhictor, S. R. et al.. " Nondestructive !!xamination (ND E)
TN, November 1967.
Reliability for Inservice inspection of 1.ight Water Reac-tors, Semi Annual Report, April 1956-September 1986,"
Dodd, C. V. et al., "Some liddy Current Problems and USN RC Report NU Rl!G/CR-4469, Vol. 5, U.S. N uclear
'their Integral Solutions," ORNI. Report ORNic4384, Regulatory Commission, Washington, D.C., April 1987-Oak Ridge National Iahoratory, Oak Ridge, TN, April 1969 Doctor, S. R. et al.," Nondestructive Exammaton (N Dli)
Reliability for Inservice Inspection of 1.ight Water Reac-thidd, C. V. and 1 u, C. C., " Nondestructive Test for tors. Semi-Annual Report, October 19S6-Niarch 19S7 "
Nicasunng The State of Ileat Treatment in Closure USN RC Report NU RIiG /CR-4469. Vol. b. U.S. N uclear Welds." ORNI. Report ORNIeThl-3024, Oak Ridge Regulatory Commission, Washington, D.C., June 1987.
National I ahoratory. Oak Ridge, TN, July 1970.
27 N U Rl!G -1426
Compilation of Reports-1965-1990 Dodd, C. V and Simpson, W. A., "Ihickness Measure-lidler, S. K., ed., " Reactor Safety Research Programs,
- ments Using Eddy-Current Techniques," ORNL Report Quarterly Report April-June 1980," USNRC Report ORNicTM-3712, Oak Ridge National Ialmratory, Oak NUREGICR-1454 Vol. 2, U.S. Nuclear Regulatory Ridge,'IN, March 1972.
Commission, Washington, D.C., November 1980.
Dodd, C. V. et al.,"Ihc Analysis of Reflection Type Coils tidler, S. K., ed., " Reactor Safety Research Programs, for liddy-Current Testing," ORNL Report ORNie Quarterly Report July-September 1980," USNRC Re-TM-4107, Oak Ridge National Ialmratory, Oak Ridge, port NURiiG/CR-1454 Vol. 3, U.S. Nuclear Regulatory
'IN April 1973.
Commission, Washington, D.C., December 1980.
DodJ C, V. et al.,
- Design Induction Probes for Meas.
lidler, S. K., ed., " Reactor Safety Research Programs, urement of I evcl of Liquid Metals," ORNL Report Quarterly Report October-December 1980," USNRC ORNieTM-4175, Oak Ridge National Iaboratory, Oak Report NURiiG/CR-1454 Vol. 4, U.S. Nuclear Regula.
Ridge,'IN, May 1973.
tory Commission, Washington, D.C., April 1981, Dodd, C. V., Smith, J. II., and Simpson, W. A., "l!ddy.
lidler, S. K., ed., " Reactor Safety Research Programs, Current livaluation of Nuclear Control Rods," ORNL Quarterly Report January-March 1981," USNRC Re-Report ORNI-TM-4321, Oak Ridge National labora, port NURiiG/CR-2127 Vol.1, U.S. Nuclear Regulatory tory, Oak Ridge TN, September 1973, Commission, Washington, D.C., July 1981.
Dodd, C. V. and Deeds, W. E., " Calculations of Magnetic lidler, S. K., ed., " Reactor Safety Research Programs, Fields from Time-Varying Currents in the Presence of Quarterly Report April-June 1981," USNRC Report Conducters." ORNL Report ORNieTM-4958, Oak NUREG/CR-2127 Vol. 2, U.S. Nuclear Regulatory Commission, Wash, gton, D.C., September 1981.
Ridge National laboratory, Oak Ridge, TN, July 1975.
m Dodd, C. V, and Deeds, W. E., " Sealing Relations for IIdler, S. K., ed., " Reactor Safety Research Programs, Eddy Current Phenomena,"
ORNL Repori Quanaly Repon July. September 1981," USNRC Re-ORNie5077, Oak Ridge National laboratory, Oak Imrt NURiiG/CR-2127 Vol. 3, U.S. Nuclear Regulatory Ridge, TN, November 1975.
Commission, Washmgton, D.C., January 1982.
Dodd, C. V. and Connell, G. D., "Ihe NDT-Comps Mi.
Edler, S. K., ed., " Reactor Safety Research Programs, crocomputer" ORNL Report ORN11rM-5773, Oak Quanaly Repon OctobuWicember 1981, USNRC P""
4, Nudear egula-
-1 Ridge National laboratory, Oak Ridge, TN, March 1977.
tory Commission, % ashington. D.C,, March 198{..
Dodd, C. V. and Chitwood, I D., "three. Frequency lidler, S. K., ed., " Reactor Safety Research Programs, Eddy-Current Instrument for Multiple Property Prob-Quarterly Report January-March 1982 " USNRC Re-lems," ORNL Report ORNic5495, Oak Ridge National laboratory, Oak Ridge,TN, March 1979-port NUREGICR-2716 Vol.1, U.S. Nuclear Regulatory Commission, Washington. D.C., July 1982.
Dodd, C. V and Cowan, R. F., "the NDT-COMP 9 Mi' lidier, S. K., ed., " Reactor Safety Research Programs, crocomputer," USNRC Report NURl!G/CR-1548, U.S.
Quarterly Report April-June 1982," USNRC Report Nuclear Regulatory Commission, Washington, D.C.,
NURl!G/CR-2716 Vol. 2, U.S. Nuclear Regulatory September 1980.
Commission, Washington, D.C., November 1982.
Dodd, C, V., Whitaker, l M., and Deeds, W.11., "An lidler, S. K., ed, " Reactor Safety Research Programs, liddy-Current laboratory Test System Using Commer-Quarterly Report July-September 1982," USNRC Re-cial liquipment," ORNL Report ORNI-6366, Oak port NUREG/CR-2716 Vol. 3, U.S. Nuclear Regulatory Ridge National laboratory, Oak Ridge, TN, April 1987, Commission, Washington, D.C., March 1983.
Dodd, C. V. and Chitwood, I D., "Three-Frequency lidict, S. K., ed., " Reactor Safety Research Programs, Eddy. Current Instrument," USNRC Report NUREG/
Quarterly Report October-December 1982." USNRC CR-5061, U.S. Nuclear Regulatory Commission Wash-Report NURliG/CR-2716 Vol. 4, U.S. Nuclear Regula.
ington, D.C., May 1988.
tory Commission. Washington, D.C., April 1983.
Dotson, C. W., ed., " Reactor Safety Research Programs, Edler, S. K., ed., " Reactor Safety Research Programs, Quarterly Report October-December 1979," USNRC Quarterly Report January-March 1983," USNRC Re-Report NUREG/CR-1349, U.S. Nuclear Regulatory port NURiiG/CR-3307 Vol.1, U.S. Nuclear Regulatory Commission, Washington, D.C. August 1980.
Commission, Washington, D.C., July 1983.
NURiiG-1426 28
Compilation of Reports-1965-1990 Edler, S. K., ed., " Reactor Safety Research Programs, Vessels, Annual Progress Report, August 1,1974-July Quarterly Report April-June '983," USNRC Report 31, 1975," USNRC Report NUREG-0007-1, U.S. Nu-NUREG/CR-3307 Vol. 2. U.S. - Nuclear Regulatory clear Regulatory Commission, Washington, D.C., Janu.
Commission, Washington, D.C., December 1983.
ary 1976.
Edler S. K., ed., " Reactor Safety Research Programs, Frederick, J. R., Fairchild, R. C., and Anderson, II. H.,
Quarterly Report July-September 1983," USNRC Re-
" Improved Ultrasonic Nondestructive Testing of Pres-port NUREG/CR-3307 Vol. 3, U.S. Nuclear Regulatory sure Vessels, Annual Progress Report, August 1, Commission, Washington, D.C., April 1984.
1975-July 31,1976," USNRC Report NUREG-0007-2, U.S. Nuclear Regulatory Commission, Washington, Edler S. K., ed., " Reactor Safety Research Programs, D.C., August 1977.
Quarterly Report October-December 1983," USNRC Report NUREG/CR-3307 Vol. 4, U.S. Nuclear Regula-Frederick, J. R. et al.," Improved Ultrasonic Nondestruc-tory Comruission, Washington, D.C., May 1984, tive Testing of Pressure Vessels, Annual Progress Re.
port, October 1,1976-September 30,1977," USNRC Edler, S. K., ed.,
- Reactor Safety Research Programs, Report NUREG/CR-0135, U.S. Nuclear Regulatory Quarterly Report January-March 1984," USNRC Re-Commission, Washington, D.C., May 1978, port NUREG/CP-3810 Vol.1. U.S. Nuclear Regulatory Commission, Washington, D.C., June 1984.
Frederick, J. R. et al.," Improved Ultrasonic Nondestruc-tive Testing of Pressure Vessels, Annual Progress Re-Edler, S. K., ed., " Reactor Safety Research Programs, port, October 1,1977-September 30,1978," USNRC Quarterly Report April-June 1984," USNRC Report Report NUREG/CR-0581, U.S. Nuclear Regulatory NUREG/CR-3810 Vol. A U.S. Nuclear Regulatory Commission, Washington, D.C., January 1979.
Commission, Washington, D.C., November 1984.
Edler, S. K., ed., " Reactor Safety Research Programs, Frederick, J. R. et al., *1mproved Ultrasonic Nondestruc-Quarterly Report July-September 1934," USNRC Re-tive Testmg of Pressure Vessels, USNRC Report port NUREG/CR-3810 Vol. 3, U.S. Nuclear Regulatory NUREG/CR-0909, U.S. Nuclear Regulatory Commis-Comrnission, Washington, D.C., February 1985.
si n, Washington, D.C., September 1979.
Edler, S. K., ed., " Reactor Safety Research Programs, Ganapathy, S et al., " Ultrasonic Imaging Techniques for Quarterly Report October-December 1984," USNRC Real time Inservice Inspection of Nuclear Power Reac-Report NUREGICR-3810 Vol. 4, U.S. Nuclear Regula.
tors," USNRC Report NUREG/CR-2154, U.S. Nuclear fg81c8ulatory Commission, Washington, D.C., October tory Commission, Washington, D.C., May 1985.
Edler, S. K., ed., " Reactor Safety Research Programs, Quarterly Report January-March 1985 " USNRC Re-Ganapathy, S. et al., " Investigation of Special "'irpose port NUREG/CR.-4318 Vo!.1, U.S. Nuclear Regulatory Processors for Real Time Synthetic Aperture Focusing Commission, Washington, D.C., August 1985.
Techniques for Nondestructive Evaluation of Nuc! car Reactor Vessels and Piping Components," USNRC Re-1 Edler, S. K., ed., " Reactor Safety Research Programs, port NUREG/CR-2703, U.S. Nuclear Regulatory Com-I Quarterly Report April-June 1935," USNRC Report mission, Washington, D.C., January 1983.
NUREG/CR-4318 Vol. 2. U.S. Nuclear Regulatory Commission, Washington, D.C., October 1985.
Ganapathy, S, et al.," Design and Development of a Spe-cial Purpose S AFI' System for Nondestructive Evaluation Fairchild, R. C., " Improved Ultrasonic Non-Destructive of Nuclear Reactor Vessels and Piping Components,"
Testing of Pressure Vessels," USNRC - Report USNRC Report NUREO/CR-4365, U.S. Nuclear Rege-NUREG-0185, U.S. Nuclear Regulatory Commission, latory Commission, Washington, D.C., August 1985.
- Washington, D.C.,1977.
Good, M. S.and Van Fleet, Le," Status of Activities for Foster,11. E., McClung. R. W., and Davis, E. V.,
Inspecting Weld Overlaid Pipe Joints," USNRC Report "Penetrameter Sensitivity and Crack Detectability after NUREGICR-4484 U.S. Nuclear Regulatory Commis-Degradation of the Radiographic Procedure," USNRC sion, Washington, D.C., February 1986.
Report NUREG/CR-0593, U.S. Nucler.r Regulatory Commission, Washington, D.C., March 1979.
Hagen, C. M., ed., " Reactor Safety Research Programs, Quarterly Report January-March 1980," USNRC Re-Frederick, J. R., Seydel J. A., and Fairchild, R. C., "Im-port NUREG/CR-1454 Vol.1 U.S. Nuclear Regulatory proved Ultrasonic Non-Destructive Testing of Pressure Commission, Washington, D.C. October 1980, 29 NUREG-1426
Compilation of Reports-1965-1990 l
I tall,T. l!.," Interface and Installation G uide: S AIT-Ur port NURl!G/CR-0341, U.S. Nuclear Regulatory Com-I Utilities," PNI. Report No. 6274, Pacific Northwest mission. Washington, D.C., November 1978.
1.aboratory, Richland, WA,1987.
Ilooper, J. L, ed., " Reactor Safety Research Programs, 11all, T,11, "SAFF-Ur Utilities Guide to SAFF-Ur Quarterly Report July 1-September 30,1978," USNRC Principles and Conventions," PNL Report PNI A275, Report NUREG/CR-0546, U.S. Nuclear Regulatory Pacific Northwest Iaboratory, Richland, WA,1987.
Commission, Washington, D.C., l'ebruary 1979.
llall, T. I!., "S AFF-UT Utilities: Reference Manual,"
Ihioper, J. L, ed.," Reactor Safety Research Programs, PNI. Report PNI.-6276, Pacific Northwest laboratory, Quarterly Report October 1-December 31, 1978,"
Richland, W A,1987.
USNRC Report NUREG/CR-0681, U.S. Nuclear Regu-latory Commission Washington, ILC., March 1979.
Ilall, T. li, Reid. L D., and Doctor, S. R.,"The SAFF-Ur Real Time Inspection System-Operational Princi.
