ML19291C073
| ML19291C073 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/10/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19291C072 | List: |
| References | |
| NUDOCS 8001170039 | |
| Download: ML19291C073 (21) | |
Text
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C., !LEhAilCf. 0: CEG KED Gi' f*E LTE: :' : E S It. SAFET) REVIEr.
A.
(EJECTIVE:
Public safety ray be enhcnced and individual and societal ris6 redt'ced by developing and irple~enting a phated program to include, in safety reviews, consideration of core degradation and rtelting beyond the desi~. t.ss'c The program phases are (1) short-at d ecium-term acticos for scc:ing and ir.r lementation; (2) research prog ar.s to decelcp additional neeced inf c r Et ict., ano (3) a rulemaking proceeding to establish long-term pclicy, goais, and requirements related to accidents involving core damage greater tha-i t.e ; re t t.t des i gr basis.
Tne foii;, sing will t.e consice:ec.
Cate ccolability Degraced core characteristics Primary syster chemistry Systers functionability and reliability Shielding and accessibility Behavior under irradiation and other environmental stresses Radioactivity transport and leakage Leakage from auxiliary systems Leak-tight high pressure decay heat removal loop Hydrogen in containment structure k
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a c. - L I;, L::*.e! tc r iticctir.; sev(re accic..s Core catcnor Filtered, iented containment strc:tarc Co nt a i r,rr e nt structure ultirate strength State-of-the-art containment approaches for f ut ure r>l a-t 5 Post-accicent recc.crj E.
NRC ACTIONS Leactor coolant system vents.
a Descriptico:
N;.R issue a letter requiring the installatior of nig'. poi nt reactor coclant s;etem and reactor vessel heaa vests t c :te 3 1
c: <:ic ftor the cc.ntrci rocr Tr.ese sents, along witn cine- :ssicn featur+-
will pro.ide the flexibility r,eedec to deal with the unenpectec presen ( c-nonccndensible gases in the reactor vessel and primary cooling system.
IE inspect implementation.
b.
Schedule:
(1)
Letter issued to operating reactors September 13, 1979 (2)
Issue letter to all applicants by March 1. 19E:
(3)
Lead plant review to be completed Decetter 13, 1979 (4) Operating licensees must install before power operation (5)
Plants with construction permits must install before application for operating license 17883j' II.B-2
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i t (1) NRR:
FYSO - 0.5 my FY81 - 0.5 ny (2)
IE:
FYBO - 0.5 my FY81 - 0.5 r;,
2.
Plant shieldirg to provioe access to vital areas and protect safety equipment for post-accident operation.
a.
Descrirtic' NR issue a letter requiring (1) a radiatico anc shieldino desic, review of spaces around system that may contain highly racio-active fluid, ono (2) implaer,tation of pla,t rodificaticns to perrit adeaJate ecces5 to t i tal areas and prcter* safety ecci;.;ert b.
Schedule:
(1)
Letter issued to operating reactors on September 13, 1979 (2)
First plant review to be completed Decerber 21, 1979 (3)
Issue letter to all applicants by February 1,1980 (4)
Issue Regulatory C ide for comment by September 1980 (5)
Issue ef fective Regulatory Guide by March 1981 1733 33 II.B-3
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FYE0 - 0.5 r,
IE:
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FY81 - 0.8 ry IE:
0.5 ry SD:
0.2 my 3.
Post-accident sampling.
a.
==
Description:==
NRR issue a letter requiring (1) review of the reactor coolant and containment atmosphere sampling systems and the radiological spectre-
=-f ct:mical analysis facilities and (2) modifications necessary to permit perscnnel to obtain sarrples within 1 hr af ter an accicent without incurring an exposure of an individual in excess of 3 rem whole-body or 18-3/4 rem to the extremities, analyze samples within 2 hrs for radioactive nobie gases, iodines, cesiums, and nonveiatile isotopes, analyze within 1 hr for borcn and analyze for chlorices within a shift.
