ML20132F115

Trip Rept of Participation in Listed Meetings Re Fuel Rod Behavior & Zircaloy Cladding

ML20132F115
Person / Time
Issue date:	08/07/1978
From:	Powers D Office of Nuclear Reactor Regulation
To:	Kniel K Office of Nuclear Reactor Regulation
Shared Package
ML20132A685	List: IA-83-619, Forwards NUREG-0999,NRC Rept on Sizewell B Evaluation. W/O Encl ML20132A682 ML20132A688 ML20132B510 ML20132B572 ML20132E820 ML20132E840 ML20132F098 ML20132F115 ML20132F385 ML20132F393 ML20132F410 ML20132F430 ML20132F452 ML20132F481 NUREG-0999, Minutes of 771111 Workshop on Simulation of Nuclear Fuel Rods in Loca.Viewgraphs Encl
References
FOIA-83-619 NUDOCS 8507180268
Download: ML20132F115 (23)

Text

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S* g y4 l 5 AUG 7' 1978

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MEMORANDUfl FOR: K. Kniel, Chief, Core Perforinance B, ranch, DSS l 4

THRU: R.O. Meyer, Leader, Reactor Fuels Section, CPB., DSS l 8

FROH: D. A. Powers, Reactor Fuels Section CPB., DSS ,

SUBJECT:

FOREIGN TRAVEL TRIP REPORT

During the period of June 10 through July 1,1978, I traveled to attend '~ '

• and participate in the following:', ] ',,',,',',,",j.;',l,',i',,] ,,,"

1

1. 3rd KfK/NRC annual information exchange on fuel rod behavior

' ,{~] " J~, , )) _,',' '

at Karlsruhe, Germany;  ;

. 2. NRC-funded Zircaloy cladding creep - ~ ~

program review at ECN-Petten,

~ ' ' " ' " ' ' ~ ' ' ~ ~ ' '

the Netherlands; "

_.'"..._._.'...'..'.".- j 1 3. discussion of Zircaloy cladding behavior ~~ ~~ ~ ~ ~ ~

with the UKAEA staff at '

i Windscale, England; .." ...'. _. ..".. .. . . .._'. ' .

l

4. visit to the British Nuclear Fuels Ltd. facility and the ~

l '

Springfields Nuclear Power'Developmerit"Laboratori6s '(formerly '  !

l called the Reactor Fuels Laboratory) 'at'Springf.ie.lds. England;'

... .. . . . . . .. . . ' ,j

5. 4th ASTM Zirconium Conference at Stratf,ord .. . . _ . - . .

.upon-Avon, E.ngland;. .

l

6. 2nd Ad Hoc Workshop on Fuel Rod Ballooning at the Springfields ~

NuclisirTower Development Laborato;rie'sat' Springfields. England. ,~

The following are some overview and summary connents on_each event.

KfK/NRC information meeting {p... . . _- . . . 4 -... ._.

This was the third of such annual informition exchadge meetings between 1 the NRC and Projekt Nukleare Sieherheit (PNS) 'o'f Kernforscliungszentnmi ' [,

v' Karlsruhe (KfK). Dr. M. Picklesimie'r-(RES/RSS/FBRB)a'nd 1 attended the~ ~ '

second portion of the two-week met' ting,' the~ subject 'of Which was ' Fuel ' / . p' i Rod Behavior Under Accident Conditions'." A meeting ' age'nda~, listof" ~ ~

... f}d participants, and a list of handouts;1s]attacyed as~Enclosur'es 1',] 2,',a'nd , .

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_ .-- - _ - - _ - . . - - . ~ . - - . . - -- -

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i K. Kniel

• l AUG 7 197g l respectively. A copy of the handouts has been bound and placed on the j

,i Reactor Fuels reference shelf (P-1110). ~ ~ ,

The discussions were structured to highlight similarities and dissimilarities l j between comparable FRG and US program results. Relative agrbementhas i J

ellet-cladding ' chemical-interaction ~ stiudies i

especiallyapparentbetweenp(MRBT) and the multirod burst test programs. Noteworthy is the fact that i the KfK MRBT program (REBEKA) ~and 'our own NRC-funded MRST pmgram at Oak Ridge National Laboratories (ORNL) have found ~to date no appseent " red-to- i t j rod" interaction that influences'the burst'locatio;n. , ., ,