Ilooper, J. L, ed., " Reactor Safety Research Programs, ples and Implementation," USNRC Report NURl!G/
Quarterly Report January I-March 31,1979 " USNRC CR-5075, U.S.
Nuclear Regulatory Commission, Iteport NURiiG/CR-OS$5. U.S. Nuclear Regulatory Washington, D.C., June 1988.
Commission, Washington, D.C., May 1979.
Hamlin, D. R. and Jackson, J. L, " Program for Field Vali-Ilooper, J. L, ed., " Reactor Safety Research Programs, Qu nerly hport Apd 1-June 30, M, MCp dation of the Synthetic Aperture FocusingTechnique for Ultrasonic Testing (S AFF-UT), Quarterly Progress Re-port NUREG/CR-0962, U.S. Nuclear Regulatory Com-port November 1980-January 1981," USNRC Report mission, Washington, D.C., September 1979.
NUREG/CR-1885, Vol. 2, U.S. Nuclear Regulatory Commission, % ashington, D.C., March 1981.
t hioper, J. L, ed., " Reactor Safety Research Programs, Quarterly Report July 1-September 30,1979," USNRC Hamlin, D. R. and Jackson,J. L, " Program for Field Vah.-
Report NURiiG/CR-1009, U.S. Nuclear Regulatory Commission, Washington, D.C., J uly 1980.
dation of the Synthetic Aperture liicusingTechnique for Ultrasonic Testing (S AFF-UF), Quarterly Progress Re-Jackson, J. L, " Program for Field Validation of the Syn-port February-April 1981," USNRC Report NUREG/
thetic Aperture Focusing Techique for Ultrasonic Test-CR-1885, Vol. 3, U.S. Nuclear Regulatory Commission, ing (SAFF-UF)- Analysis llefore Test," USNRC Re-Washington, D.C., June 1981.
port NURl!G/CR-0288, U.S.
Nuclear Regulatory Hamlin, D. R., " Program for Field Validation of the Synthetic Aperture liicusing Technique for Ultrasonic Jackson, J. L " Program for Field Validation of the Syn-Testing (SAFF-UI)-Final Report," USNRC Report thetic herture Focusing Techniquic for UltrasonicTest-NUREG/CR-4078, U.S. Nuclear Regulatory Commis-ing (SAFF-UF) Midyear Progress Report," USNRC
-ion, Washington, D.C., November 1985.
Report NUREG/CR-0290, U.S. Nuclear Regulatory Ileasier. P. G. et al., " Performance Demonstration Tests for Detection of Intergranular Stress Corrosion Crack-Jackson, J. L," Program for Field Validation of the Syn-ing " USNRC Report NUREG/CR-4464, U.S. Nuclear thetic Aperture FocusingTechnique for UltrasonicTest-Regulatory Commission, Washington, D.C., February ing (SAFF-UF), Quarterly Progress Report August-1986-October 1980" USNRC Report NUREG/CR-1885, Vol.
1, U.S. Nuclear Regulatory Commission, Washington, Heasler, P. G.,"An Evaluation of Factors Influencing UI-D.C., January 1981.
trasonic Inservice inspection for Intergranular Stress Corrosion Cracks-Mini-Round Robin,' USNRC Re-Kupperman, D. S., Claytor, T. N., and Prine, D. W.,
port NURl!G/CR-4908, U.S. Nuclear Regulatory Com-
"NDli of Stainless Steel and On-1 ine I eak Monitoring of mission, Washington, D.C., July 1990.
LWRs: Annual Report October 1983-September 1984,"
USNRC Report NUREG/CR-4124 Vol.1, U.S. Nuclear Hooper, J. L, ed., " Reactor Safety Research Programs, Regulatory Commission, Washmgton, D.C., April 1985.
Quarterly Report January 1-March 31,1978," USNRC Report NURl!G/CR-0086, U.S. Nuclear Regulatory Kupperman, D. S. et al.,"NDfi of Stainless Steel and On-Commission. Washington, D.C., June 1978.
I.ine Ecak Monitoring of LWRs: Semiannual Report October 1984-March 1985," USNRC Report NURLG/
Ilooper, J. L, ed., " Reactor Safety Research Programs, CR-4368. U.S. Nuclear Regulatory Commission, Wash-Quarterly Report April 1-June 30, '978," USNRC Re.
ington, D.C., September 19S5.
1 NURI G-1426 30
Compilation of Reports-1965-1990 Kupperman D.S.et al.,"NDliof Staink.ahteclandOn-NUREGICR-3753, U.S. Nuclear Regulatory Commis-1.ine Irak Monitoring of1.WRs: Annual Report October sion, Washington, D.C., May 1984.
1984-September 1985," USNRC Report NURl!G/
CR-4124 Vol. II, U.S Nuclear Regulatory Commission, Triggs, T J. et al.,"lluman Reliability Impact on Inser-Washington, D.C., February 1986.
vice inspection: Review and Analysis of Iluman Perform-ance in Nondestructive Testing (Emphasi/ing Ultrason-Morris, C.J. and ilecker, F.1 " State-of Practice Review ics)," USNRC Report NUREG/CR-4436 Vol. 2, U.S.
of Ultrasonic Ircservice Inspection of Class I System Pip.
Nuclear Regulatory Commission, Washington, D.C.,
March 1986, ing in Commercial Nuclear Power Plants," USNRC Re-port NURl!G/CR-2468, U.S. Nuclear Regulatory Com-Wheeler, W. A. et al.,"Iluman Factors Study Conducted mission, Washington, D.C.,1982.
in Conjunction with a Mini-Round Robin Assessment of
'"5" # echnkal h'donnanc('," UN Wngt Nestor J r., C. W., t hid, C. V., and Deeds, W. I L, "Analy-
- ' " A ""'*"I ""E"I"* U sis and Computer Programs for Eddy Current Coils Con-sion, Washington, D.C., August 1986.
centric with Multiple Cylindrical Conductors," ORNI.
Report ORNie5220 Oak Ridge National 12tboratory, Oak Ridge, TN, July 1979.
Piping: Analysis Pate, J. R. and Dodd, C. V., " Computer Programs llrothers, A.J. et al.,"A Survey of I racture Modes as Re-for liddy-Current Defect Studies," USNRC Report lated to Reactor Primary Coolant Pipe Rupture, Gli Re-NUREG/CR-5553. U.S. Nuclear Regulatory Commis.
port GliAP-4446, General lilectric Corporation, San sion, Washington, D C., June 1990.
Jose, CA, May 1964.
1,1t W,"Approdnyan M('thoM()r Fracture Analy-Polky, J. N. and Miller, D. D., "An Ultra.High Speed
,prough-%,all t racked Pipes,,, USNRC Report s('s Residue Processor for SAlfl' Inspection System Image NUREG/CR-1853, U.S. Nuclear Regulatory Commis-linhancement," USNRC Report N U REG /C R-4170, sion Washington, D.C., February 198 n U.S. Nuclear Regulatory Commission, Washington, D.C.,1985.
liiber, R. J. et al, " Review of Through Wall Cntical Crack Formulations for Piping and Cylindrical Vessels,"
Polky,J. N.," Development of a Real-Time Number Proc-llattelle Report llMI-18S3,llattelle MemorialInstitute, essor for SAFP Inspection," USNRC Report NURiiG/
Columbus,011, May 1970.
CR-4634, U.S. Nuclear Regulatory Commission, Wash-ington, D.C., May 1986.
liiber, R. J. et al., " Cold I.cg integrity livaluation - Phase i Final Report," USNRC Report NUREG/CR-0584, Simpson, W. A. et al., " Computer Program, for Some U.S. Nuclear Regulatory Commission, Washington, Eddy-Current Problems-1970," ORNi cTM-3295, Oak D.C., January 1979.
Ridge National laboratory, Oak Ridge, TN, June 1971.
English, W. F. and Gilman, J. D.,"llWR Primary Piping Spanner, J. C. et al., "lluman Reliability impact on in.
Stresses for System Reliability Analysis," Gli Report service Inspection: Phase 1, Summary Report," USNRC GEAP-5724, General Electric Corporation, San Jose, Report NUREG/CR-1436 Vol 1 U.S. Nuclear Regula.
CA, September 1968.
tory Commission, Washington, D.C., March 1986.
Gibbons, W. S. and llackney,11. D., " Survey of Piping
'ac w may ant hpe Ruptme sfa Spanner,J.C.et al. " Qualification Process for Ultrasome p" ", ',
port G E AP-4574, G enci al l!!cet ric corpo.
Testing in Nuclear Inservice Inspection Applications"
'"" "' "" "*' ^'
"Y USNRC Report NU REG /CR-4882, U.S. Nuclear Regu-latory Commission. Washington, D.C., March 1990.
Gilman, J. D.. " Stress Intensity Factor for a Circumferen-tial Throuch-Wall Crack in a Straight Pipe," Gli Report Taylor, T. T. and Selby, G. P., "l! valuation of AS Mli Sec-OEAp_55'57, General Electric Corporation, San Jose, tion XI Reference i.evel Sensitivity for Initiation of Ul-CA. January 1968.
trasonic inspection Examination," USNRC Report NURiiG/CR-1957, U.S. Nuclear Regulatory Commis-Kanninen, M. F., Popelar, C. I L, and llrock, D., " A Criti-sion, Washington, D.C., April 1981.
cal Survey on the Application of Plastic Fracture Me-l chanics to Nuclear Pressure Vessels and Pipmg "
Taylor, T. T., " An Evaluation of Manual Ultrasonic n-USNRC Report NURl!G/CR-2110, U.S. Nuclear Regu-i spection of Cast Stainless Steel Piping," USNRC Report latory Com nission. Washington. D.C., May 1981.
l 31 N U REU --1426
Compilation of Reports-1965-1990 l
Kanninen, hl. F., ed., " Proceedings of the CSNI/NRC Reynolds, bl.11., "A Failure Diagram for Axially Flawed Workshop on Ductile Piping I racture Mechanics,"
Pipes," GE Report GEAP-5622, General Electric Cor-USNRC Conference Proceedings NUREG/CP-0075, poration, San Jose, CA, April 1968.
U.S. Nuclear Regulatory Commission, Washington, D.C., May 1988.
Rodabaugh, E. C., Maxey, W. A., and Eiber, R. J., "Re-view and Assessment of Research Relevant to Design As-Klecker, R. ct al.,"NRC teak Ilefore-Ilreak (LilH.NRC) pects of Nuclear Power Plant Piping Systems" Battelle Analysis Method for Circumferentially Through-Wall.
Report NUREG--0307, llattelle Columbus, Columbus, Cracked Pices Under Axial Plus llending loads",
011, July 1977.
USNRC Report NUREG/CR-4572, U.S. Nuclear Regu-latory Commission, Washington, D.C., May 1986.
Rodabaugh, E. C.,1skander, S. K., and Moore, S. E.,
"End Effects on Elbows Subjected to Moment loadings,"
Mayfield, M. E., Rodabaugh, E. C., and Eiber, R. J.,
ORNL Report ORNIJSub/2913/7, Oak Ridge National
" Relevance of Fatigue Tests to Cold Leg Piping,"
laboratory, Oak Ridge, TN, March 1978.
USNRC Report NUREG/CR-0325, U.S. Nuclear Regu-latory Commission, Washington, D.C., September 1978.
Rodabaugh, E. C. and Moore, S. E., " Evaluation of the Plastic Characteristics of Piping Products in Relation to Mayfield, M. E. et al., " Cold Leg Integrity Evaluation:
ASME Code Criteria," USNRC Report NUREG/
Final Report," USNRC Report NUREG/CR-1319, U.S.
CR-0261. U.S. Nuclear Regulatory Commission, Wash-Nuclear Regulatory Commission, Washington, D.C.,
ington, D.C., July 1978.
February 1980.
Rodabaugh, E. C. and Moore, S. E., " Stress Indices for Moore, S. E. and llryson, J. W., " Progress Report for the Girth Welded Joints, including Radial Weld Shrinkage, Design Criteria fot Piping r Nonles Program for the Mismatch and Tapered-Wall Transitions," USNRC Re-Two Quarterly Periods July I to Sept. 30 and Oct. I to port NUREG/CR-0371, U.S. Nuclear Regulatory Com.
Dec. 31,1975," ORNI. Report ORNIJNUREG/FM-18, mission, Washington, D.C., September 1978.
Oak Ridge National laboratory, Oak Ridge, TN, May 1976.
Rodabaugh, E. C. and Moore, S. E., " Stress Indices and Flexibility Factors for Nozzles in Pressure Vessels and Moore, S.11. and Uryson, J. W., " Design Criteria for Pip.
Piping " USNRC Report NUREG/CR-0778, U.S. Nu-ing and Nonles Program Quarterly Progress Report for clear Regulatory Commission Washington, D.C., June April-June 1976," ORNL Report ORNLJNUREG/
1979.
TM-91, Oak Ridge National laboratory, Oak Ridge, TN, Feb.uary 1977.
Rodabaugh,11 C., " Comments on the Leak-Ilefote-Break Concept for Nuclear Pov,er Plant hping Systems,"
Moore, S. E. and Bryson, J. W., " Design Criteria for Pip-USNRC Report NUREG/CR-4305, U.S. Nuc! car Regu.
ing and Nozzles Program Quarterly Progress Report for latory Commission, Washington, D.C., August 1985.