IE is to inspect i r.c l eme nta t i o n,
b.
Schedule:
(1) Letter issued to operating reactors on September 13, 1979 (2)
Issue letter to all applicants by March 1, 1980 (3) Revise Regulatory Guide 1.21 by June 1, 1980 (4)
Issue effective Regulatory Guide 1.21 by February 1980 178833b II,B *-
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FYB1 - 0.5 my SD:
0.1 my 4.
Traininc foi c.itigating core camage, fiRR issue a letter requiring that all operating personnel a.
Desci mtion:
t,e given training in the use of systems already installed at the plant to conteci cr r.itiaate an accident in which the core is severely damaced (see 61sc 1.C.2).
IE is to inspect revised training pro;;ran t.
Sc % dale:
Issue lettet te cperating reactors and all applicarts by fe m tar;
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c.
Resources:
fiRR:
FiSO - 0.1 my IE:
0.7 my IE:
FY81 - 0.7 my 5.
Research on core melt and fission product transport.
a.
==
Description:==
The RES Fuel Melt Research Program will develop a data base and verified methodology for assessing the consequences and mitigation of fuel melt accidents.
The program addresses the range of severe reactor accident phenomena from the time when extensive fuel damage and major core geometry chances have occurred until the containment has failed and/or the molten core materials have attained a semi permanent configuration and further movement is II.B-5
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Stac'es c.'
irproccnents in cc. air, cnt design, (:C., to icduce thc ? ist. of corc res'.; :ccidcrts is alto in:'.udcd.
The program is composed of integrated tasks which include scoping, phenomenological, separate effects, and demonstration experiments which provide results for the development and verification of analytical models and codes.
These codes and supporting data are then used for the analysis of thermal, mechanical and radiological consequences of acc' dents and for decisions related to requirements of design features for mitigation and performance confirmation.
The technical scope of the program includes work in the following areas:
(1) Fuel debris behavior:
Thermal-hydraulic behavicr of fuel melt debris beds (particulate and rubble) - coolability limits and extenced dry-out ir,,essel and in reactcr cavity.
(2) Fuel interactions with structure and soil:
Thermal, mechanical and chemical interactions of fuel melt with structures (concrete, steel, refractory and sacrificial materials and soil).
(3) Radiological source term:
Release and transport of aerosols and radionuclides in fuel melt accident scenarios for radiological consequence assessment.
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i-t.-I c o ;. l a " t interictions:
i c m61 and t.tchanical phenatens t
nsociaton wi th m nl e. e 1,;t t ; a t i c:,s a f r..a. t en f uel m9 t eria l s wi t h i tsctcr coolant and containment fluids and resulting 1 cads en reactor vessel, ano the loading and structural response associated with hydrogen explosions in containment.
(5) Systems analysis coces:
Safety systerr/ mitigation feature response performance analysis codes, and accident consequences.
(6) Mitigation features:
Evaluation of feasibility risk reduction potential requirements and performance of imprc.ed and alternate safety system a"d ~itigation features (containment, vent-filters, and c_ ore retention).
b.
Schedule:
key program-level milestones in FY80-81 period include the f ol l o<. i ng:
(1)
Interim system codes and supporting data base available FY80-81.
(2)
Large fuel melt test facility operating in FY80.
(3) Vent-filtered containment evaluation complete FY81.
(4) Alternate containment concepts evaluation starts FY81.
(5) Core retention device feasibility study starts FY81.
(6) Mitigation feature safety s nthr)bionanalysisstarts FY81.
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Resources:
RES:
FfE0 - 16,0EO.000 FY81 - 16,980,000 6.
Research on severely damaged fuel, a.
Descripticn:
(1)
In pile studies:
Fuel behavior research will include in pile testing to help evaluate the effects of conditions leading to severe fuel damage.
Such tests will be performed in the PBF in FY 1981 and later in the ESSOR facility in Ispra, Italy.
