ML042260365
| ML042260365 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/15/2004 |
| From: | Hofmann P, Karb E, Petersen C, Schanz G, Sepold L, Zimmerman H Govt of Germany, Institut fur Material- und Festkorperforschung |
| To: | Office of Nuclear Reactor Regulation |
| Byrdsong A T | |
| References | |
| 50-413-OLA, 50-414-OLA, ASLBP 03-815-03-OLA, Catawba-Applicant-D, RAS 8322 | |
| Download: ML042260365 (13) | |
Text
- 1.L-12j2 0 4 12 04 -Linda Hall Library 6169 kE65
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Lv DOCKETED USNRC RESULTS OF'TRE1FR2 IN-PILE TESTS ON "i:
LWR FUEL ROD BESHA ')
- ngus nI4l.A .:. : . L.
1EU Sepld
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,r . OrFICEQFSEETAftY PJofmann ,
z) 2)22 CtPecersen , G.Schani f p ;HULEMAKiNGS AND , li.Zlerma ).z
-ADJUDICATIONS STAKernforFcungszntru I Es !uptabtetlug Ingenieurtebhnik 0.
4 I: stipti PW a Material- und Festkfrperfothung2 .
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'D M70~ Karlerube NOTICE: ThiS matedal may be prOeetlderai Republic of Germany.
by copyofgM law (le 17, U.S. Code)
ABSTRACT - --
Presented are the results of the FR2
- behavior under LOCA conditions performed Ia-Pile tests on:fuel rod with PWR-type unirradiaved and irradiated (2500 to 35000 MWd/t) not indicate major differences from fuel rods. The burst!-4ta: do out-of-pile results. Na in fluence of burnup on the burst data
-4 kith major clad deformations of the was observed. In the regions mented pre-irradiated rods the frag-fuel pellets were found crumbled within the fuel ro4. The posttest examinations indicate clad tion to be comparable to out-of-pile mechanical beehavior an i a.
results and a relativity small fission gas release during the transient.
C4 OBJECTIVES, TEST PROGRAM the in-pile experiments simulating
-ii -of-coolant accident (LOCA) in a pressurized formed in the FR2 reactor at the Kernforschungszentrum the second heatup phase A6 a loss-water reactor (PWR).were per-
- 1.IL The research is part of the Nuclear Karlsruhe (KfK)
I The main objective of the FR2 In-PileSafety' Project's fuel behavior program.
about the effects of a nuclear environment Tests was to provide information eat on the mechanisms of fvel rod failure under LOCA conditions. The nuclear mainly by the genuine nuclear heat generation environment is characierized in UO2 fuel. X:
The tests were conducted with irradiated short-length single rods.unirradiated as well as with previously The objectives of the program tequire ii a comparison with non-nuclear
- 1 .trcally heated rod simulators tests. Therefore,' reference testp with elec-were conducted in the' in..pie'loqop;under ditions identical to those of the nuclear ton-i-s given -inTable 1.-The main parameter tests. the entire test program-a I of burnup, ranging from 2,500 to a parameter the rod internal pressure of the test program tka, the degree maximum of 35,000MWO/tty. As a second 1
at steady state temperature. The pressure was varied betw'een 25 ba'rs'and 125 bars
,1
- 2 to be expected during the lifetimes of range used was larger than it is adjusted during the preparations PWR rods. The depired presku're was I, I for the transient! test by adding;bolium II 1i
- 11k. .
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NUCLEAR REGULAWRY COMMISSION /
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In the matter d- _____________ /
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Applicant _ RECEIVED Intervenor REIECTED Cont'g O _'r_____ wrnA.w 7f'iliXy Conrator__ DATE O er_ _ Witnss'
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.1i... ta t d ,jSo AB 2EtjN' 9!EL TEJS TS ON, TEST I'ATRIX: I: ; : -:: , 7. ."i, -
- I-Te. Nub,of ,J Number Targ 99t Raneg cii type of lest*oos Series of of Tests Burn up PressuuC
- - ' Irradated i Sta te 't per atur- -
'- 1 A ._
M 1/:6 barI
. Cal t14l ibratinn.I Igpn A -- L_ 1.. -,
- 100
. ,; = - q - - : ftl rred1 &ted floo ; :s rtei - - iau >t^Yt f R ^iE : .o '
s
' '.* rradiated I-'"}'!5 Rods C 6 F 25i 0
f- 110 .- .