July-September 1976," ORNI Report ORN!JNUREG/
TM-107, Oak Ridge National Iahoratory, Oak Ridge, Simonen, F. A. and Goodrich, C. W., " Parametric Calcu-TN, April 1977, lations of Fatigue Crack Growth in Piping " USNRC Re-port NUREG/CR-3059, U.S. Nuclear Regulatoy Com-Moore, S. E. and Uryson, J. W., " Design Criteria for Pip-mission, Washington, D.C., March 1983, ing and Nonles Program Quarterly Progress Report for October-December 1976." ORNL Report ORNL1 Simonen, F. A. et al., " Crack Growth livaluation for NUREGffM-144, Oak Ridge National I aboratory, Oak Small Cracks in Reactor-Coolant Piping," USNRC Re-Ridge, TN, September 1977.
port NURI G/CR-3176, U.S. Nuclear Regulatory Co:n-mission, Washington, D.C., April 1983.
Moore, S. E. and Mershon, J. L, " Design Criteria for the Spacing of Nonles and Reinforced Openings in Cylindri-Strosnider. J., J r., ed.," Proceedings of the CSNI Special-cal Nuclear Pressure Vessels and Pipe," USNRC Report ist Meeting on Leak-Heiore-Break in Nuclear Reactor NUREG/CR-2308, U.S. Nuclear Regulatory Commis-Piping," USNRC Conference Proceedings NUREG/
sion, Washington, D.C., February 1982.
CP-0051, U.S. Nuclear Regulatory Commission, Wash-ington, D.C., August 1984.
Reynolds, M. H.. " Fracture MerSanics and the Stability of lingineering Structures " Gl' deport GEAP-4678, Gen-Tagart, S. W., " Mechanical Design Considerations in Pri-eral Electric Corporation, San Jose, CA. September mary Nuclear Piping " GE Report G EAP-4578 General i
1965.
Electric Corporation, San Jose, CA, March 1964.
I
{
l NURl!G-1426 L
Compilation of Reports-1965-1990 Wilson, S. A.,"listimating Pipe Reliability by the Distri-press lleport," llattelle Report llMI-1853, llattelle bution of Time to Damage M e thod," Gli Report Memorial Institute, Columbus, Oll, November 196S.
GliAP-10452, General lilectne Corporntion, San Jose, CA, March 1972.
liiber, It. J. et al., "lovestigation of the Initiation and lix-tent of Ductile Pipe Rupture, Phase i 1 irn! Report," llat-Wilson, S A., "listimating the Itelative P,obability of telle Reput itMI-1866, llattelle Memorial Institute, Co-Piping Severance Ily 1 ault Cause," Gli Report lumbus, 011. J uly 1969.
GliAP-20615, General !!!cctric Corporation, San Jose, CA, September 1974.
!!iber, R. J. et al.," Investigation of the initiation and lix-tent of Ductile Pipe Rupture, May-September 1969 Pro-gress steport," llattelle Report ilMI-1873, llattelle l'ipirig: Experittiental Memorial Institute, Columbus,011, October 1969.
Ahmad, J. et al.,"lilastic Plastic I inite filement Analysis liiber 11. J. et al.," Investigation of the initiation and lix-of Crack Growth in 1 arge Compact Tension and Circum-tent of Ductile Pipe Rupture-Phase !!, January-March ferentially Through Wall. Cracked Pipe Specimen,"
1970 Progress lleport," llattelle Report ilMI-ISSO, llat-USNRC Report NURl!G/ Cit-4573.U.S. Nuclear Regu' telle Memorial Institute, Columbus,011, April 1970.
latory Commission, Washington, D.C., October 19h6.
liiber, R J. et al.," Investigation of the initiation and lix-AIAcimer, J M. et al., " Pipe-to-Pipe impaa Program,"
tent of Ductile Pipe Rupture-Phase 11, April-June 1970 PNI Iteport PNic4954, Paafic Northwest I ahoratory.
Progress Iteport," llattelle Report llMI-1887, llattelle Richland, W A,1984.
Memorial lustitute, Columbus,011, July 1970.
Al/hcimer, J.
M.,
" Pipe-to-Pipe impact Program,"
liiber, R. J. et al.. " investigation of the Initiation and lix-USNRC Report NUllEG/CR-3231, U.S. Nuclear Repu-tent of Ductile Pipe Rupture-Phase 11 July-September latory Commission, Washington, D.C., May 19S7.
1970 i rogress Report,"llattelle Report ilMI-1892, llat.
telle Memorial Institute, Columbus,011, October 1970.
11rothers, A. J.,"l'aligue Crack Growth in Nu:lcar Reac-tor Piping Steels," Gli Report Gl!AP-5607, General liiber, R. J. et al.," Investigation of the initiation and lix-lilectnc Corporation, San Jose, CA, March 1968.
tent of Ductde Pipe Rupture-Phase 11 October-Dccember 1970 Progress Report," llattelle Report Ilrothers, A. J., " tow-Cycle, Strain-Controlled Fatigue llMI-1902, llattelle Memorial Institute, Columbus, Oll, Crack Propagation in Nuclear Piping Steels," Gli Report January 1971.
GliAP-10181, Gen"ral filectric Corporation, San Jose, CA, May 1970.
liiber, R. J., Maxey, W. A., and Duffey, A. R.,"investiga-tion of the Initiation and lixtent of Ductile Pipe Rup-liiber, R. J. et al.,"In estigation of the initiation and lix-ture,"llattelle Report ilMI-1908,liattelle Memorialin-tent of Ductile Pipe Rupture, May-December 1966 Pro-stitute, Columbus,011,1971.
gress Report," llattelle Report llMI-1793, Itattelle Memori;d Institute, Columbus,011, January 1967.
Greemtreet, W l, "lixperimental Study of Plastic Resporses of Pipe lilbows," ORNI. Report ORNil liiber, R.J. et al.," Investigation of the Initiation and fix-NURl!G-24, Oak RiJge National laboratory, Oak tent of Dt.ctile Pipe Rupture, Jidy-September 1967 Pro-Ridge, TN, I ebruary 1978.
gress Report," llattelle Report ilMI-1817, llattelle Memorial Institute, Columbus,011, October 1967.
Ilate, D. A.," Reactor Primary Coolant System Pipe Rup-ture Study, Progress Report No. 30, July-December liiber, R. J. et al., " Investigation of the initiation and lix-1973." Gli Report Gl!AP-10207-30. General lilectric tent of Ductile Pipe Rupture, January-March 1968 Pro-Corporation, San Jose, CA, March 1974.
gress Report," llattelle Report ilMI-1836, flattelle Memorial Institute, Columbus, Ol1, April 1968.
Itale, D. A.," Reactor Primary Coolant System Pipe Rup-ture Study, Progress Report No. 31, January-June 1974,"
liiber, R. J. et al.," investigation of the initiation and lix-Gli Report Gl! AP-10207-31, General lilectric Corpora-tent of Ductile Pipe Rupture, April-June 1968 Progress tion, San Jose, CA, September 1974.
Repor"," llattelle Report ilMI-1847, llattelle Memorial Institute, Columbus,011 July 1968.
I f ale, D. A.," Reactor Primary Coolant System Pipe Rup-ture Study, Progress Report No. 32, July-December liiber, R. J. et al.,"Investipation of the Imtiation and fix-1974 " Gli Report GliAP-10207-32, General lilectric tent of Ductile Pipe Rupture, July-September 1968 Pro-Corporation, San Jose, C A, March 1975.
i l
l 33 N URl!G-1426
Compilation of iteports-1965-1990 1 late D. A.,"l;eactor Primary Coolant System Pipe Rup-Nuclear Regulatory Commission, Washington, D.C.,
ture Study, Progress Report No. 33, January-J une 1975,"
N1ay 1987.
Gli Report G liAP-10207-33, General lilectric Corpora.
tion, San Jose, CA, October 1975, lliser, A.1-, " Fracture Toughness Characternation of Nuclear Piping Steels," USNRC Report NURl!G/
Ilate, D. A.,
- Reactor Primary Coolant System Pipe Rup.
CR-5188, U.S. Nuclear llegulatory Commission, Wash-ture Study, Progress Report No. 34, July-December ington, D.C., November 1989.
1975," Gli Report Gl!AP-10207-34, General lilectric Corporation, San Jose, CA, February 1976.
Kanninen, hl. F. et al.,"The Development of a Plan for the Assessment of Degraded Nuclear Piping by lixperi-Ilale, D. A.," Reactor Primary Coolant System Pipe Rup.
mentation and Tearing Instability Fracture Alechanics ture Study, Progress Report h 35, January-Niarch Analysis," USNPC Report NURl:G/CR-3142 Vol. I and 1976," Gli Report Gl!AP-10207-35, General lilectric
- 2. U.S. Nuclear Regulatory Commission, Washington, Corporation, San Jose, CA, hiay 1976.
D.C., June 1983.
llale D. A.," Reactor Primary Coolant System Pipe Rup.
Kashima, K. and Wilkowski, G. 51., eds., " Proceedings of ture Study, Progress ~ ' ort No. 36, April-June 1976,"
the Seminar on 1 liAK lllil ORl!-ilRl!AK: Progress in Gli Report Gl!AP-NUill!G-10207-36, General I!!ce.
Regulatory Policies and Supporting Research," USNRC tric Corporation, San Jose, CA, September 1976.
Conference Proceedings NURl!G/CP-0092, U.S. Nu.
clear Regulatory Commission, Washington, D.C., h1 arch Ilate, D. A.." Reactor Primary Coolant System Pipe Rup-1988-ture Study, Progress Report No. 37, July-September 1976," Gli Report Gl!AP-10207-37, General lilectric Kilsby, !!. R., "A Survey of Water Reactor Primary Sys-Corporation, San Jose, CA, November 1976.
tem Conditions Pertinent to the Study of Pipe," Gli Re-port GliAP-4445, General lilectnc Corporation, San Ilate, D. A.." Reactor Primary Coolant System Pipe Rup.
Jose, CA, January 1964, ture Study, Progress Report No. 3S, October-December 1976," Gli Report Gl!AP-10207-38, General I!!cctric Kdsby,li. R.," Reactor Pomary t,oolant System Rupture Corporation, San Jose, CA, February 1977.
Study, Quarterly Progress Report No.1, Apnt; June 1965 " Gli Report Gli AP-4911, General lilectric C orpo-Ilate, D. A.," Reactor Primary Coolant System Pipe Rup_
ranon, San Jose, CA, J uly 1965.
ture Study, Propiess Report No. 39, January-h1 arch 1977, Gli Report Glial-10207-39, General lilectric K !sby,!!. R.," Reactor Pnmary Coolant System Rupture
' "b, Gli Report Gli AP-4964, General llectric L orpo-
"U N"U
' P""
"' ~,, u h.-
mber Corporation, San Jose, CA, N1ay 1977.
- 1965,
'" U "" ' "" "', CA, October 1965.
Ilate, D. A.," Reactor Primary Coolant System Pipe Rup-ture Study, Progress Report No. 40, April June 1977 "
y Gli Report Gl!AP-NURIiG-10207-40, General lilec-Kilsbp IL R," Reactor Primary Coolant System Rupture Study, Quarterly Progrevs Report No. 3, October-tric C orporation, San Jose, CA August 1977.
1)ecember 1965[" Gli Report GliAP-5082, General llays, R. A., Vassilaros, bl. G., and Gudas, J. P.. " Frac.
ture Analysis of Welded Type 304 Stainless Steel Pipe "
Kiss,l!.," Reactor Primary Coolant System Pipe Rupture USNRC Report NURFG/CR-4538 Vol.1. U.S. Nuclear Regulatory Commission, Washmgton, D.C., February Study, Progress Report No. 27, Ap'ril-June 1972," Gli M 6.
Report Gli AP-10207-27, General lilectric Corporation, San Jose, CA, July 1972.
IlealJ, J. D. and Kiss, ii., "t w Cycle Fatigue of Proto-Kiss, li. " Reactor Primary Coolant System Pipe R upture type Pipe Components " Gli Report GliAP-10763, Gen-Study, Progress Report No. 28, July-December 1972,'
eral lilectric Corporation, San Jose, CA, January 1973.
Gli Report Gl! AP-10207-28. General lilectric Corpora-Ifebble,T. l et al.," Analysis of Delta. Ferrite Data from Production Stainless Steel Pipe Welds," USNRC Repert Kiss, H. " Reactor Primary Coolant System Pipe Rupture NURl!G/CR-34S2, U.S. Nuclear Regulatory Commis-Study, Progress Report No. 29, January-June 1973," Gli sion, Washington, D.C., January 1984.
Report Gl! AP-10207-2S, General Ek ;tne Corporation, San Jose, CA. August 1973.
Iliser, A. l.. and Callahan, G. N1.,"A User's Guide to the N R C's Pipmg Fracture hicchanics Data liase Klepfer. II. II., "laperimental and Analytical Program (Pil RACV USNRC Report NURiiGICR-4h44. U.S.
Recommendations-Reactor Pipe Rupture Study," GE l
N U R EG-1426 34
Compilation of Repirts 1965-1990 Repnt Gl: AP-4474, General lilectne Corporation, San January-hiarch 1966," Gliiteport Gl!AP-514', General Jose, CA, January 1965.
lilectric Corpnation San Jose, CA. Apnl 1966.
Kramer,G.and Papaspyropoulos V.,"An Assessrnent of Vandenberg, S. it., " Reactor Primary Coolant System Circumfertntially Complex Cracked Pipe Subjected to Rupture Study, Quarterly Progress Report No. 5, April-Bending," USNRC lleoort NURl!G/CR-46S7, U.S. Nu, June 1966," Gli iteport GliAP-5192, General Electric clear Regulatory Coimm.,sion, Washington, D.C., Octo-Corporation, San Jose, CA, August 1966.
ber 19S6.