In the PBF, RES will perform a series of in-reactor fuel experiments te determine the effect of cooling rate on dar. aged rod frag entation and oistortion Fission product release and hydrogen generation will also be measured durir,;
the test.
In the ESSOR f acility, similar tests will be perfortred on the longer length, larger fuel bundles possible in the Super Sara Loop.
These tests will aid in the characterization of fuel rod fragments over a large radial expanse and the resulting effect on bundle blockage.
(2) Hydrogen studies:
The objective of this work is to increase our understanding of the radiolytic formation of hydrogen in a reactor and to determine its consequences in terms of pressure-time histories and hydrogen deflagrat#on and detonation.
In addition to the above this work will also II.B-8
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( ) t'.e p>eparation of a compendic-cf hydrogen information related includc.
(c) a to reactor safety, (b) analysis of radiolysis under accident conditions, review of hydrcgen sampling and analysis methocs, (d) effects of hydrogen i
embrittlement on reactor vessel materials, and (e) a review of means of handl ng accident generated hydrogen with recommendations on improving current methods The fiES objective Studies of post-accident coolant chemistry:
(3) in this area is the development of a relationship between fissicn product d
release and fuel failure, and the improvement of post-accident sampling an This wil' be accomplished via the investigation of anal ysis techniques.
fission product release in a sariety of fuel failure e>periments.
(4) liodeling of severe fuel damage:
The effort in this area is the fuel rods beyond 2200cF which suffer a loss in ti;-
deseioptent cf fuel nodels for eutectic liquid gecmetry to compute extensive damage phenomena such as:
fuel slumping, hydrogen generation, fission product release, and formation, rubble-bed particle size, extent of fuel and interaction with the coolant, clad melting, and flow blockage.
ill se b.
Schedule:
The r8F test series on severely damaged fuel rods will begin in (1)
ESSOR tests on severely damaged fuel bundles will begin in FY 1982.
FY 1981.
to Hydrogen studies will begin in FY 1980 and continue through FY (2) 1983.
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(3) Coolant chemistry stories ill comente in FY 1950 anc cor. tins
"'#1 c: ;1eted.
(4) Preliminary planning in the severe fuel damage modeling will begin in FY80 and continue as needed.
Actual code development will probably not begin until FY 1951.
c.
Resources:
RE5:
FY80 - $4,050,000 FYE1 - $5,550,000 7.
Hydrcgen explosion in containment.
a.
==
Description:==
Develop a method to predict the resDonse of containrert sit :tures to hydrogen explci!cns.
Both t",e loading asscciated with the hyv.c;c. cxpicsion and structura4 resconse will be included.
Perform a systematic study of the uncertainties involsed in the predicticn of containment response to hydrogen explosions.
As assessment of the bounds of uncertainty associated with the current state-of-knowledge will be made.
b.
Schedule:
(1) Begin - March 1980 (2) End - September 1981 178834dLd' 11.B-10
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Resources:
(1) FYE0 - 160,000 (2)
FY81 - 580,000 E.
Rulemaking proceeding.
a.
==
Description:==
A notice of intent to conduct rulemaking will be issued to solicit comments on the issues and facts relating to the ccnsideration of the need for design features to mitigate the consequences of degraded core and core relt accidents.
Specific areas for comment should incluce, but not be limited to:
(1) Possible design features to mitigate the consecuences of these types of accidents; (2)
In lieu of such features, additional and supplenental means cf preventing core damage or core-melt accidents, through improved engineered safety features; s
(3) The objective of such design features; (4) The characteristics and functions of such design features-,
(5) The probabilities and consequences of the various event sequences that might result in releasing significant amounts of radioactivity to the environment; 00 b
Task II.E Draft - 32/L -
(6) Ihe expected effectiveness and performance of suggested means of reducing the consequence! of such sequences, in particular, systems for controlled, filtered venting of the containment and for preventing the uncontrolled combustion of hydrogen; (7) Possible modification of other requirements, in particular those for siting, emergency plans and procedures, if such design features were required; Carry out a rulemaking proceeding as scoped in NUREG-0585, Appendix A, Item 10 and revise as necessary related rules and/or regulatory guides.