! A follow-up meeting on August 24, 1978 at ORNL is planned to further align

, the FRG and NRC MRST programs'.' Thos'e from' Germany that tentatively plan

to participate are Dr.F. Erbacher (KfK)', ~ 1)r." M. Weidipger (Kraftwerk Union), ~ ~

y ' ', ~ ~,{1 '

' ' ' ' ~ ~

j and Mr. K. Wiehr (KfK). , ,

At the conclusion of the meeting an interest was expressed to invite the '

Japanese to actively participate'in'futu~re'e'xchang#s, thus making a tri ' '

lateral exchange. The general ~ consensus among the ' participants,' including *

! Dr. M. Ishikawa (the invited delegate from. DAERI),' appeared to '. support suc.h '~i

. ~ . .

4 , ,

i ECN program review meeting i j

Presently the NRC is funding Zircaloy creep experimests at ORNL. While ORNL '

~

is the prime contactor, the Dutch'hase agreed tb furnish the~ irradiation facility for the in-pile creep' pdrtion~of the iirograni. 'And the irradiations ' '

l j are currently flux reactor HFR)(underway at Petten," NorthF in theHolla~nd.,_ Energieonderzock

' 7

~

Centrum Netherland'(ECN

}

A cladding specimen, which is' mounted in an instrumented thimble that was developed at ORNL, can be irradiated in HFR under a spectrum of prototypical power reactor conditio 3 (1.g..' 300-425'C cladding temperatures, exposure 1 i to a fast flux of 5x10 3n/cm' sec,' and up' to + 3000 psig a' cross the cladding  ;

i wall). The data acquisition system 'which includes several eddy-current '

! surface probes, is designed to' provide the capability for continuous in-pile '

measurement of cladding surface displacements. . . . -

3 Such a unique arrangement has the capacity to furnish the first non-theoretical 1 answers to several questionable" aspects of Zircaloy behavior (e.g., the kinetics "

ofcreepdownandcreepout,creptsurfaceconfiguration~s,andBauschingereffect). ~

i Accordingly, the utilization of these experimenta1'results into licensing '

reviews of vendor fuel performance codes is , clearly evident'. ,,

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K. Kniel ' '

AUG 7 1978 i

My visit to the site also included a tour of the reactor facility and the data acquisition system. A list of those participating in discussions is attached as Enclosure 4. ,l,',

UKAEA_ Windscale facility _ , , , , _,

i Discussions with Dr. V. Eldred. a Head of the Fuel Examination Division at Windscale Nuclear Power Development Laboratories (WNPDL) revealed that WNPDL f

- is involved in several interesting areas' of PCI testing.' fuel surveillance, ~

and irradiated-properties testing; ~sonie of thes'e~ endeavors are'similar to ' ' '

(in fact in anny respects actually oVerlav)'th'e hRC-funded prog' rams. The t Windscale staff thought that their researth progre'ss' reports (which are * "

l usually comercial in confidence) were Wing ~ sent to' the' NRC under mutual information exchange agreements' with' the'1JK."Nowevep.~I am not aware of c

anyone in NRR or RES who is re' eivirig(the'se Windscale reports. (In resolve the problem, and if necessary extend their distribution list. ,

~

j pending concurrence by D. Pickmah,)" I've ~ attached as~ Enclosure 5' 6~ list of those participating in the discussions and ~as' Enclosure 6' a list of the i UK research reports given to me'. We concluded.the' meeting'with a tour of '

the post-irradiation examination'ahd tletting}, facilities'." ,',

j , ,

BNFL-UKAEA visit . . - . . . - . . . - . - ~

l A visit to Springfields was made to tour the British Nuclear Fuels Ltd. *' '

l facility and the Springfields Nuclear Power Development Laboratories.  ;

l A list of some of the people withlvhom discussions were' held is attached -

l as Enclosure 7. The laboratory tour included a'stopo'ver at Hindle's infamoue PROPAT rig i i

of.this trip report)(the subjec1;id11;be, discussed in the final sect ASTM Zirconium Conference , , , , , , , _ , . ,,,, ,,,

Over 200 representatives from 21 nations attended the 4th ASTM Zirconium -

Conference in Stratford-upon-Avon. Englandr There wre a total of 38 papers presented (for a listing of titres'and authors see Enclosure B). I have placed a copy of the abstracts on' the Rea~c' top Fuels' reference shelf. During

• a conference luncheon, the 3rd'Kroll Zirconium Metal Award was presented to ~

Dr. Benjamin Lustman, manager of'Reactorwtallurgy"at the Bettis Atomic ~'~ ~~

Power Laboratory. {, , ~ ' ,,,] 7 The 5th ASTM Zirconium Conference has been scheduled for Boston in the

• sumer of 1980. ,

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K. Kniel AUG7 1978  !