Vandenberg, S. R., " Reactor Primary Ctulant System Nakagaki, h1., hiarschall, C. W., and lirust, it, " Analysis Rupture Study, Quarterly l'rogress Report No. 6. July-of Cracks in Stainless SteelTIG Welds," USNRC Report September 1966." Gli Report Gl!AP-5279, General NURl!GICR-4806, U.S. Nuclear Regulatory Commis.
lilectric Corporation, San Jose, CA, November 1966.
l sion, Washington, D.C., December 1986.
Vandenberg, S. R., " Reactor Primary Coolant System lhllasek, R. J. and liiber, R. J., " investigation of hiode Rupture Study, Quarterly Progress Report No. 7, 111 Crack lixtension in Reactor Piping," llattelle Colum.
October-December 1966," GH Report Gl!AP-5427, bus laboratory Report to Oak Ridge National labora.
General l'.lectric Corporation, San Jose, CA,1:ebruary 1967.
tory for the Ai!C, December 1973, Podlasek, R. J. and liiber, R.J.,"I'inal Report on Investi.
Vandenhag, S. R, " Reactor Primary Ctulant SyMt m gation of hiode 111 Crack lixtension in Reactor Piping,"
Rupture Study, Quarterly Progress Report No. 8, llattelle Columbus laboratories, Columbus, Oil, De.
January-March 1967," Gl! Report Gl!AP-5474, General cember 1973.
lilectric Cor poration, San Jose, CA, h1ay 1967.
Van enberg, S. R., " Reactor Primary Coolant System Reynolds, M.11., "l racture Toughness of Some Engi-necting Alloys," Gli Report GEAP-5014, General Elec, uptun',9u@, Quannh Woge Rgt No. 9, Apnb NCP"" Gl!AP-5512, General filectric tric Corporation, San Jom, C A, March 1966.
k( o"r"poration San Jose, L,A August 1967.
Reynolds, M.11., " Failure llehavior in ASTM A10611 Vandenberg, S. R., "Reactm Primary Coolant System Pipes Contammg Axial Through-Wall l' laws," Gli Re-Rupture Study, Quarterly Progress Report No.10, July-port G11AP-5620, General lilectric (orporation, San September 1967," Gli Report Gl!AP-5554, General Jose, (,A, Apnl 1968.
tilectric Corporation, San Jose, CA, December 1967.
Reynolds, M.11., " Failure lichaviar of I lawed Carbon Vandenberg, S. R., " Reactor Pnmary Coolant System Steel Pipes and Fittings," Gli Report GliAP-10236, Rupture Study, Quarterly Progress Report No. 11.
General filectric Corporation, San Jose, CA, October October-December 1967 " Gl! Report Gi!AP-5587, 1970.
General filectric Corporation, San Jose, CA, March 1968.
Scott, P, M. and llrust, F. W., "An lixpenmental and Analytical Assessment of CircumferentialThrough-Wall Vandenberg, S. R., " Reactor Primary Coolant System Cracked hpes Under Pure Hending," USNRC Report Rupture Study, Quarterly Progress Report No. 12, NUREG/CR-4574, U.S. Nuclear Regulatory Commis' January-March 1968," Gl! Report Gli AP-5637, General sion, Washington, D.C., September 1986.
lilectne Corporation San Jose, CA, June 1968.
Scott, P. M and Ahmad, J, A.,"lixperimental and Ana-Vandenberg, S. R., " Status of Pipe-llupture Study at lytical Assessment cJ Circumferentially Surface-Cracked General lilectric-II," Gli Report GliAP-5653, General Pipes Under llending," USNRC Report NUREG/
Idectric Corporation, San Jose, C A, July 1968.
CR-4872, U.S. Nuclear llegulatory Commission, Wash-ington, D.C., April 1987, Vandenberg, S. R., " Reactor Primary Coolant System Rupture Study, Quarterly Progress Report No.13, April-Scott, P. M.," Assessment of Design Basis for 1.oad-Car-June 1968," Gli Report Gl!AP-5680, General f!lectric rymg Canacity of Weld Overlay Repairs," USNRC Re-Corporation, San Jose, CA, September 1968.
port Nb.IliG/CR-4877, U.S. Nuclear Regulatory Com-mission. Washmpton, D.C, April 1987.
Vandenberg, S. R,, " Reactor Primary Coolant System Rupture Study, Quarterly Progress Report No.14 July-Vandenberg, S. R., " Reactor Primary Coolant System September 196S " Gli Rep >rt GEAP-5716, General Rupture Study, Quarterly Progress Report No. 4, Electric Corporation, San Jose, C A, December 1968.
35 NUREG-1426
Compilation of Reports-1965-1990 Vandenberg, S. R.,
- Reactor Primary Coolant System Vandenberg, S. R.,
- Reactor Primary Coolant System Rupture Study, Quartetiy Progress Report No.15.
Rupture Study, Quarterly Report No. 25, J uly-October-December 196S," Gli Report GliAP-5770, September 1971," Gli Report Gli AP-10207-25, General lilectric Corporation, San Jose, CA, h1 arch General lilectric Corporation, San Jose, CA, October 1969.
1971.
Vandenberg S. R., " Reactor Primary Coolant System Vandenberg, S. it., " Reactor Primary Coolant System Rupture Study, Quarterly Progress Report No. 16, Rupture Study, Progress Report No. 19, October January-htarch 1969," Gli Report GEAP-10024, Gen.
1971-htarch 1972," Gli Report GEAP-10207-26, Gen-eral lilectric Corporation, San Jose, CA, April 1969 eral lilectric Corporation, San Jose, CA, April 1972.
Vandenberg, S. R., " Reactor Primary Coolant System Vawdaros, hl. G. et al., "J-Integral Tearing instability for Rupture Study, Quarterly Progress Report No.17, April _
8 Inch Diameter ASThl A106 Steel Pipe " USNRC June 1969," Gli Report Gl! AP-10072, Generallilectric Report NURliG/CR-3740, U.S. Nuclear Regulatory Corporation, San Jose, CA, July 1969.
Commission, Washington, D.C., h1 arch 1984.
Wdkowski, G. bl. et al., " Degraded Piping Program-Vandenberg, S. R., " Reactor Primary Coolant System Phase 11 Semiannual Report, h1 arch 1984-September Rupture Study, Quarterly Progress Report No.18, July-1984." USNRC Report NUREG/CR-4082, Vol.1, U.S.
]
September 1969," GE Report Gl!AP-10120, General Nuclear Regulatory Commission, Washington, D.C.,
lilectric Corporation, San Jose, CA, October 1969 January 1985.
Vandenberg, S. R., " Reactor Primary Coolant System Wdkowski, G. hl. et al., " Degraded Piping Program-Rupture Study, Quarterly Progress Report No.19 Phase 11, Semiannual Iteport, October 1954-htarch October-December 1969," Gli Report Gl!AP-10143.
1985," USNRC Report NUltEG/CR-4082. Vol. 2, U.S.
General Electric Corporation, San Jose, CA, January N uclear Regulatory Commission, Washington, D.C., J uly 1970.
1955.
Vandenberg, S. R., " Reactor Primary Coolant System Rupture Study, Quarterly Report No. 20, January-htarch Wilkowski, G. N1. et al., " Degraded Piping Program-1970," Gli Report GliAP-11069, General lilectric Cor-Phase H, Semiannual Report, April 1985-September poration, San Jose, CA, April 1970.
1985," USNRC Report NUREG/CR-4082, Vol. 3, U.S.
Nuclear Regulatory Commission, Washington, D.C.,
Vandenberg, S.
R., "Sti.tus of Pipe-Rupture Study N1 arch 1986.
at General Electric Company-lll," Gli Report GEAP-10205, General Electric Corporation, San Jose, Wilkowski, G. hi. and h1ayfield, hl. l!. eds.," Proceedings CA, June 1970.
of the Seminar on LliAK-Bl! FORE-IIREAK: Interna-tional Policies and Supporting Research," USNRC Con.
Vandenberg, S. R., " Reactor Pnmary Coolant System ference Proceedings NUREG/CP-0077, U.S. Nuclear Rupture Study, Quarte ly Report No. 21, April-June Regulatory ( ommission, Washington, D.C., June 1986.
1970," Gli Report GEAP-10207, General Electric Cor-poration, San Jose, CA, July 1970.
Wilko vski, G, h1. et al., " Degraded Piping Program-Phase 11, Semiannual Report, October 1985-hiarch Vandenberg, S. R., " Reactor Pnmary t,oolant System 1986," USNRC Report NUREG/CR-4082, Vol. 4, U.S.
Rupture Study, Quarterly Report No. 22, J uly-Nuclear Regulatory Commission, Washington, D.C.,
Sep?mber 1970 " GE Report GliAP-10207-22, Gen.
September 1986.
eral Electric Corporation, San Jose, CA, October 1970.
Wilkowski, G. h1. et al., " Degraded Piping Program-Vandenberg, S. R., " Reactor Primary Coolant System Phase II, Semiannual Report, April 1986-September Rupture Study, Quarterly Report No. 23, October-1986," USNRC Report NUREG/CR-40S2, Vol. 5, U.S December 1970," GE Report GliAP-10207-23, General Nuclear Regulatory Commission, Washington, D.C.,
Electric Corporation, San Jose, CA, January 1971.
April 1987.
Vandenberg, S. R., " Reactor Primary Coolant System Wilkowski, G. hl. et al., " Analysis of Expenments on Rupture Study, Progress Report No. 24. January-June Stainless Steel Flux Welds," USNRC Report NURl!G/
1971,* GE Report GEAP-10207-24, General Electne CR-4878, U.S. Nuclear Regulatory Cornmission, Wash.
Corporation, San Jose, CA, July 1971.
ington. D.C., April 1987.
1 NURl!G-1426 3h
Compilation of Reports-1965-1990 Wilkowski, G. M. et al., " Degraded Piping Program-Childress, C. II.,
- Fabrication IIistory of the Third Phase 11, Sixth Program Report, October - 1986-and Fourth AS'thi A-533 Steel Plates of the licasy-September 1987 " USNRC Report NURl!G/CR-4082, Section Steel Technology Program," USAIIC Report Vol. 6, U.S. Nuclear Regulatory Commission, Washing-ORNL-4313-2, Oak Ridge National laboratory, Oak ton, D.C., April 1988.
Ridge, TN, February 1970.
Wilkowski, G. M. et al., " Degraded Piping Program _
Childress, C. II., " Fabrication Procedures and Accep-
. Phase 11, Seventh Program Report, October tance Data for AS'Ihl A-533 Welds and a 10-in. thick 1987-December 1988," USNRC Report NURiiG/
ASThi A-533 Plate of the Heavy-Section SteelTechnol-CR-4082, Vol. 7, U.S. Nuclear Regulatory Commission, ory Program," Documentary Report 3, USAliC Report Washington, D.C., March 1989.
ORNL-4313-3, Oak Ridge National laboratory, Oak Ridge, TN, January 1971.
Wilkowski, G. M. et al., " Degraded Piping Prograrn-Childress, C. II., " Manual for ASTM A-533 Grade 11 Phase 11, Summary of Technical Results and Their hig' nificance to 1 cak.llefore llreak and in. Service Flaw Class 1 Steel (llSST Plate 03) Provided to the Interna-Acceptance Criteria-Fir.al Program Report, March tional Atomiclinergy Agency," USA 11C Report ORNL-1984-January 1989," USNRC Report NURl!G/
TM-3193, Oak Ridge National laboratory, Oak Ridge, TN, March 1971.
CR-4082, Vol 8, U.S. Nuclear Regulatory Commission, Washington, D.C., March 1989.
Childress, C, E., " Fabrication and Mechanical Test Data for Acceptance of the First Six 6-Inch-Thick Intermediate Wilkowski, G. M and Chao, K. S., eds., " Proceedings of Test Vessels of the Heasy-Section SteelTechnology Pro-the Seminar on LilAK-IlliFORE IlREAK: Further gram," USAEC Report ORNI/Ihi-4351, Oak Ridge Developments in Regulatory Policies and Supporting -
National laboratory, Oak Ridge, TN, October 1973.
Research," USNRC Conference Proceedings NUREG/
CP-0109, U.S. Nuclear Regulatory Commission, Wash-Childress, C. I!. " Fabrication and Mechanical Test Data ington, D.C., February 1990.
for the Four 6-Inch-Thick Intermediate Test Vessels Made from Steel Plate for the HeavySection Steel Tech-nology Program," Documentary Report 5,ORNic Pressure T,essel Steels TM-5074, Oak Ridge National Ialmratory, Oak Ridge, TN, January 1976.
Canonico, D. A., " Transition Temperature Considera-tions for Thick-Wall Nuclear Pressure Vessels," US AEC Cook, K. V. and McClung, R. W., " Flaw Density lixami-Report ORNL-TM-3114. Oak Ridge National Labora-nations of a Clad Boiling Water Reactor Pressure Vessel tory, Oak Ridge, TN, October 1970.
Segment," USNRC Report NURI!G/CR-4860 Rev.1, U.S. Nuclear Regulatory Commission, Washington, Canonico, D. A. and llerggren, R. G., " Tensile and Im.
D.C., February 1988.
pact Properties of'lhick-Section Plate and Weldments,"
USAliC Report ORNI/Ihi-3211, Oak Ridge National Cook, K. V., Cunningham, Jr., R. A., and McClung, R.
I lateratory, Oak Ridge, TN, January 1971.
W., " Detection and Characterization of Indications in l
Segments of Reactor Pressure Vessels," USNRC Report NUREG/CR-5322, U.S. Nuclear Regulatory Commis-Canonico, D. A. et al., "Use of Instrurnented Charpy Tests to Determine Onset of Upper-Shelf Energy,"
sion, % ashington, D.C., August 1989.