In connection with this rulemaking, the licensed industry will be required to address the feasibility of filtered vented containment.
b.
Publish advance notice of proposed rulemaking.
(1) Schedule:
April 1980 (2) Resources:
SD:
0.2 my c.
Publish proposed rule.
(1) Schedule:
March 1981 (2) Resources:
NRR:
1 my SD:
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Tat 6 II.E Draft - 12/10/79 E.SILate comments received and research results to establish effective d.
rcle or t u _ad round proposea rule.
(1) Schedule:
Rule to Commission by December 1981 (no hearing);
l ru e to Cor.ission, December 1982 (hearing)
(2) Resources:
(a) SD:
FY80 - 6.0 my fir P: F YE0 - 1. 0 my (b) SD:
FYE1 - 6.0 my fir D - FY61 - 1.0 my 9.
Conceptual Design of Filtered, Vented Containment.
a.
==
Description:==
Order all licensees holding CP or OL to provide conceptual design of filtered vent on containment.
Analysis of design to include safety improvement achievable; additional hazard introduced, if any; proposed design basis; cost and schedule proposed.
b.
Schedule:
Issue orders to all licensees by April 1, 1980.
Replies
'equired in 12 montns.
Review included in Task II.C.1 with other pilot studies.
c.
Resources:
NRR:
FY80 - 0.1 my RES:
FY80 - 0.1 my 178834[
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UNITED STATES OF AMEPlCA MJCIZAR TULUIATOPJf CO:O'ISSIO:I BEFDPE TE AT0"IC SAEY A!.3 LICE :SI?G E0ARD In the Matter of EIPSPOLITA:I EDISON CO:'?AI.7, el al_.
Docket No. 50-289 (Three Mile Island, Unit 1)
AFFIDAVIT OF HARIZY SII7ER I., Harley Silver, being duly sworn, do depose and state:
1.
I am a Senior Project Manager in the Division of Project Management, Office of I uclear Reactor Regulation of the United States !!aclear Regulatory Commission. I am responsible for managir,g the sehty revie of assigned nuclear power plants, including Three Mile Island, Unit 1 Restart Program. My professional qualifications statement is attached.
2.
The answers to UCS' Interrogatories 6-91, 124-127, 143, 144, 158, and 159 were prepared by me.
I certify that the answers given are true and accurate to the best of my knowledge.
Harley Silver Subscribed and sworn to before me this day of-Notary Public My Commission expires:
1788346
Harley Silver Senior Projo-t.anager Division of Pr; ject Manacement Office of i;uclear Reactor Recalation t;uclear Regulatory Conmission Professional Qualifications I am a Senior Project Manager, responsible for managing the safety review for the fiuclear Regulatory Com.ission of assigned plants, including Three Mile Island Unit 2.
I have served in this capacity since October 1973, and had been assigned Three Mile Island Unit 2 from Ma3 1975 until mid-1979.
Since the fall of 1979, I have been assigned as the Project Manager of the TMI-l Restart Program.
I received the degree of Bachelor of Mechanical Engineering from he.-i York University in 1949 and have subsequently taken graduate level courses in Engineering and Business Administration.
Between 1950 and 1952, I served in the United States Air Force as a First Lieutenant.
From 1952 to 1955 ' was employed as a Design Engineer ::y the M. W. Kellogg Company.
From 1955 through 1962, I was employed as a Project Engineer by architect-engineering firms, including Hydrocarbon Research, Inc. and Bechtel Associates.
Between 1963 and 1970, I was employed by the Westinghouse Electric Corp.
in both the Astronuclear Laboratory and eapons Systems Department as, successively, Project Engineer, Supervisor of various design groups, and Manager of Systems Integration.