Ad, Hoc Workshop j i A one-day meeting of the Ad Hoc fuel behavior group (formerly organized -

l

' a result of UKNII-NRC PWR Ticensing discusselons in 1977) was convened at '

the UKAEA Springfields site on June 30.' An attendance list is ,provided as ,

Enclosure 9.

The subject theme and logical inferences of this second meeting was in no

obvious respects different from that of the first meetin . which was held '

i in the fall of 1977 at the Natiorial' Bureau of Standards NBS). At both meetings, invited speakers presented short technical arguments (see ~

Enclosure 10 for a listing of the Springfields speakers and presentation -

l sybjects) for or against the occurrence of 1.0CA-induced axially-extended '

fuel rod ballooning in which the' cladding circumferential strains are of '

l such magnitude as to impair the core coolability. The following selected

• coments are on relevant topica' that were' presented 'at Springfields, but j

not at NBS.

s

1. French EDGAR tests, which use direct-electrical heating of the ' '

r cladding, have not yielded axially-exten'ded ballooning deformations

l as seen in the Hindle tests. .. " . . ' . ' . ' ' . . ' . ' , . '

! 2. The UKAEA has replicated Hindle's PROPAT apparatue at the Windscale ' ~

site and has demonstrated the capability of duplicating the balloons as seen by Hindle. ,, 7 ,,' ' '

l 3. Hindle's new bundle test was conducted in a muffle furnace. Following '

i

. a pre-test soak at 695'C. the rods were creep-ruptured in the high

• l alpha-phase. The results are compa'rable to Hindle's single rod tests.

l 4. A new transient fuel perfomance code called MABEL has been developed by the UKAEA and subsequently applied by the Nuclear Power Company l l I

l .

to search for the likelihood of in-pile ballooning'as seen ex-pile by 1 Hindle. Unfortunately, rudimentary aspectsthat are missing in the '

code ineffectuates its present utility.' (For those~ interested. I ~ '

have a copy of a report that des ~cribes ,the co'de,.) '  :

As at NBS. the meeting adjourned with a division of opinions amongst the participants; namely, the Springfields UKAEA staff unconvinced as to whether PWRs are coolable following a loss-of-coolant event, and the '

remainder of the participants convinced that the Hindle tests are irrelevant to PWR flow blockagei eval'uatibns. Perhaps some progress was i

made and is best expressed by a quote from the meeting conclusions by .

"])

D.Pickman(DeputyHeadofSpringfields): .. . .

p4 f

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l l _ - _ _ _ . . _ ~ ,. _ .. , _ _. _ _ _ _ . _ _ _ _ . _ _ . _ _ . . . . _

K. Kniel , Aug 7 1978 "Maybe the problem is not as serious as we previously expected." , ,

Dale A. Powers Reactor Fuels Section Core Perfonnance Branch -

. Division of Systems Safety -

Enclosures:

As stated - -

cc: S. Hanauer R. Mattson/F. Schroeder ~~'

R.Fraley,ACRS(16) - - '~" ' " " - -

• ~~ "* - -'- ' ' "

SD & RES ads

"~' " " ' ~ ~ "

OR. SS&EA. PM & SS ads IAE(4)

~- - " ~ ~ " ' '

~* -

- -~'

NRC POR D. Ross -- -~

P. Check - ' - .~

P. Picklesimer " - - -

- - ~ - - - -

P. Showoon CENTRAL FILES J. Lafleur - ' - - - - ~ - - -

NRR RDG FILE Fuels Section - *-- "-

CPB RDG FILE T. Novat " - - "' -

Z. Rosztoczy -- - - -

V. ste11o - - - -

P. Boehnert -" -

i

, W. Johnston * ' - - --

l J. McGough -

C. Hann PNL

-- '-- - r --

J. Dearien. PNEL . . . . . . . . . . .

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.r,..., CPB/ DSS DSS /CPB A jj l

.u.....> OPowers:jt RMeye M ilf '~

. . , . , h/A-/78 8/7/78 NRC FORM SIS (9 76) NRCM 0240 W w.o.oov.anu.= ,pm,= ,ime errec., tote .ese.es4

ENCLOSURE 1 Agenda of the American - German Workshop on Tuel Rod Behavior under Accident Conditions, June 12 - 14, 1978 in Karlsruhe Monday.' June 12 -

- Workshop Opening A. Flage, M.L. Picklesimer ,,

Morning Session - Status and results of FNS 4238 bundle F. Erbacher, K. Wiehr experiments

- Status and results of ORNL-MRST R. Chapman bundle experiments Af ternoon Session j- Discussion *cf bundle experiments (open pre,blems, modelers's needs,_

next steps, test matrix for furth'er bundle tests).