ORNL 13eport ORNL-5086, Oak Ridge National labo-ratory, Oak Ridge, IN, November 1975.
Did n R, "Ihu-2 Vessel Investigation Project (VIP) Metallurgical Program, Progress Report January-September 1989 " USNRC Report NUREG/CR-5524 -
Canonico, D. A., " Significance of Reheat Cracks to the
-Vol.1, U.S. Nuclear Regulatory Commission, Washing-Integrity of Pressure Vessels for Light Water Reactors "
ton, D.C., March 1990.
ORNL Report ORNIJNUREG-15, Oak Ridge National laboratory, Oak Ridge, TN, July 1977.
Diercks, D. R., "Ihu-2 Vessel Investigation Project (VIP) Metallurgical Program, Progress Report October Childress, C. E., " Fabrication History of the First Two 1989-June 1990," USNRC Report NUREG/CR-5524 12-In. Thick ASTM A-533 Grade 11, Class i Steel Plates Vol. 2, U.S. Nuclear Regulatory Commission, Washing-of the Heavy Section Steel Technology Program," Docu-ton, D.C., November 1990.
mentary Report 1 USAEC Report ORNic4313. Oak Ridge National Iahoratory, Oak Ridge, TN. February Goodwin, G. M. and Nanstad, R. K. "liffect of Tempera-1469.
ture on the Stress-Relaxation Response of a Pressure -
37 N URf!G-1426
l Compilation of Reports-1965-1990 i
Vessel Steel " USNRC Report NURl!G/CR-3728, U.S.
IISSTP-TR-19, TRW Systems Group, Redondo lleach, Nuclear Regulatory Commission, Washmpton, D.C., Oc-CA, June 1972.
tober 1984.
Shabbits, W. O., Pryle W. I1., and Wessel,11. T., *1leavy-llobson, D. O. and Nanstad, R. K., " Effects of Off-Section Fracture Toughness Properties of A533 Grade ll Specification Procedures on the hicchanical Properties of Class 1 Steel Plate and Submerged Arc Weldment," Wes-Italf llead Weld Repairs," USNRC Report NURFG/
tinghouse Report WCAP-7414, Westinghouse lilectric CR-3265. U.S. Nuclear Regulatory Commission, Wash.
Corporation, PWR Systems Divison, Pittsburgh, PA, De-ington, D.C., July 1983.
cember 1969.
Klier, li, P., llawthorne, J. R., and Steele, l_11., "The Shabbits, W. O., " Dynamic Fracture Toughness Proper-Tensile Properties of Selected Steels for Use in Nuclear ties of Ileasy Section A533 Grade 11 Class 1 Steel Plate,"
Reactor Pressure Vessels " NRL Report 6649, Naval Re-Westinghouse Report WCAP-7623, Westinghouse lilec-search Iahoratory, Washington, D.C., December 1967.
trie Corporation, PWR Systems Dwision, Pittsburgh, PA, December 1970.
Klindt, K. K.and Canonico, D. A.,"livaluation of Discon-tinuiFes in llSSTTwelve-Inch-Thick Plate," US AliC Re-Stallmann, F. W., " Theory and Practice of General Ad-port ORNL-TM-4155, Oak RiJge National l aboratory, justment and Model Fitting Procedures," USNRC Re-Oak Rid:;e, TN, June 1973.
port NURiiG/CR-2222, U.S. Nuclear Regulatory Com-mission, Washington, D.C., December 1981.
I egge, S. A., "Analy sis and 11xperimental Verification of the Thermal llehavior of a Four inch Steel Section Stallmann, F. W.," Curve Fitting and Uncertainty Analy-Undergoing Nuclear lleating," Westinghouse Report sis of Charpy lmpact Data" USNRC Report NURiiG/
WCAP-8022, Westinghouse Electric Corporation, Pitts.
CR-2408, U.S. Nuclear Regulatory Commission, Wa.h.
burgh, PA, December 1972, ington, D.C., January 1982.
loss, F. J., " Dynamic Tear Test Investigations of the Steltman, W. J., llerggren, R. G., and Jones, T. N.,
Fracture Toughness of Thick Se: 'on Ste'el," NRL Re, "ORNL Characterization of Ileavy-Section Steel Tech-port 7056, Naval Research I.aboratory, Washington, nology Program Plates 01,02 and 03," USNRC Report D.C., May 1970.
NURiiG/CR-4092, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., April 1985.
Lundin, C, D. and Mohammed, S., "Effect of Welding Conditions on Transformation and Properties of I-leat-Williams, J. A., "The Ductile Fracture Toughness of Affected Zones in LWR Vessel Steels," USNRC Report Ileasy Secti a Steel Plate " USNRC Report NURl!G/
CR-0859 U.S. Nuclear Regulatory Commission, Wash-NURI!G/CR-3873, U.S. Nuclear Regulatory Commis.
sion, Washington, D.C., November 1989.
ington, D.C., September 1979.
Mager, T. R., " Fracture Toughness Characteruation Radiation Embrittlement Study of A533, Grade 11, Class 1 Steel." Westinghouse Report WCAP-7578, Westinghouse lilectric Corpora-Baldwin, C. A.," Neutron Spectral Characterization Cal-tion, PWR Systems Division, Pittsburgh, PA, October culations for the Fourth Nuclear Regulatory Commission 1970.
IIcavy Section Steel Technology IT-Cl' trradiation Ex-periments," USSRC Report NURl!G/CR-3311, U.S.
Pennell, W. li and Pugh, C. E., " Mission Survey for the Nuclear Regulatory Commission, Washington, D.C.,
Pressure Vessel Research Users' Facihty (PVRUF),"
June 1983.
USNRC Report NURiiG/CR-5350, U.S. Nuclear Regu-latory Commission, Washington, D.C., June 1989.
Baldwin, C. A., Kam, F.11. K., and Stallmann, F. W.
" Neutron Spectral Characteruation for the Fifth Heavy Randall, P. N., " Gross Strain Measure of Fracture Section Steel Technology (HSST) Irradtation Series Toughness of Steels,"TRW Report ilSSTP-TR-3,TRW
' Simulator Experiments'," USNRC Report NUREG/
Systems Group, Redondo Beach, CA, November 1969 CR-4031, Vol.1, U.S. Nuclear Regulatory Commission, Washington, D.C., November 1984.
Randall, P. N.,"G ross Strain CrackTolerance of A533-B Stee!," TRW Report DSSTP-TR-14 TRW Systems Haldwin, C. A.," Quality Assurance Assessment / Plan for Group, Redondo Heach, CA, May 1971.
the Fifth lleavy Section Steel Technology (IISST) Irra-diation Study ' Neutron Exposure'," ORNL Report OP-Randall, P. N.," Effects of Strain Gradients on the Gross TS-O AA-1, Oak Ridge National l aboratory, Oak Ridge, Stram Crack Tolerance of A533-B Steelf TRW Report TN, December 1984.
NURiiG-1426 38
Compilation of Reports-1965-1990 Cheverton, R. D. et al., " Impact of Radiation limbritt-llawthorne, J. R. and loss, F. J., "The liffects of Cou.
lement on Integrity of Pressure Vessel Supports for Two pling Nuclear Radiation with Static and Cyclic Service PWR Plants " USNRC Report NURiiG/CR-5320, U.S.
Stresses and oI Periodic Proof Testing on Pressure Vessel Nuclear INulatory Commission, Washington, D.C.,
hlaterial llehavior," NRI Report 6620, Naval Research January 1909 laboratory, Washington, D.C., August 1967.
Clarke, G. A.,"An livaluation of the Unloading Compli.
Ilawthorne, J. R. and I oss, F. J., " Availability of Data on ance Procedure for J Integral Testing in the f lot Cell, Fi.
Irradiated hiaterials as Related to Design Requirements nal Report," USNRC Report NURiiG/CR-1070. U.S.
for Water Cooled Reactor Pressure Vessels," NRI. Re-Nuclear Regulatory Commission, Washington, D.C., Oe, port 6625, Naval Research Iaboratory, Washington, tober 1979.
D.C., August 1967.
Corwin, W. R.," Assessment of Radiation liffects Relat-Ilawthorne, J. R. and Watson,11. E., *llot Cell liquip-ing to Reactor Pressure Vessel Cladding " USNRC Re-ment Developed for Remote 'lension rest Specimen port NURiiG/CR-3671 U.S. Nuclear Regulatory Com-livaluations at NRt. " NRI. Report 6765, Naval Research mission Washington, D.C., July 1984.
laboratory, Washington, D.C., November 1968.
Ilawthorne, J. R., Koziol, J. J., and Ilyrne, S. T., "livalu-Corwin, W. R., Berggren, R. G., and Nanstad, R. K" ation of Commercial Production of A 533-il Steel Plates "Charpy Toughness and Tensd.e Properties of Neutron and Weld Deposits with Extra low Copper Content for
\\
Irradiated Stainless Steel Submerged-Arc, Weld Cladding Radiation Resistance," NRI Report 8136, Naval Re-Overlay," USNRC Report NURiiG/CR-3927, U.S. Nu-search laboratory, Washington, D.C., June 1977.
clear Regulatory Commission, Washington, D.C., Sep-tember 1984.
llawthorne, J. R., "lixploratory Imestigations of low Charpy-V Upper Shelf Steels with Irradiation," NRL Corwin, W. R.,"1leavy-Section Steel Irradiation Program Report 8171, Naval Research Iaboratory, Washington, Semiannual Progress Report for October 1989-htarch D.C., December 1977.
1990," USNRC Report N URl!G/CR-5591, Vol.1, No.1.
U.S. Nuclear Regulatory Commission, Washington, Ilawthorne, J. R., " Significance of Copper, Phosphorus, D.C., August 1990.
and Sulfur Content to Radiation Sensitivity and Postirra-diation Heat Treatment of A 302-H Steel," USNRC Re-Davidson, J. A. et al.,The Irradiated Dynamic Fracture port NUREGICR-0327, U.S. Nuclear Regulatory Com-Toughness of ASTH 1 A533, Grade H, Class 1 Steel Plate mission, Washington, D.C., April 1979.
and Submerged Arc Weldment," Westinghouse Report WCAP-8775, Westinghouse lilectric Corporation, Pitts.
Ilawthorne, J. R., " Notch Ductility Degradation of Iow burgh, PA, October 1976.
A!!oy SteelsWith low-to-intermediate Neutron Fluence Exposures," USNRC Report NUREG/CR-1053, U.S.
Ebrahimi, F. et al.,"Developmen af a hiechanistic Un.
Nuclear Regulatory Commission, Washington, D.C., Oc-derstanding of Radiation limbrittement in Reactor Pres, tober 1979, sure Vessel Steels-Final Report,"_ USNRC Report NUREG/CR-5063, U.S. Nuclear Regulatory Commis-I lawthorne, J. R.," Evaluation of I AliA Coordinated Pro-sion, Washington, D.C., January 1988.
gram Steels and Welds for 288'C Radiation Embrittle-ment Resistance," USNRC Report NUREG/CR-2487, Guthrie, G. L and Simonen, E. P., " Correlation Hetween U.S. Nuclear Regulatory Commission, Washington, Power and Test Reactor Data Bases " USNRC Report C, FeMuary 1982.
NUREG/CR-5328, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., February 1989.
Ilawthorne, J. R., " Status of Knov< ledge of Radiation Embrittlement in USA Reactor Pressure Vessel Steels,"
USNRC Report NUREG/CR-2511. U.S. Nuclear Regu-Haggag, F. hl., Corwin, W. R., and Nanstad, R. K., "Irra-diatton Effects on Strength and Toughness of Three. Wire latory Commission, Washington, D.C., February 1982.
Series-Arc Stainless Steel Weld Overlay Cladding,"
flawthorne, J. R., "Sigmficance of Nickel and Copper USNRC Report NUREG/CR-5511. U.S. Nuclear Regu-Content to Radiation Sensitivity and Postirradiation ileat latory Commission, Washington, D.C., February 1990.
Treatment Recovery of Reactor Vessel Steels," USNRC Report NURl!G/CR-2948, U.S. Nuclear Regulatory 11awthorne, J. R. et al.," Radiation Damage Surveillance Commission, Washington, D.C., November 1982.
of Power Reactor Pressure Vessels," NRI. Report 6349, Naval Research laboratory, Washington, D.C., January Hawthorne, J. R., hienke, H. H., and Iliser, A. !," Light 1966.
Water Reactor Pressure Vessel Survulance Dosimetry 39 NURIO-1426 u.___-_-_
Compilation of Reports-1965-1990 Improvement Program: Notch Ductility and Fracture U.S. Nuclear Regulatory Commission. Washington, Toughness Degradation of A 302-11 and A 533-11 D.C., h1 arch 1990.
Reference Plates from PSF Simulated Surveillance and Through-Wall Irradiation Capsules," USNRC Report llobson, D. O. and Dodd, C, V., " Interim Report on the NUREG/CR-3295, Vol.1, U.S. Nuclear Regulatory Creepdown of Zircaloy Fuel Cladding," ORNL Report Commission, Washington, D.C., April 1984.
ORNIJNUREG/Fhl-103, Oak Ridge National Labora.
tory, Oak Ridge, TN, hiay 1977.
llawthorne, J. R. and hicake, IL 11., " Light Water Reac-tor Pressure Vessel Surveillance Dosimetry Improve-Ilobson, D. O. et al.," Analyses of Su rface Displacements ment Program: Postirradiation Notch Ductility and Ten-of Zircaloy Fuel Cladding in the llOBillE Creepdown sile Strength Determinations for PSF Simulated Irradiation Experiments," USNRC Report NUREG/
Surveillance and Through-Wall Specimen Capsules,"
CR-1844, NUREG-74, U.S. Nuclear Regulatory Com-USN RC Report N U REG /CR-3295, Vol. 2. U.S. Nuc! car mission, Washington, D.C., h1 arch 1981.