In 1971, I joined Offshore Power Systems as Manager of Component Engineering, in which capacity I remained until joining the f;uclear Regulatory Commission.
I am a Registered Professional Engineer in the State of tiew York (Certificate fiumber 32892).
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UNITED STATES OF APERICA NUCIER RmUIATORY CO:CIISSIO::
BEFDPS, TUE ATOMIC SArETY A!:0 LICT::SI!D PDARJ In the Matter of VETP.0POLITA I EDISON COPPAI7, e al_.
Docket No. 50-289 (Three Mile Island, Unit 1)
AFFIDAVIT OF GERALD R. MAZETIS I, Gerald R. Mazetis, being duly sworn, do depose and state:
1.
I am a Section Icader in the Reactor Systets Branch, Division of Systems Safety, Office of Iliclear Reactor Regulation of the United States Nuclear Regulatory Commission. My responsibilities include supervising the safety reviews of the reactor coolant system, emergency core coolirg system, and other reactor systems which are assigned to me during the review of nuclear power reactor license applications. My professional qualifications statement is attached.
2.
The answers to UCS' Interrogatories97-123, 133-139, 155-157 were part.ially prepared by me.
I certify that the answers given are true and accuratti to the best of my knowledge.
. Gerald R. I;aze. tis Subscribed and sworn to before me this day of My Commission expires:
Notary Public
} [83 3[}j
GERALD R. MAZETIS PROFESSIONAL QUALIFICATIONS I am employed as a Section Leader in the Reactor Systems Branch, Division of Systems Safety, Office of Nuclear Reactor Regulation. My responsibili-ties include supervising the safety reviews of the reactor coolant system-emergency core cooling system, and other r'eactor systems which are assigned to me during the review of nuclear power reactor license appli-ca tions.
I graduated from the U.S. Naval Academy in 1963 with a Bachelor of Science degree.
In 1968 I received a Master's degree in Nuclear Engineering from Catholic University of America and have been pursuing additional part-time graduate studies.
From 1968 to 1972, I was an engineer with the General Electric Company where I was involved in the licensing of boiling water reactors. My duties included coordinating technical inputs to safety analysis reports and participating in various safety reviews of General Electric reactor systems.
In January 1972, I accepted employment with the Atomic Energy Commission (now the Nuclear Regulatory Commission) in the Reactor Systems Branch.
I have been the assigned reviewer for various safety systems of Davis-Besse Unit 1, Clinton Station, and the B&W standard plant design.
In addition,
.I.have. reviewed. the,1.0CA a paJyses. for,.several..pcess.ur.ize4 wa L.er.rea.c. tors.
n Since being assigned as Section Leader in June 1976, my duties have included the supervision of the safety reviews of both Boiling Water Reactors and Pressurized Water Reactors.
178834{
UNITED STATES OF AFEP.ICA NUCIEAR F5/JIATORY CO:O'ISSION BEK)PZ THE ATC"IC SAMY A*.D LICF?:SI'D E0AFD In the Matter of METROPOLITAN EDISON CC:?AITf, et al.
Docket No. 50-229 (Three File Island, Unit 1)
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AFFIDAVIT OF JO?!? C. VOCEI}EDE I, John C. Vogelwede, being duly sworn, do depose and state:
1.
I am 2 ' Reactor Fr.gineer with the Core Perfomance Branch, Division of
. Systems Safety, Urited States I:uclear Regulatory Commission.
F.y responsibilities include the review of nuclear fuel design and performance data and the related analyses as used in support of power plant licensing subrittals. FJ professional gaalifications statement is attached.
2.
The answers to UCS' Interrogatories97-123, 133-139, 155-157 were partially, prepared by me.
I certify that the answers given are true and accurate to the best of my knowledge.
John C. Vogelwede Subscribed and sworn to before me this day of Notary Public 1788 3
PJ Commission expires:
Professional Qualifications John C. Voglewede Core Performance Branch
(
Division of Systems Safety U.S. Nuclear Regulatory Commission My name is John C. Voglewede.