Tuesday, June 13 Morning Session - Transient burst tests with irradiated Art Bauer cladding-status, results, next steps

- Overview and PIE of PCM *an'd II-tests R. Hobbins, W. Quapp in PBT

- Status and results of out-of pile- P. Hofmann

• . PCM tests of KfK

- Ceneral discussion: Conclusions, next -

steps and modeler's needs.

l

.2- .

1, .

Afternoon Session - Embrittlement Criteria

• Tom Kassner

- In pile LOCA testa in the Int-Loop of E. Karb ,

FR2 (Status, results, strain profiles, E. RXpple t metallography, next steps) Pt Hofmann j

. F. Wunderlich '

- In pile LOCA test in PSF (status, W. Quapp , c ,

results, next steps) , ,

- Discussion (burnup effects on fuel .

behavior, open questions, further .*

procedures) e, I Wednesday, June 14 Y Morning Session - Out-of pile experiments i,n COSIMA and G. Class

1. possibility for reference' tests to PBF K. Hain - '

- High temperature creep model in SSYST

• M. Bocek (NORA) . S. Raff ,

i i (

- New Developments in MATPRO (effects of D.L.Hagraan oxygen, fission gas, deformation beha , 1 vior, failure criteria, annealing of I irradiationdamageandcoldwork) *

- Relative importance of material proper

• D.L.Hegman- 14- ,

ties and uncertainties ' , ' -

R. Oehlberg l

Concluding. Session  :

- Discussion on open problent concerning

• materials properties model'in's. General discussion on present out-of pile and 8 inpile experiments and results 2

- General discussion on open questions and -

I fuel behavior research work needed in the .*

near future.' *

• ENCt.0SURE 2 1

l American - German Workshop on ,,

Fuel Rod Behavior under Accident Conditions, June 12 - 14, 1978 in Karlsruhe l

i I,

l l

e List of participants: ,

t i M,0. Picklesiser USNRC a

D.A. Powers V.J. Quapp Ecac M.R. Martin " l D.L. Magroan R.L Mobbins R. Oehlberg Electric Power Research Inst.  :

T.F. Kassner Argonne Nat. Laboratory '

I R.H. Chapman ORNL i

A.A. Bauer Battelle Columbus Labs M. Ishikawa JAERI, i l

C. Cheliotis KW-Erlangen- i H.C. Weidinger a

F. Wunderlich A. Chakraborty GRS-K81n W. Gulden IKE-Stuttgart a

M. Schindler ,

M. Bocek gtK a

G. Class "

S. Dagbjartsson F. Erbacher "

A. Flege G. Hofmann u- '

F. Hofmann "

E. Karb "

S, Leistikov n

5. Malang R. Meyder ,

U. Muller u W.B. Murfin Del. of Sandia to KfK , I H. Neitzel KfK a l

5. Raepple ,

G. Schan n K. Wiehr I

l ENCLOSURE 3 .

1 American - German Workshop on ,

Fuel Rod Behavior under Accident Conditions, June 12 - 14, 1978 in Karlsruhe List of haadouts l) F. Erbacher, M.J. Neitsel, K. Wiehr .

Studies on Zircaloy fuel clad ballooning in a LOCA.

Results of burst tests with indirectly heated fuel rod simulators.

2) R. Chapman Results and status of ORNL single rod and multirod bundle -

tests in a steam environment.

3) C.'.Cheliotis...H.C. Weldinger Multi Red - LOCA - Test t.ith Zry - cladding sections in 3 x 4 - Geometry.

I-

4) A.A. Bauer i Transient-heating tube-burst tests of spent-fuel Zircaloy cladding.

$) D.0. Hobson Cladding creepdown under compression.

6) R.R. Hobbins, W. Quapp

~

Overview and PIE of PCM and IE-tests in PBF. l

7) P. H$feann, C. Politis

• Chemical Interaction between UO 2 and Zry-4 in the temperature range between 9oo and 15oo*C.