Regulatory Commission, Washington, D.C., April 1984.
Ilunter, C. W. and Williams, J. A.," Fracture and Tensile Hawthorne, J. R.," Exploratory Studies of Element inte,-
llehavior of Neutron.lrradiated A533-il Pressure Vessel actions and Composition Dependencies in Radiation Steel," HEDL Report HEDI.-Th1E 71-76, Hanford En-Sensitivity Development," USNRC Report NURiiG/
gineering l'evelopment I ahoratory, Richland, WA, Feb-CR-4437, U.S. Nuclear Reguk tory Commission, Wash-ruary 1971.
ington, D.C., November DS5.
Loss, F. J. et al.," Analysis of Radiation Induced Embrit-Ilawthorne,J.R.and Hiser, A.L.," Experimental Assess-tiement Gradients on Fracture Characteristics of Thick-ments of Gundremmingen RPV Archive hiaterial for Walled Pressure Vessel Steels," NRL Report 7209, Na-Fluence Rate Effects Studies," USNRC Report val Research Laboratory, Washington, D.C., h1 arch 1971.
N'LIREG/CR-5201, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., October 1988.
loss, F. J. and Gray, J r., R. A., "J-Integral Characteriza-tion of Irradiated Stainless Steels," NRL Report 7565, Hawthorne, J. R.,"An Exploratory Study of Element in.
Naval Research Laboratory, Washington, D.C., Septem-teractions and Composition Dependencies in Radiation ber 1973.
Sensitivity Development-Final Report," USNRC Re-port NUREGICR-5357, U.S. Nuclear Regulatory Corn-hiaerker, R.11. and Williams, ht. L.," Calculations of Two mission, Washington, D.C., April 1989.
Series of Experiments Performed at the Poolaide Facility Using the Oak Ridge Research Reactor," USNRC Re-Hawthorne, J. R. and Hiser, A. L," Influence of Fluence port NUREG/CR-2696, U.S. Nuclear Regulatory Com-Rate on Radiation-Induced hiechanical Property mission, Washington, D.C., hiay 1982.
Changes in RPV Steels: Final Report on Exploratory Ex-periments," USNRC Report NUREG/CR-5493, U.S.
hiacrker, R. E. and Worley, IL A.," Activity and Fluence Nuclear Regulatory Commission, Washington, D.C.,
Calculations for the Startup and Two-Year Irradiation h1 arch 1990.
Experiments Performed at the Poolside Facility,"
USNRC Report NUREG/CR-3886, U.S. Nuclear Regu-Hiser, A. L., less, F. J., and hienke, it 11., "J-R Curve latory Commission, Washington, D.C., October 1984.
Characterization of Irradiated Low Upper Shelf Welds,"
USNRC Report NUREG/CR-3506, U.S. Nuclear Regu-hiacrker, R. E., " Gamma. Ray Characterization of the latory Commission, Washington, D.C., April 1984.
Two-Year Irradiation Experiment Performed at the Pool-side Facility," USMIC Report NUREG/CR-4039, U.S.
Hiser, A. L.," Correlation of Cy and Ku TransitionTem-Nuclear Regulatory Commission, Washington, D.C.,
perature Increases Due to Irradiation," USNRC Report January 1985.
NUREG/CR-4395, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., September 1985.
h1ager, T. R. and Thomas, F. O., " Evaluation by Linear Elastic Fracture Nicchanicsof Radiation Damage to Pres.
Hiser A. L," Post-Irradiation Fracture Toughness Char-sure Vessel Steels," Westinghouse Report WCAP-7328 acterization of Four Lab-hielt Plates." USNRC Report (Rev.), Westinghouse lilectric Corporation, PWR Sys-NUREGICR-5216 Rev. 1, U.S. Nuclear Regulatory tems Division, Pittsburgh, PA, October 1969.
Commission, Washington, D.C., June 1989.
N1ager, T. R., " Post-Irradiation Testing of 2T Compact Hiser, A. L, " Correlation of irradiation-induced Transi.
Tension Specimens," Westmghouse Report WCAP-tion Temperature increases from C, and Kn/Ke Data:
7561, Westmghouse Electric Corporation. PWR Systems Final Report / USNRC Report. N U R EG/CR -5494, Division, Pittsburgh, PA, August 1970.
N U REG - 1426 40
Compilation of Reports-1965n940 McGowan, J. J., " Tensile Properties of Iriadiated Nu-Perrin, ' S. et al.," Simulated Void.llox. Capsule Charpy clear Grade Pressure Vessel Plate and Welds for the Impact Test Results," USNRC Report NURl!GI Fourth I(SSI' 1rradiation Series," USNRC Report CR-3320 Vol. 5,!!PRI Report NP-4630,lilectric Power NURl!G/CR-3978, U.S. Nuclear Regulatory Commis-Research Institute, Palo Alto, CA, August 1986.
sion, Washington, D.C., January 1985.
Pota[mys, U. and Ilawthorne, J. R.,"The liffect of Resid-
"^I UC""'nts on 550*F Irradiation Response of Selected McGowan, J. J., "Tensac Properties of Irradiated Nu-I ressure Vessel Steels and Weldments,, NRI. Report clear Grade Pressure Vessel Welds for the 'I hird flSS I 6803, Naval Research Iahoratory, washington, IM.,
Irradiation Series." USNRC Report NUlt!!G/CR-40S6, November 1968.
U.S. Nuclear Regulatory Commission, Washington, D.C., March 1985.
Remec, I., Stallmann, F. W., and Kam, F.11. K.. " Neutron Spectral Characterization for the l'ifth licavy Section McGowan, J. J., Nanstad. R. K., and Thoms, K. R.,
Steel Technology (llSST) lrradiation Series, 'Neutronics
" Characterization of irradiated Current Practice Welds lixposure Paramet ers',"
USNRC Report NURFG/
and A533 Grade D Class 1 Plate for Nuclear Pressure CR-4031, Vol. 3, U.S. Nuclear Regulatory Commission, Vessel Service " USNRC Report NURiiG/CR-4880 Washington, D.C., March 1985.
Vols. I and 2, U.S. Nuclear Regulatory Commission, Washington, D.C., July 1988.
Segaser, C. l. " Feasibility Study, Irradiation of 11eavy Section Steel Specimens in the South Test Facility of the Oak Ridge Research Reactor," USAliC Report ORNI.-
Miller, I I'., llaldwin, C.
A., and Johnson, J.
O.,
.I'M-3234, Oak Ridge National 1.aboratory, Oak Ridge, "Neutronies Calculations for the Ilulk Shielding Reactor
.l'N, May 1971.
licavy Section Steel Technology Irradiation lixperi-ment," ORNI Report ORNIRM-8045, Oak Ridge Na-Stallmann, F. W. and Kam, l'.11. K., " Neutron Spectral tional lhoratory, Oak Ridge, l'N, February 1980.
Characterization of the Second Nuclear Regulatory Commission llcavy Section Steel Technology 4T-CT Miller, l F.,"A Computerized Process Control System Irradiation lixperiment," USNRC Report NURIIG/
for the ORR-PSF 1rradiation lixperiment, Part 2:
CR-0505, U.S. Nuclear Regulatory Commission, Wash.
Mathematical liasis and Computer implementation of ington, D.C., December 1978.
the Temperature Control Algorithm," USNRC Report NUREG/CR-1710, Vol. 2, U.S. Nuclear Regulatory Stallmann, F. W., llaldwin, C. A., and Kam, F.11. K.,
Commission, Washington, D.C., November 1980.
" Neutron Spectral Characterization of the Fourth Nu-clear Regulatory Commission lleavy Section SteelTech-Miller, l F., " Analysis of Temperature Data from the nology IT-CT Irradiation lixperiments: Dosimetry and Uncertainty Analysis,, USNRL Ifeport NURiiG/
ORR-PSF Irradiation lixperiment: Methodology and Computer Software," USNRC Report NURiiG/
CR-3333, U.S. Nuclear Regulatory C omnusca,on, Wash-CR-2273, U.S. Nuclear Regulatory Commission, Wash-ngton, D.C., July 1983.
ington, D.C., November 1981.
Stallmann, F. W,,"Statisticallivaluation of Metallurgical Test Data in the ORR-PSF-PVS Irradiation lirperi-Miller, L F. and llobbs, R. W., " Data Acquisition and ment," USNRC Report NURliG/CR-3815, U.S. Nu-Control of the 1ISST Series V Irradiation IIxperiment at clear Regulatory Commission, Washington, D.C., August the ORR," USNRC Report NURl!G/CR-3872, U.S.
1984.
Nuclear Regulatory Commission, Washington, D.C.,
March 1985.
Stallmann, F. W., " Determination of Damage lixposure Parameter Values in the PSF Metallurgical Irradiation Miller L F. et al.," Neutron lixposure Parameters for the lixperiment," USNRC Report NURl!G/CR-3814, U.S.
MetallurgicalTest Specimens in the Fif th Ileavy-Section Nuclear Regulatory Commission, Washington, D.C., Oc-toher 1984.
Steel Technology irradiation Series Capsules," USNRC Report NURiiG/CR-5019, U.S. Nuclear Regulatory Stallmann, F. W., Kan, F.11. K., and llaldwin, C. A.,
Commission, Washington, D.C., March 1988.
" Neutron lixposure Parameters for the Fifth licavy Sec-tion Steel Technology irradiation Series," USNRC Re-Miller, L F. cl al.," Neutron lixposure Parameters for the port NURiiG/CR-4284, U.S. Nuclear Regulatory Com-Metallurgical Test Specimens m the Sixth Ileavy-Section mission, Washington, D.C., July 1985.
Steel Irradiation Series," USNRC Report NURl!G/
CR-5409, U.S. Nuclear Regulatory Commission, Wash.
Stallmann, F. W.," Analysis of the A 302-11 and A 533-H 1
ington, D.C., May 1990.
Standard Reference Materials in Surveillance Capsules 41 NU Rl!G-14 26
Compilation of Reports-1965--1990 of Commercial Power Reactors," USNRC Report Retidual Stresses NUREG/CR-4947, U.S. Nuclear Regulatory Commis-sion. Washington, D.C., January 1988 Rybicki, E. F. et al.,
- Residual Stresses at Girth llutt Welds in Pipes and Pressure Vessels, Final Report, Stallmann F W., Kam, F.11. K., and Taylor,11. J.,"PR-April 1, 1976 to June 30, 1977," Ilattelle Report
!!Dil: Power Reactor Embrittlement Data llase, Version NUREG-0376, Dattelle Columbus laboratories, Co-
- 1. Program Description," USNRC lleport NUREGI lumbus,011, November 1977.
CR-4816, U.S. Nuclear Regulatory Commission, Wash-ington, D.C., June 1990.
Rybicki, E. F, " Residual Stresses Due to Weld Repairs, Cladding and litectron 18 Velds and liffect of Resid-Steele, L.11., llawthorne, J. R., and Gray, Jr., R. A.,
ual Stresses on Fract.
mavior, Annual Report Sep-
" Neutron irradiation Embrittlement of Several liigher tember 1,1977 to Noven ber 30,1978," USNRC Report Strength Steels," NRI. Report 6419, Naval Research NUREG/CR-0559 U.S. Nuclear Regulatory Commis-laboratory, Washington, D.C., September 1966, sion, Washington, D.C., December 1978.
11 bicki, E. F., Shadley, J. R., and Sandhu, A. S.,"Experi-3 Steichen, J. hi. and Wilhams, J. A., "Iligh Suain Rate mental livaluation of Residual Stresses in a Weld Clad Tensile Properties of Irradiated ASThi A533 Grade 11 Class 1 Pressure Vessel Steel," IIEDL Report ilEDL-Plate and Clad Test Specimens," USNRC Report Th1E 73-74,Ilanford lingineering Development Labora, NUREG/CR-4646, U.S. Nuclear Reputatory Commis-tory, Richland, WA, July 1973.
sion, Washington, D.C., October 1986.
R>bicki,11. F. and Stonesifer, R.11., " Computational i
Stelzman, W J. and llerggren, R.
G.,
.. Radiation hiodel for Residual Stresses in a Clad Plate and Clad Strengthening and limbrittlement in lleavy Section Steel Fracture Specimera," USNRC Report NUREGI Plates and Welds, ORNL Report ORNic487L Oak CR-4635, U.S. Nuclear Regulatory Commission, Wash.
Ridge National laboratory, Oak Ridge,1 N, June 1973.
ington, D.C., October 1986.
Williams, J. A., "The Irradiation and Temperature De-Smith, G. C. and llolz, P. P., " Repair Weld Induced Re-pendence of Tensile and Fracture Properties of ASThi sidual Stresses in nick Walled Steel Pressure Vessels,"
A533, Grade B, Class 1 Steel Plate and Weldment,"
USNRC Report NUREG/CR-0093 U.S. Nuclear Regu-IIEDL Repon liliDieTh1E 73-75, llanford lingineer*
latory Commission, Wa:hington, D.C., June 1978.
ing Development laboratory, Richland, WA, August l
1973.
Steam Ger.erators Williams, J. A.,"Some Comments Related to the Effect Allen, R. P., Clark, R. L, and Reece, W. D.," Steam Gen-of Rate on the Fracture Toughness of Irradiated ASThi A533-H Steel Based on Yield Strength llehavior "
er tor Group Project Task 6-Channel !! cad Decon-i llEDL Report HEDI-SA 797, Hanford Engineering tamination," USNRC Report NUREG/CR-3841, U.S.
Development laboratory, Richland, WA, December Nuclear Regulatory Commisaan, Washington, D.C.,
1974.