I am employed as a Reactory Engineer with the Core Performance Branch, Division of Systems Safety, U.S. Nuclear Regulatory Commission, Washington, D.C.
The responsibilities of this position include the review of nuclear fuel design and performance data and the related analyses as used in support of ~
power plant licensing submittals.
My general technical background is that of a nuclear fuels engineer with experience in high-temperature materials, steady-state and transient fuel performance modeling, and scientific application of data processing equipment.
I am familiar with the
- mechanical properties, testing, fabrication, characterization, and criticality control of nuclear ceramics.
I am also familiar with the regulatory requirements associated with nuclear fuel performance.
I hold the degree of Bachelor of Science in Physics (1969) from St. Procopius College and the degree of Master of Science in Computer Science (1976) from Illinois Institute of Technology.
From 1965 to 1969, I was an undergraduate student at St. Procopius College (Illinois Benedictine College) at Lisle, Illinois.
From 1969 to 1977, I was employed as a Scientific Associate with the Ceramics / Fuel Properties Group in the Materials Science Division at Argonne National Laboratory.
During this period, I worked with high-speed data acquisition and control systems in order to study the transient behavior of nuclear fuels in out-of-reactor simulation experiments.
I developed computer models for the analysis of these experiments and was also involved with property specification and model development for the laboratory fuel performance codes.
As principal investigator in a mechanical properties program, I studied high-temperature creep and densification behavior of oxide nuclear fuels.
I was responsible for the nuclear criticality and operational control of a plutonium mechanical testing facility.
In February 1977, I began working for the Core Performance Branch, Division of Systems Safety, U.S. Nuclear Regulatory Commission, as a Reactory Engineer. The responsibilities cf this position include the review of nuclear design and performance data, which are submitted as part of an applicant's Safety Analysis Report. The specific areas of review are the nuclear and fuel systems design as well as the thermal and hydraulic design of the reactor core (Chapter 4 of the Standard Format).
My major responsibility has been the rcview of analytical methods for fuel thermal performance predictions, N.^ rwhich are developed -and. described by each. reactor, vendor and subseouently. referenced.
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in nuclear power plant licensing submittals. These analytical methods are normally implemented in the form of computer codes.
In June of this year, I was reassigned to the Three Mile Island Unit 2 Lessons Lea'rned Task Force as the representative of the Core Performance Branch.
I served in this capacity until October 1979, at which time I was transferred to the Three Mile Island Unit 1 Restart Review Task Force.
I am an active member of the American Muclear Society. A list of my professional publications is attached.
JOHN C. V0GLEWEDE PUBLICATIONS 1.
R. O. Meyer and J. C. Vog1euede, Teq crature Gr:dien: Vacuun Furnace for Diffusion Studies to 2000*C, Rev. Sci. Inst. 42 (7), 993-995 (July 1971).
2.
A. A. Solomon, J. L. Routbort, and J. C. Voglevede, Ficsion-induced Creep of UOg and its Significance to Fuct-element Ferfcr ance, ANL-7857 (September 1971).
3.
J. L. Routbort, N. A. Javed, and J. C. Voglewede, Thermal Crcep of Mircd-oxide Fuel Fellcts, A=. Ceram. Soc. Bull. 51, 389 (April 1972). ABSTRACT 4.
J. L. Routbort, N. A. Javed, and J. C. Voglevede, Ccg rescire Creep of Mixed-oride Fuct Ecllcts, J. Nucl. Mater. 44(3), 247-259 (September 1972).
5.
J. L. Routbort and J. C. Voglewede, Crccp of Niccd-cride FucZ Fellcts at high Stress, Am. Cera=. Soc. Bull. 52(4), 352 (April 1973).
ABSTRACT 6.