8) T.T. Kassner, H.M. Chung, A.M. Garde -

Development of an oxygen embrittlement criterion for Zircaloy fuel cladding applicable to LOCA conditions in light va ter reactors.

-2, ,

( ,

i

9) E. Rarb .

I I

a.In pile experiments in the FR2 DK-Loop on Fuel rod i behavior during a LOCA.

b.In pile experiments on LWit fuel behavior during LOC accidents.

F. Wunderlich ,

c. comparison between FR2 - Fra - irradiation and FWR-Conditions. ,

lo) W.J. Quapp -

l Results of the first nuclear blowdo s tests on single rods

( (LOC-1I series in the FBF).

11) G. Class, K. Main Main items of COSIMA work.

12) M. Bocek .

. High temperature creep model in SSYST NORA. *

13) D.L. Hagraan

}'aw developments in NATPRO. ,

i

14) C.S. Hartley f

Constant true strain-race testing using

> optical strain sensing.

15) D.L. Hagraan

a. Relative importance of material properties.

b. R. Oehlberg Influence of material properties and uncertainties on LOCA calculations.

6 6

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1 ENCLOSURE 4 -

I.

)

i i

i ECN PROGRAM REVIEW' MEETING LIST OF PARTICIPANTS 1

1 ECN T. Van Der Kaa. ,

R. Swanentwrg De Veye i i

N.VanDerKleij

- J. Goedkoop 4

NRC M. Picklesimer D. Powers ,

l me 9

e i

O i

i k

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e

t ENCLOSURE 5 WINDSCALE MEETING PERSONS CONTACTED UKAEA V. Eldred E. Hyam A. Garlick R. Sumerling A. Stuttard AtomicEnergy)

(SouthAfrica Board D. De G. Jones O

e 4

D G

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1 ENCLOSURE 6 .

U.K. REPORTS RECIEVED j l

1. A. Garlick, " Fracture of Zircaloy Cladding Under Simulated Power Ramp Conditions " J. of Nucl. Mat. , 49_, No. 2, p. 209 (1973).  !

2. J. Prestwood and R. Sumerling, "NDT for Irradiated Reactor Fuel Pins by Eddy Currents and Gama Scanning," Non-Destructive Testing, p. 90 (April 1975). ,

3. A. Garlick, R. Sumerling and G.L. Shires " Crud-induced Overheating Defects in Water Reactor Fuel Pins," J. Br. Nucl. Energy Soc., H.

No.1,p.77(1977).

4. G.G.' Bond D. Cordall, R.M. Cornell,'W.N. Fox, A. Garlick, and D. A. Howl, "SGHWR Fuel Perfomance Under Power Ramp Conditions," J. Br. Nucl. Energy Soc. , 3, No. 3, p. 225 (1977).

5. 'R. Sumerling, R. Hargreaves, and D.H. Willey, " Fuel-cladding Ratchetting in SGHWR Fuel Pins," J. Br. Nucl. Energy Soc., E. No.1, p. 41 (1978).

6. A. Garlick, " Examination of an Instrumented Fuel Element After Dryout Tests in Winfrith SGHWR," J. Br. Nucl. Energy Soc.,16 No.1, p. 71 (1977). ,

7. A. Garlick and J.G. Gravenor, "A Criterion and Mechanism for Power Ramp

• Defects,"UKAEAunpublishedinternalreport(1977)[ -

8. K.M. Rose, " Stable Defomation of Zircaloy Fuel Pin Cladding in a Hypothetical Loss-of-Coolant Accident," UKAEA Report DC0 Ref. 7154(s), i June 1978. -

9. R.J. Burtor$ and B.J. Holmes, "Some Analysis of Clad Ballooning in a ,

i PWR Following a Major LOCA." Nucl. Power Co. Report, PWR/R30, June 1978. ,

10.' T. Healey, B.D. Clay, and R.B. Duffey, " Analysis of the Axial Ballooning Behavior of Directly Heated Zircaloy Tubes" CEGB Report, RD/B/N4154, September 1977.

o G

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. ENCLOSURE 7 BNFL-UKAEA VISIT PERSONS CONTACTED f BNF K. Sumner l UKAEA F. Trowse E. Hindle R. Shaw '

M. Mallet D. Loche

^

ORNL R. Chapman AtomicEnergy)

(SouthAfrica Board D. De G. Jones Nuclear Research Center (Israel) Z. Hadari .

t e

0

ENCLOSURE 1) ,,

LIST OF PAPERS ,

i (1) Zizoaloy Performance in Light Water Remotors.  !