August 1984, 1
Alzheimer, J. hl. et al., " Steam Generator Tube Integrity Williams, J. A., "The Irradiated Fracture Tc ughness of l
I *E**' 0"""
Y N#P "' "" U f
ASTH 1 A533, Grade B, Class 1 Steel hicasured with a USNRC Report NUREG-0359, U.S. Nuclear Regula.
Four-inch Thick Compact Tension Specimen," llEDL tory Commission, W ashmgton, D.C.,1977.
Report HEDicTh1E 75-10, Hanford Engineering De.
velopment laboratory, Richland, WA, January 1975.
Alzheimer, J. hl. et al.," Steam Generator Tube Integrity Program Phase I Report," USNRC Report NUREG/
Williams, J. A., " Tensile Properties of Irradiated and Unirradiated Welds of A533 Steel Plate and A508 Forg-CR-0718, U.S. Nuclear Reg'79.-ulatory Commission, W ington, D.C., September 19 ings," USNRC Report NUREG/CR-1158, U.S. Nucicar Regulatory Commission, Washington, D.C., July 1979.
Hickford, R.1. et al., " Eddy Current Round Robin Test on laboratory Produced Intergranular Stress Corrosion Williams, bl. L, Remee, I., and Kam, F.13. K. " Neutron Cracked Inconel Steam Generator Tubes," USNRC Re-Spectral Characteri/ation for the Fifth Heasy Section port NUREG/CR-3561 U.S. Nuclear Regulatory Com-Steel Technology (lISST) Irradiation Series, 'Neutronics mission, Washington, D.C., January 1984.
Calculations'," USNRC Report NUREG/CR-4031, Vol.
- 2. U.S. Nuclear Regulatory Commission, Washington, ihrks, A. S. et al.," Preliminary Report on Steam Genera-D.C., h1 arch 1985.
tor Group Project-Task 9 NDE Round Robin," PNI.
NUREG-1426 42
Compilation of iteports-1965-1990 Report PN1-5499, Pacific Nonhwest I aboratory, Clark, R. A. and lxwis, ht., " Steam Generator Group Richland, W A,1984.
Project Semi Annual Progress Iteport, January through June 1985," PNI. Report PNI-5603, Pacif Northwest flow en, W. hl., Ileaaler, P. G., and Whl
,..,l..*livalu-Iaboratory, Richland, WA.1985.
ation of Sampling Plans for in.fenice Inspection of Steam Generator Tubes: Pen 1,*
USNRC Repon Clarh it. A. and Runz, R. J., " Compendium and Com-NURl!G/CR-5161, U.S. Nuclear Regulatory Commis, parison of International Practice for Plugging, Repair and sion, Washington, D.C.,1988.
Inspection of Steam Generator'l ubing." USNRC Report NUllLG/CR-5016 U.S. Nuclear Regulatory Commis-llowen, W. M., Ileasler, P. G., and White, R.11.,"livalu.
si..n, Washington, D.C., April 1988.
ation of-Sampling Plans for in Service inspection of Steam GeneratorTubes: Maleling of !!ddy Current Re-Doctor, P. G-et al.,"The In Senice 1listory of the Surry Unit 2A Steam Generator, PNI, Renort PNI A880, Pa-liability Data, Analytical !! valuations and initial Monte Carlo Simulations," USNRC lteport NUHl!G/CR-5161 cific Northwest 1 aboratory, Richland, % A,1983.
Vol.1. U.S. Nuclear Regulatory Commission, Washing.
Doctor, P. G. et al., " Steam Generator Group Project ton, D.C., Aprn,1989' Progress Report on Data Acquisition / Statistical Analy-sis." USNRC Report NURl!G/CR-3579, U.S. Nuclear liradley, IL R. et al., " Steam Generator Group Proj.ect -
Regulatory Commission, Washington, D.C., January Task 13 Final Report: NDl! Validation," USNRC Report
- 39g4, NURl!G/CR-5185. U.S. Nuclear Regulatory Commis.
sion, Washington, D.C., August 1988.
Doctor, P. G. et al., " Steam Generator Group Project-Task 7: Final Report-Post.Senice liaseline liddy-Clark, R. A. and lewis, M., " Steam Generator Group Current lixamination," USNRC Report NURl!G/
Project Semi Annual Progress Report, January-June CR-5087 U.S.
Nuclear Regulatory Commission, 1983," PNI. Report PNIA859. Pacific Northwest I rbo-Washington, D.C., December 1988.
ratory, Richland WA,1983.
Doctor, P. G. et al., " Steam Generator Group Project-1 Clar k, R. A. and llickford, R. L.,
- Steam Generator Tube Task 9: Final Report-Nondestructive livaluation Round Integrity Proi, ram 1xak Rate Tests, Progress Report",
Robin Vol.1: Description and Summary Data " USNRC USNRC Report NUREG/ Cit-3562, U.S. Nuclear Regu-Report NUREG/CR-4849. Vol.1, U.S. Nuclear Regula.
latory Commission Washington, D.C., January 1984, tory Commission, Washington, D.C., January 1989.
Clark, R. A. and lewis, hi., " Steam Generator Group Doctor, P. G et al.,"Steain Generator Group Project-Project Semi. Annual Progress Report, July-December Task 9: Final Report-Nonden ructive Evaluation Round 1982." USNRC iteport NURl!G/CR-3580, U.S. Nuclear Robin, Vol. 2: Raw Inspection Data " USNRC Report Regulatory Commission, Washington, D.C., January NURiiG/CR-4849, Vol. 2 U.S. Nuclear Regulatory 1984.
Commission, Washington, D.C., h1 arch 1989.
- Clark, R. A. and I.cwis, hi., " Steam Generator Group Dodd, C. V, et al.,
- Eddy-Current inspection ft L 1m.
Project Annual Report-1982," USNRC Report Genuator Tubmg Program Quarter 1y Progress Report NUREG/CR-3581. U.S. Nuclear Regulatory Commis.
for Period Endmg June 30, 1978,,, USNRC Report sion. Washington, D.C., February 1984.
NUREG/CR-0479. U.S. Nuclear Regulatory Commis-sion, Washington, D.C., November 1978.
Clark, R. A.,lxwis, M., and Muscara, J.," Steam Genera-Dodd, C, V et al., *liddy. Current inspection for Steam-tor Group Project Semi-Annual Progress Report January Generator Tubing Program Vuarterly Program Report,,
Through June 1984" PNL Report PNir$267, Pacific USNRC Report NURliG/CR--0520, U.S. Nuclear Regu.
Northwest laboratory, Richland, WA,1984.
latory Commission, Washington, D.C., September 1978.
. Clark, R. A. and lxwis, bl., " Steam Generator Group Dodd, C. V. et al., " Eddy Current inspection for Steam Project Annual Report, 1983," USNRC Report Gercator Tubing Program Annual Progress Report for NURl!G/CR-4361,- U.S. Nuclear Regulatory Commis-Period Ending December 31, 1979," USNRC Report sion, Washington, D.C., September 1985-NUREG/CR-0764, U.S. Nuclear Regulatory Commis-sion, Washington, D.C., May 1979.
Clark, R. A. and lewis, M., " Steam Generator Group Project Annual Report, 1984," USNRC Report Dodd, C. V., Deeds, W. E., and McClung, R. W.. " Eddy.
NUREG/CR-4362, U.S. Nuclear Regulatory Commis.
Current inspection for Steam Generator Tubing Pro-sion. Washington, D.C., September 1985.
gram Quarterly Progress Report for Period linding 43 NURl!G-1426
r Compilation of fleports-1965-1990
'1
)
j March 31,1979," USNitC itepart NUltl:G/ Cit-0918, i AdJ, C. V., Deeds, W. !!.. and McClung,11. W., "liddy.
i U.S. Nuclear llegulatory Commission, Washington, Current inspection for Steam Generator Tubing Pro-i D.C., August 1979.
gram Quarterly Progress Iteport for Penod linding Sep-tember 30, 1981," USNitC llelwt NUlt!!O/ Cit-2305, Dodd, C. V., Deeds, W, fi., and McClung, it. W.. "liddy.
Vol. 3, U.S. Nuclear itegulatory Cornmission. Washing.
Current inspection for Steam Generator Tubing ton, D.C., July 1982.
Program Quarterly Progress Iteport for Perkd I!nding June 30,1979," USNitC lleport NUld!G/ Cit-1069 DodJ, C. V., Deeds, W.11., and hicClung,11. W., *liddy.
1 U.S. Nuclear iteputatory Commission, Washington, Current inspection for Steam Generator Tubing Pro-
)
D.C., Getober 1979.
gram Annual Progess lleport for Period I!ndmg Decem-ber 31,1981," USNitC lleport NUlti!G/ Cit-2305, Vol.
Dodd, C, V., Deeds, W, !!, and hicClung,11. W., *liddy, 4, It.S. Nuclear llegulatory Commissian, Washington, Current inspection for Steam Generator Tubing Pro.
D.t August 1982.
gram Quarterly Progress lleport for Perk d lindmg Se@
Ihdd, C. V., Deeds, W.11., and McClung,11. W.,"l!ddy-tember 30,1979 USNitC lleport NUlt!!G/ Cit-137.,
egulatory Commission. Washington, Current inspection for Steam Generator Tubing Pro-N ar
- g gram Quarmly Progress iteport for Perkd linding March 21,1982," USNitC lleport NUlti!G/CR-2824, Current Inspection for Steam Generator {. W. *1!ddy-g'[
" #[
fgf tg WmmMon, WaWng-Dodd, C. V., Deeds, W, ii., and McClung, l Pubm, g Pro-gram Annual Progress Report for Perkd linding Decem.
D(dd, C V., Des W.1:., and McClung, Ri W., *liddy-ber 31,1979," USNitC Report NURiiG/ Cit-1563, U.S.
Current inspection for Steam Generator Tubing Pro-Nuclear Regulatory Cominission, Washington, D.C., July gram Quarterly Progress Report for Perkd finding 1980.
Jur e 30,1982." USNRC Report NUltLIG/CR-2824, Vol. 2. U.S. Nuclear llegulatory Commission, Washing.
Dodd, C. V, and Deeds, W. I!.,"liddy Current inspection ton, D.C., January 1983.
for Steam Gene rator Tubing Program Quarterly Progress Iteport fo "crkd linding March 31,1980," USNitC Re-Dodd, C. V., Deeds, W, II., and McClung, R. W.. "l!ddy.
port NUlc.G/CR-1828, U.S. Nuclear Regulatory Com-Current inspection for Steam Generator Tubing Pro-mission, Washington, D.C., December 1980.
gram Quarterly Progress lleport for Period linding Sep-tember 30, 1982." USNRC Report NUlti!G/CR-2824 Dcdd, C. V. and Deeds, W, !!., "liddy-Cu rren t ins pection Vol. 3. U.S. Nuclear Regulatory Commission, Washing-for Steam Gewrator Tubing Program Quarterly Progress ton, D.C., February 1983.
Report for Perial linding June 30,1980," USNRC Re-port NUREG/CR-1829 U.S. Nuclear Regulatory Com.
DoJJ. C. V., Deeds, W. !!, and McClung, R. W., "llddy-rnission Washington, D.C., January 1981.
Current inspection for Steam Generator Tubing Pro-i gram Annual Progress Report for Period linding Decem-Dodd, C. V., Deeds, W. IL, and McClung, R. W., "liddy-ber 31,1982," USNRC Report NURI!G/CR-3161, U.S.
Current inspection for Steam Generator Tubing Pro.
N uclear Regulatory Commissmn, Washington D.C., J uly
)
gram Quarterly Progress Report for Period finding Sep-1983-tember 30,1980," USNRC Report NURIIG/CR-1982, lhdd, C. V., Deeds, W,11., and Smith, J.11., "lidd Current inspection for Steam Generator 'lubing Pr'y-
" 8"' '
E "'
1., April Sl gram Quarterly Progress Report for Pen,'od lindin March 31,1983," USNRC Report NURliG/CR-3200, Dodd, C. V., Deeds, W. h,., and McClung, lj. W., "liddy-Current inspection for Steam Generator rubmg Pro
- Vol.1. U.S, Nuclear Regulatory Commission Washing.
grarn Annual Progressm Report for Penod !!nding De-ton, D.C., August 1983.
cember 31, 1980," USNRC Report NURl!G/CR-2149, Dodd, C. V e, al., "liddy-Current Inspection for Steam U.S. Nuclear Regulatory Commission, Washington, Generator Tubing Program Quarterly Progress Iteport D.C., August 1981.
for Period linding June 30, 1983," USNRC Report Dodd, C. V,, Deeds, W, P.., and McClung, R. W., *liddy Current inspection for Steam Generator Tubing Pro-Dodd, C. V. et al., "I!ddy-Current inspection for Steam gram Quarterly Progress Report for Perkd !!nding Generator Tubing Program Quarterly Progress Report J une 30, 1981," USNRC Report NURl!G/CR-2305, for Period finding September 30,1983 " USNRC Report Vol. 2, U.S. Nuclear Regulatory Commission Washing-NURI!G/rR-3200, Vol. 3. U.S. Nuclear Regulatory ton, D.C., February 1982.
Commission, Washington, D.C., March 1984.
NURl!G-1426 44
Cornpilation of Rep >rts-1%5-1990 i,
j Dodd, C. V. et al., *liddy. Current inspection for Steam Kurti, H. J. et al.," Steam Generator Tube integrity Pro-Generator Tubing Program Annual Progress Report for gram: Phase !!, I inal R eport " USNitC Report N U Rl!G/
j Period finding December 31, 1983," USNRC Report CR-2336. U.S. Nuclear Regulatory Commission, Wash-NURIIG/CR-3200, Vol. 4. U.S. Nuc! car iteculatory irvin D.C., August 1988.