J. L. Routbort and J. C. Voglevede, Ccrre!ation of Cride Fuc! Crecp :/ith Microctz'.w:ure and the Influence cn Eucl-element Fcrform:nec, A=.
Ceram.
Soc. Bull. M(4), 398 (April 1973). ABSTPACT 7.
J. L. Routbort and J. C. Voglevede, Final-stage Ecnsification of Niced-cride Fuct, Am. Ceram. Soc. Bull. 52(9), 721-722 (September 1973).
ABSTRACT 8.
J.T.A. Roberts, J. L. Routbort, J. C. Voglevede, and A. A.
- Solomon, Develcp"'en: cf a Nechanical '! ciel cf In-rcactor Fuct Eehavicr: S:a:u:
Report, A';L-8028 (July 1973).
9.
J. L. Routbort and J. C. Voglevede, Crccp of Niced-cride Fuci Fe!! cts Sc:. 5_6 (6), 330-333 (June 1973).
at High S recs, J. Am. Ceram.
6 10.
J.T. A. Roberts and J. C. Voglevede, Application of Deformaticn Mcps :c the Study cf In-reac:or Sahavicr of C ide Fuels, J. Am. Cera=. Soc.
6(9),
472-475 (Septerber 1973).
11.
J. L. Routbort and J. C. Voglevede, Final-stage Ecnsification of Mixed-oxide Fucl, Am. Cera=. Soc. Bull. 5_3(4), 363 (April 1974).
ABSTRACT 12.
J. C. Vogleuede, Thermal Densification of Mixed-oride Fuel, A. Ceram.
Soc. Bull. 53(8), 619 (August 1974). ABSTRACT v s ?.. q3 3 $. Yogi'eved5,' Terfo2h:<cb Addll$ic' bf tashi Mchcrj,' 'M.t 'Thesik
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lilinois Institute of Technology (May 1976).
14.
C. R. Kennedy, F. L. Yaggce, J. C. Voglewede, D. S. Kupperman, B. J. Wrona, W. A. Ellingson, E. Johanson, and A. G. Evans, Cracking and Eccling Schavicr of UOp as Eclated to Fellct-Cladding Nechanical Interaction: Interim Report July 1976, Argonne National Laboratory Report Aht-76-110 (October 1976).
1 em
15.
Ce R. 4,ennedy, J. C. Voglevede, and F. L. Yaggee, Cracking and Crack ReaZing of UOe Pe?Iets in Si.-ulated IVR Po:.'er Cycles, Am. Ceram. Soc. Bull. 55_(9),
821 ($cptember 1976).
ABSTRACT k
16.
C. R. Kennedy and J. C. Voglewede, Relocation Phenomena in UO2 PeZZets Subjected to Simulated LiiR Pover Cycles, Am. Ceram. Soc. Bull. 56(3), 342 (March 1977).
ABSTRACT 17.
J. C. Voglewede, Application of Fuel Properties Data to Out-of-Reactor SimuZation Studice, ie::. Ceram. Soc. Bull.
56(3), 342 (March 1977). ABSTRACT 6
18.
B. J. Wrona, J. C. Voglewede, and T. M. Galvin, Effects of PeZZets Density and Arial Restraint on Failurc Threshold, Trans. Am. Nuc1. Soc. 26, 376-377 (June 1977).
ABSTRACT 19.
R. O. Meyer, C. E. Beyer, and J. C. Voglewede, Fission Cas ReZease frcm FucZ at High Eurnup, U.S. Nuclear Regulatory Commission Report NUREG-0418, (March 1978).
20.
R. O. Meyer, C. E. Beyer, and J. C. Voglewede, Fission Cas Release from FacZ at High Eurnup, Nuclear Safety M(6), 699-708 (November-December 1978).
21.
J. L. Routbort, J. C. Voglewede, and D. S. Wilkinson, FincZ-Stage Dcncificatio';
of Ricci Ocide fuels, J. Nucl. Mater. 80(2), 348-355 (May 1979).
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/
(788353
.