JTARoberteandFEGelhane(ElectrisPowerResearchInstitute) 3 (2) The Effect of Intermediate Particles on Localised Corrosion of Sirealoy. -

l L lande and E Yides (Institutt for Atomenergi) i l

(3) Mechanical Properties, Texture and Microstructure of ErNb}8n1 as a I Punction of the Final Esat Treatment.

EIMatuoha,IJWerner,3WildhagenandIWilhelm(GESS)

(4) Dustility of Eiroaloy Canning Tubes in Relation to Stress Batio in Bianial Testing.

T Andersoonand A Wilson (Sandvik AB)

(5) The Loonlised Dustility Method for avaluating zirealey-2 Cladding.

L Coffin (Genormi Electrie Company)

(6) EWU Review on Corrosion and Dimensional Behaviour of Ziroalor under Water Reactor conditions.

F Garsarolli, R Mansel and E Tenohkhoff (Ermftwerk Union AG) and SReschke(NuklearRohrgesellschaft)

(7) FurtherEvidenceofZikwaloyCorrosioninFuel.ElementsIrradiate'd in the Winfrith SGEWR. -

RSumerling,AGarliok,AStuttard,PSimsandFWTrowse(UKAtonio AnergyAuthority)

The Performance of Irradiated Copper and Ziroonium 3arrier-modified *

(8)

Ziroaloy C1mAA4 ggggy gigglgggg pg{ gggggggggg, D5Tomalin,R3AdamsonandRPGangloff(GeneralElectricCompany)

(9) A Survey of Chemical hvironm6atsfer Activity in the hbrittlement of Siroaloy-2.

WTGrubb(GeneralElectricCompany)

(10) The Effect of Irradiation on the 8trungh, Dustility and Defoot [

SensitivityofFullyRecrystallisedZirealoy(Tube.

EPetternoon(AB Atomenergi),GYesterlund ASEA-ANM)and T Anderseen(8andvik AB)

(11) Primary Creep of Zirealoy-2 Under Irradiation.

Y Pidlerie (Atomic Energy of Canada Ltd)

(12) Analysis of Irradiation Growth and Multiazial Defo mation Behaviour of Sirosley Puel Ch'div.

G S Clevinger, B L Adams and E L h tty (Baboook and Wiloom Co)

D

r

(.

I (13) The Analysis of BWR Fuel Pin Length Cheaps. j J B Earbottle and R M Cornell (Central Electricity Generating Board)

(14) Irradiation Crowth in Cold Worked Zircaloy-2.

R A Murgatroyd and A Rogerson (UK Atonio Energy Authority) .

(15) simulation of Reactor Irradiation Induced Damage by Eigh voltage Electron Microscopy.

S N Buckley and S A Manthorpe (tfE Atonio Energy Authority)

(16) Stress Corrosion Crack Initiation and Growth, and the Formation of Pellet /CladInteractionDefects.

E Tiden and L Lunde (Institute for Atomenergi)

I (17) Out-of-Pile Testing of Iodine Strees Corrosion Cracking in Zircaloy l' Tubing tinder the Aspects of the PCI Phenomenon. '

M Poehs, I Stehle and E Steinberg (Kraftwerk Union AG)

(18) Iodine-Induced Stress Corrosion Cracking of Fixed Deflection Stressed Slotted Rings of Zirealoy Fuel Cl w W .

R 8ejnoha (Combustion keineering Ltd) and J C Wood (Atonio Energy of Canada Ltd). .

• ~

(19) An SCC Model for Pellet / Cladding Interaction Failures in LVR Fuel Rods.

J T A Roberts (Electric Power Research Institute), 3 Salth (Unknreity of'Mannheeter.Insi)u6e af. Science and Technology), E.h Jones, D Cubiocotti '

(SRI Interactionki),)F L Yagee (Argonne National Laboratory-) and A E Mille (StanfordUniversity <

(20) Hydride Cracks as Initiators for Stress Corrosion Crseking of Zircaloys.

E Cox (Atonio Energy of Canada Ltd)

• l 9

(21) Predicting High-Tseperature Transient Deformation from Microstructural 1

Models.