{
Commission, Washington, D.C., hiay 1984.
Ku u, R. J. et al.. " Steam Generator Tube Integrity Pro-Dodd, C. V, et al., "liddy Current inspection for Steam gram / Steam Generator Group Project-Final Summary Generator Tubing Program Semi Annual Progress Re-Report," USNRC Report NUR1!G/CR-5117, U.S. Nu.
lort for PerhKl finding June 30,1984," USNRC Report clear Regulatory Cornmission, Washington, D.C., May i
NURiiG/CR-3949 Vol.1. U.S. Nuclear Regulatory 1990.
Commission, Washington, D.C., December 1984.
MC E d al, *liddy. Current inspection for Dodd, C. V. et al., "l!ddy. Current inspection for Steam Stearn. Generator Tubing Program Quarterly Progress Report for Period finding March 31,1978," USNRC Re-Generator'lubing Prograrn Annual 1,'rogtess Report for port NURIIG/CR-0164, U.S. Nuclear Regulatory Com-r Period I!nding Decernber 31, 1984.' USNRC Report NURl!G/CR-3949, Vol. 2. U.S. Nuclear Regulatory mission. Washington, D.C., July 1978.
Commission, Washington, D.C., June 1985-Morris, C. J. et al., *lldJy. Current inspection of i
inconel-600 Steam Generator Tubes at the Tube Shet,"
Dodd, C. V., Deeds, W. E., and McClung, R. W., "Im-USNRC Report NURl!G/CR-1626, U.S. Nuclear llegu.
proved !!ddy. Current Inspection for Steam Generator latory Commission, Washington, D.C., November 1980.
Tubing, Progress Report for Period January 1985 to De.
cember 1987 " USNRC Report NURl!G/CR-5478, U.S.
Reece, W. D., lloenes, G. R., and Parkhurst, M. A.,
Nuclear Regulatory Commission, Washington, D.C.,
- Steam Generator Group Project Progress Report-January 1990.
Task 3 Ilealth Physics " USNRC Report NURiiG/
CR-3578, U.S. Nuclear llegulatory Commission Wash.
Enderlin, W.1. and !!augh, J. W., " Vibration ar'd Wear in ington, D.C., January 1984.
Steam Generator Tubes Following Chemical Cleaning.
Serniannual Report" USNRC Report NURI'.0/
Schwenk, IL ll. and Wheeler, K. R., " Steam Generator Group roject,fask Rb-Seconda,y Side fixamination, USNRC{ Report NURl!G/L R-3843, U.S. Nucle CH-4276, U.S. Nuclear llegulatory Commission Wash.
ington, D.C.' June 198'5' latory Comrnission, Washington, D.C., July 1984.
Enderlin, W. l. and llaugh, J. W., " Vibration and Wear in Stearn Generator Tubes Following Cheraical Cleaning, Schwenk, !!. II., " Steam Generator Group Project Task 10-Secondary Side lixamination Final Report,"
Final Report," USNRC Report NUREG/CR-4276 Vol.
- 2. U.S. Nuclear Regulatory Commission, Washington, USNRC Report NUREG/CR-4850, U.S. Nuclear Regu-D.C., March 1986.
latory Commission, Washington, D.C., July 1987.
Sinclair, R. II., " Secondary Side Photographic Tech.
Foster,11. E. et al., " Feasibility Studies for Nondestruc-niques Used in Characterization of Surry Steam Genera.
l tive Testing of Duplex Tube-to-Tubesheet Joints and tor," USNRC Report NUREG/CR-3094, U.S. Nuclear Tubes for an LMFilR Steam Generator," ORNL Report Regulatory Commission, Washington, D.C., October i
ORNir$094, Oak Ridge National Lalmratory, Oak 198J.
Ridge, TN, December 1974.
Tanner, J. E., Reece, W. D., and Scherpelz, R. l. " Steam Kurtz, R. J. and Lewis, M.," Steam Generator G roup Pro-Generator Group Project Progress Report-Task 3,"
ject Semi. Annual Pmgress Report, January through June PNL Report PNL-5269, Pacific Northwest 1aboratory, 1986," PNL Report PNIA012. Pacific Northwest Iabo.
Richland, WA.1984.
ratory, Richland, WA,1986.
Vagins, M. et al., " Steam Generator Tube Integrity Pro-Kurtz, ILJ., I swis, M., and Clark, R. A., " Steam Genera
- gram. Annual Progress Report, January 1-December 31, tor Group Project: Annual Report,1985 " USNRC He.
1977," USNRC Report NURl!G/CR-0277, U.S. N uclear port NUREGICR-4848, U.S. Nuclear Regulatory Com, Regu'atory Commission, Washington, D.C.,
August
- g973, mission, Washington, D.C., April 1987.
Wheeler, K. R., " Initial Inspection of the Service De.
Kurtz, R. J. and Irwis, M., " Steam Generator Group Pro-graded Surry 2 A Steam Generator, June 1982." PNL Re-ject Annual Report-1986," PNL Report PNie6150, Pa-port PNI-5268, Pacific Northwest Iaturatory, Richland, cific Northwest laimratory, Richland, WA,1987.
WA,1984.
45 NUREG-1426
. - - - ~.
l Compilation of Heroris-- 1965-1990 Wheeler, K.11. et al.," Steam Generator Group l'roject.
Chopra. O. K. and Chung, i1 hl., *! ong-Terrn !!mbrittle-Task S.
Selective Tube Unpluggmp," USNltC Report ment of Cast Duplex Stainless Steels m I.WR Splems:
NURI GiCit-3842, U.S. Nuclear iteputatory Comtms-Semiannual itepor t ()ctober 14S6-h1 arch 1987,"
- 5. ion Washinrton, D.C., July 1954.
USNRC lleport NURI.0/UR-4744 Vol. 2. No.1. U.S.
Nuclear Regulatory Commission Washington,ILC., July 1937-Thermal Embrittlement (Cast Slainless Steel)
Chopra, O. K. and Chu ng,11. h1.,"I eng-Term limbtittie.
Chops a, O. K. and Chung, i1. hl., *1 eng-Term 1 mbiittle-ment of Cast Duples Stainless Steels in I,WR Systems:
inent of Cast 1)uplex Stainless Steels m 1. Wit Systems:
Annual Report October 1982-Septernber 1983,"
Sennannual Herort Apnt-September 1987," USNRC USNRC Report NURl!G/CR-3857, U.S. Nuticar Repu-Report NURI'G/ Cit-4744, Vol. ?, No. 2. U.S. Nuclear latory Commission Washington, D.C., August 1984.
Rerulatory Commnsion, Washington, D.C., July 1989 Chopra, O. K., and Chung, i1. hl., "l ong-I crm limbut.
Chopra, O. K. and Chu ng, i1. hl., *1 ong l'e r m limbnttle-tiement of Cast Duplex Stainless Steels m 1 Wit Systerns:
n ent of Ca't Duplex Stainless Steels in 1 WR Systems:
Annual Report October 1983-September 1954 "
Semiannual Report October 1987-htarch 1988,"
USNRC llepott NURliG/CR-4204, U.S. Nuclear iteru.
USNitC Report NUHl!GiCR-4744 Vol. 3, No.1, U.S.
latory Commission, Wai.hington, D.C., h1 arch 1985.
Noelcar Regulatory Comnmsion, Wa<,hington, I AC., De-cernber 1989 Chopra, O. K. and Chung,11. h1.,"I eng Term Iimbottle-ment of Cast Duplex Stainless Steels m 1.WR Systems:
Chopra,0. K and Chung,ll h1.,"l ong-Term limbrittle.
Annual Report October 1984-September 1985,-
ment of Cast Duplex Stainless Steels in 1.WR Systems:
USNRC iteport NUltliG/CH-4503, U.S. Nucicar Regu.
Semiannual lleport Aptd-Septernber 198S" USNRC latory Cornmission, Washington, D.C., January 1986.
Report NURI:G/CR-4744. Vol. 3. No. 2. U.S. Nuclear Reputatory Comnnssion, Washington, D.C.,
August Chopra, O. K. areJ Chung, i 1. ht., "I eng-Term lirnbri:tle-1990.
ment of Cast Duplex Stainless Stect:. in 1.WR Sptems:
Semiannual Report October 1955-hiarch 1986."
Chopra, O. K. and Sather, A., " Initial Assessment of the USNRC Report NURl!G/CR-4744 Vol.1, No.1. U.S.
hicehanisms and Significance of I nw Temperature Nuclear Regulatory Cornmiwion Washington, ILC.,
1;mbnttlement of Cast Stainless Steelsin i.WR Systems,"
September 1986.
USNitC Report NURiiG/CR-53N5, U.S. Nuclear Repu-latory Commiwon, Washington, D.C., August 1990.
Chopra.O. K.and Chung ll. hl.. "1 eng Term !!mbrittle-ment of Cast Duplex Stainless Steels in 1.WR Systems:
lliser, A. l..," Tensile and J-R Curve Characterization of Serniannual Report April-September 1956," USNRC
'lhei mally-Aged Austenitie Cast Stainless Steels "
Report NUlti!G/CR--4744 Vol.1, No. 2. U.S. Nuclear USNRC Report NURl!G/CR-5024. U.S. Nuclear Repu.
Regulatory Commission, Washmgton, D.C., h1 arch 1987.
latory Commission, Washington, ILC., September 1988, N URIE 1426 46
f #4C 8 Of1M 3%
US IJUC4 i AH ht GUL Af oft t' CoMMfibiOy
- 1. hl PUH1 tJLA4til H suo,, ne,,,44C, And,,n,W,n,Nu,n.
1 A66egend tsy f V
1749)
NHcM$ w,
,,a me W SW BIBLIOGRAPHIC DATA SHEET
- * *. d *"r 3 a
u,.uocoon.mth..e.
3 NUlt110-1426 VOI 1 i m a xNo e,vu ni a 3 oA t nwvH f eum u,Hi u Compilation of itep>rts from itescarch Suppirted by the Materials 7
voy3n vuy lingineering lisanth, Dinsion of linginecimg 1
May 1991 1965-1990 a fin on onANT MuMin a
- t. Aun oais, e n os O; nt e ;H i Compiled by A. l Iliser, Jr.
Technical
- r. et niva COvi nt a viou.,,e o.ie.,
Q 61.Hi OHMir JU..Ol tG AI Jt/.A I K.Jf 4. a cono ow, poco. n. ne no rn.mno.e...O, pov4te Dmstun, OPece tr hogm, V 6. twear heyulalWy Commistum. 4t,rj
+ NAML AND ADOHL bb (it F4H rn mng.on.
a Division of lingineering Office of Nuclear llegulatory itesearch U.S. Nuclear llegulatory Commission Washington, DC 20555 O. t>PONbOhtt Ks OHG APJi/ Altutd = NAMt. ArJU ADDht $$ (It f 4HC, tyge * $ame et atme'; H twh etteW Vtmde NHC Dmsum. 0t110e or fieJ6pn.
IJ 8. Nuclear Regulattey Ctenmitslun, and rnalling ockpest )
Same as nbove
- 10. tiU69*LLML N I AH f NO1i N
- 11. At1816 TACT (700 wordt or less)
Since 1965, the Materials !!ngineering Ilrunch, Division of lingineering, of the Nuclear llegulatory Com.
Inission's Office of Nuclear llegulatory itescarch, and its predecessors dating back to the Atomic linergy Commis-sion (AI!C), has sponsored research programs concerning the integrity of the primary system pressure boundary of light water reactors. *lhe compments of concern in these research programs have included the reactor pressure vessel (ItPV), steam generators, and the piping. 'ihese research programs have covered a broad range of topics, including fracture mechanics analysis and experimental work for 14pV and piping applications, inspection method development and qualification, and evaluation of irradiation effects to itPV stects.
'this report provides as complete a listing as practical of formal technical reports submitted to the NitC by the investigators working on these research programs. 'this listing includes topical, final and progress reports, and is segmented by topic area. In many cases a report will cover several topics (such as in the case of progress reports of multi faceted programs), but is listed under only one topic. Therefore, in searching for reports on a specific topic, other related topic areas should be checked also.
- 12. KEY WORDS/DESCRIPTORS (List words tw phrasse that wm assist researchees in krating tte repyt l 13 AV AILAblUI 4 AILMI NI Unlimited 14 SECURITY CL ASS 4 tCAllON reactor pressure vessels, piping, fracture mechanics, non destructive examination, g,,,,,,,,,3 radiation embrittlement, dosimetry, environmentally assisted cracking, fatigue, steam generators, annealing, research reports Unclass.fied i
(This ireporo Unclassified Ib. NUMut R OF PAbt 8 16 64 46C(.
NRO Fc#tM 335 (?-89)
pummmia THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER
UN11ED STATES
' '" ' u ' 5 $ " ^ 4 7
PLit T AGI b fill i Alta I
NUCLEAR REGULATORY COMMISSION h
- 2 0 5 % 1 ;3 9 $.t 1 i a s n, *,,..,,,,",",,,,',,,,
WASHINGTON, D C. 20%5 U !.,
yy-r, fpen 1 v g o i s.p, e
a Of flCI AL liUSINE SS p,g[P[4'e,.g,f[7l'ilfC47
,f g,
Pitq AL1Y f OR PRIVA1( Ubi (10
<~3
- yeg i-WNSHINGT19
'~
r dC
,7 a g,,.
?
Cy e-C',
w n,-
ou te =
x..
O:
- ~ ;
Oba GE
-c CE
/c OF Mxs O
7I E:
z.
?
r i
=
E-w V
. _