E E 8111h and R A Holt (Atonio Energy of Canada Ltd)

(22) A Microstructural-Based Constitutive Relation for Dilute Alloys of et-Zireonium.

C 8 Eartley, Ju-John Lee (University of Florida), A Carde, H M Chung and T F Kassner (Argonne National Laboratory)

(23) Simplified Equation of State for Zircaloy Cladding Plastic Deformation.

D L Hagrus and P E MacDonald (IG & 0)

(24) A Comparison of Erperiaental Cladding Microstructure Resulting from UO2 -Zirealoy Interaction with a Diffusion Assessment of Oxygen Transport for a Coupled Two-Media Probles.

A W Cronenberg and M S El-Genk (30 & 0) i

f

(,

1 (25) Advances in Understanding and Predicting Inelastic Defoammation in Ziroaloy.

S Oldberg Jnr (Electric Power Research Institute), A K Miller (Stanford Univoreity), D Lee, C F Shih, F Zaverel (Genormi Electric Company), R M Pelloux, R C Ballinger and G E Lucas (Massaehusette i InstituteofTechnology) ,

1 (26) Zircaloy Cladding Deformation .in a Steam Environment with Trsnsient  !  !

Beating.

R R Chapman, J L Crowley, G Eofmann and A W Longest (Oak Ridge NationalLaboratory)

(27) Influence of Iodine on the Strain and Rupture Behaviour of Zircaloy

Cladding Tubes at Eigh Temperatures.

F Bofmann (Institut fGr Material und Fortk&rperforschung)

~

(28) Studies of Zircaloy Fuel Clad Ballooning in a LOCA - Results of Durst Tests with Indirectly Beated Fusi Rod Simulators.

F Erbacher, M J Neitzel and K Wiehr (Institut fGr Reakt8rbauelemente) i (29) The Effect of ei-Phase Beat Treatusent on the Subsequent )-Phase Ballooning Behaviour of Zirealoy-4 Fuel Sheaths.

C E L Bunt and W G Newell (Atonio h ergy of Canada Ltd)

(30) The Axial Ballooning Response of Zircaloy Fuel Tubes -

During Transient Heating. .

B D Clay, T Healey, (Central Electricity Geneirating Board) and R Stride (UKAtomicEnergyAuthority) ,

i (31) Tube-Durst Response of Irradiated Zircaloy Spent-Fuel Cladding to Transiont Besting.

AABauer,WCallagherandf,MLowry(Battelle)

(32) A Proposed Criterion for the Oxygen Babrittlement of Zircaloy-4 Fuel Cladding.

ASawatsky(AtonioEnergyofCanadaLt4)

(33) The Effect of Oxygen on the Deformation of Zircaloy-4 at Elevated Temperatures.

A 8 Riska11a (Combustion Engineering Ltd), R A Holt (Atonio Energy of Canada Ltd) and J J Jonas (McGill University)

(34) Evaluation Models of Ziroaloy 0xidation in the Light of Recent Experiments.

H Ocken (Electric Power Research Institute), R Biederman (Worcester Polytechnic Institute), C Hann and R Westerman (Batta11e)

(35) Chealcal Interaction netween U02 and Zirealoy-4 in the Temperaswee Range Between 900 and 1500'C.

P Rofmann and C Politis (Institut fdr FertkorPerforschung)

c.

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(36) The Interaction of Oxidation and Creep in Ziroaloy-2.

R Burton, A T Donaldson and G L Reynolds (Central Electricity GenerstingBoard)

()7) h hbrittlement of Zircaloy Clad M1 Rode Irradiated Under Film Boiling Conditions. ,

R R Iobbins, S L Seiffert, 5 A Floger, A S Mehner and P E MacDonald (F,&G)

()S) Developent of an Oxygen kbrittlement Criterion for Zirealoy Cladding Applicable to I4CA Conditions in Light Water Reactors.

R M Chung, A M Garde. T F Kassner (Argonne National Laboratory) 4 e

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I[ ENCLOSURE 9' (

mm. . United Kingdom Atomic Eners Authority, -

Mr. D.O. Pickman , (NorthernDivision)

,, - Springfields Nuclear Power Development Laboratories, ,

Springfields, Salwick,.

Preston, Lancs. PR4 ORR 'k Mr. R.A. Shaw .

Mr. E.D. Hindle Mr. C.A. Mann , , ,

Dr. K.M. Rose .

Reactor Development Laboratories,

• Mr. A. Garlick United Kingdom Atomic Energy Authority, Windscale Works, Salla Field,

,. Seascale, Cumbria CA20 1FF Dr. E.D. Hyam " " " -

Dr. D. Hicks . United Kingdom Atomic Energy Authority,

, (NorthernDivision),

Risley Nuclear Power Development, Risley,

• Warrington WA3 6AT .

Mr. J.G. Collier AEIU Building 329 United Kingdom Atomic Energy Authority Harwell, Sidcot, o' 0xfordshire OX11 ORA Mre K. Pearson United Kingdom Atomic Energy Authority, AEE Winfrith,

• Dorchester, Dorset.

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l iDr. T. Healey Central Electrical Generating Board, Berkeley Nucl, ear Laboratories, Berkeley, Glos. GL13 9PB Mr. M.C. Whitaker Central Electrical Generating Board, Generation, Development and Construction Division,

. Barnett Way, Barnwood, Glos. GL4 7RS Mr. A.H. Conway-Jones ..

Kr. J.E. Edwards Central Electrical Generating Bos.rd, Nuclear Health & Safety Department, Courtenay House, ,

18 Warwick Lane, London EC4 4EB N.P.C. .

Mr. I.T. Rowlands Nuclear Power Co.(Whetstone) Ltd., -

Cambridge Road, Whetstone, Leics. LE8 3LH .

Mr. R.J. Burton -

Mr. J.N. Beker

.I

" " "~

Mr. D.A. Ward ,

France .

Mr. Chagrot Dept. de Surete Nucleaire, Safety Division,

• Institut de Protection, Fontenay aux Roses,

. Paris, France.

e U.S.A. .

Mr. H.H. Klopfer General Electric Corporation, San Jose, ,

California, U.S.A.

Mr. R.H. Chapman Oak Ridge National Laboratories, Oak RidEe, Tennessee, U.S.A.

(, *

( -

continued U.S.A.

Dr. M.L. Picklesimer Fuel Behaviour Research Branch, Division of Reactor Safety Research,

- United States Nuclear. Regulatory Commission, Washington DC 2055 U.S.A.

Mr. D.A. Powers United States Nuclear Regulatory Commission,'

Rockville, Maryland,

~~ ,

Washington D.C.

U.S.A.

Mr. G. Parry Combustion Engineering Inc.

Windsor .

Conneeticut, U.S.A.

Mr. A.L. Lowe Eabcock & Wilcox, Lynchburg,

- Virginia, .

U.S.A.

Mr. T. Papazoglou Mr. F. Kingsbury Westinghouse Nuclear -

?ittsburg, ,

- . Pennsylvania, U.S.A.

Mr. Leo Van Swan Exxon Nuclear Richland, Washington State, U.S.A.

Mr.'R.A. Adamson General Electrical, Vallecitos, ,

California, U.S.A. .-

Germany Mr. F. Erbacher Institut fur Reaktorbauelemente (IRB)

Kernforschungszentrum, 75 Karlsruhe, Postfach 3640, West Germany ,

Mr. A. Fiege Projektlei1Eung Nucleare Sicharheit (PITS-PL)

Kernforschungszentrum, 75 Karlsruhe, Postfach 3640, West Germany.

O

(. .

Gaman con'. tnu+ -

Dr. A.K. Chakraborty Gesellschaft far Reaktorsicherheit abH Glockengasse 2 .

5000 Edin 1, F1G Dr; A. HBfler Gesellschaft far Reaktorsicherheit mbH 01ockengasse 2 5000 Kein 1, F to Dr. Weidinger Kraftwerk thion (KWU)

Erlangen West Germany Mr. T. cam P &E< c. 'i n i tii ;b r .

/ '.xecu t ivo,

.u..t....  !,i:~ . i , t .one Inspectorate,

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'..sr i..n . ",, t i . 01.

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l ENCLOSURE 10  ;

I Af[ H0C MEETING THOSE MAKING PRESENTATIONS NRC M. Picklesimer Summary of NBS meeting UKAEA D. Pickman Summary of ASTM Conference ORNL R. Chapman MRBT creep rupture tests IP M. Chagrot EDGAR tests KfK F. Erbacher REBEKA tests UKAEA A. Garlick Windscale ballooning tests UKAEA E. Hindle UKAEA bundle test .,

UKAEA K. Rose -Theory of stable ballooning i

NPC R. Burton MABEL code t

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