.14 -PSe~l amfiet-ci E 6 l 5 20 -120
- - 55
- 0 1 : t ' s1: ( i . .$ d:.t G1 6235 0t - 90
, ._ *~~~~~~~~Irdae
',,.'':: Rods : _
l0 60 - 125 Etectr;ir;c l4l y Heat ed
- 110.
- Sn
'0 ; to t^n' fission gas generated during the previous irradiations. ReatuP var td!between 6 and 20 K/s.
rates EXPERIMENTAL CONDUCT T..- each test the test rod is exposed to a standard temperature hifstory -.
'deriveu from calculstion for a'PWR fuel rod under the .eoditions of the fe s'conie. laeitup phase during a cold-leg break LOCA. The transient is initiated by interruption of the loop:coolant flow and depressurization of the 4{
coclarti During the subsequent heatup phase the test rod power is kept con-stan- q.ltil the target cladding temperature of approx. 1200 K is reached.
AL tt. temperature the rod power is rapidly reduced by reactor scram The rt.st 4r3cedure is given in Fig. 1. -
- h:: test rod internal pressure i-sadjusted prior to the transient,
-uring the transient the gas is confinedin the rod siIh thar the intornAl b
preswzrfe is measured but not controlled. The deformation and the burst of the rod cladding are monitored by means of the cladding temperature and rod xnternal pressure traces.
(-ts,4dding temperature was measured by six thermocouples resistance' spot-
-we._,od to the rod surface at six different axial and azimuthal locations.
Two rjir-erent attachment versions (A and B) were used.
2-134 11, o
L . Libay
- 14 , f .Li - 2 4 1.2~4 - Linda Ha1 Library: 816 926 8785 P TEST RESULTS AND RESULTS OF NON-DESTRUCTIVE PTE AkV_0 Burst'Data The burst temperatures are plotted versus burst pressures iIt ia.. ig Th' d'ata obtained frdm -irradi.re and irradiated rods 'ie indi.¢ited by ji diffetent~symbols,-Fof corpardsuintwo dashed curves appioximatin z e t.:
-of-pile ORL *) Multirod Burst ,Test single-rod resulte are inc1. ed;,
There was no diffeece foutd between the burst data-rom unirradfltedrods :
and those irradiated to the different burnups,. Furthermore, burstrX iessur§ -
and burst temperatures measured during the in-pile tests .ie withpthee ta band obtained from out-of-pileeexperimetits with-electricilly heated'fuel' .<
rod simulators. This was confirmed by the results from the own st i'ator, (SSS) tests being performed tmder"'identical conditions ln the in-pi-0e tost.
loop. The BSS data are included in Fig. 2.
The definitions of burst temperature and burst pressure used in the evaluation of the FR2 In-Pile Tests are as follows:
The burst temperature is defined as the temperature of the cladding at the burst location at burst time. It was determined by extrapolation from the thermocouple closest to the burst location. In order to compensate: for the deviations of the surface-welded thermocouples a correction valuetwas.
added. In this method azimuthal temperature variations cannot be taken into account.
The burst pressure is defined as the rod internal pressure measured at
'( the beginning of the fast pressure drop, i.e., when the pressure gradient.
_, ) Ap/,t exceeds the value of minus 10 bars/s. The pertinent time after initiation of the transient is called burst time.
Pi In Fig. 3 the measured maximum circumferential strains AU/UI (burst strains) are plotted versus burst temperatures. 0
... X.,
Here again the results from unirradiated and irradiated rods are indi-cated by different symbols. The three data points from the simulartor (BSS) tests available to date are included in this diagram. The results from the FR2 In-Pile Tests lie in the range between 25 and 67 % circumferential strain. (The 67 % limit is reached when the deforming rod touches the
- . shroud.) The results do not show an influence of irradiation on the burst sCrain and do basically correspond with the maximum deformaiiois found in
.-. out-of-pile tests using an indirect heating of tht cladding ' , including
- - tests performed with spent reactor fuel cladding.
A correction factor mentioned above was applied to the burst tempera-tures in Fig. 3. According to microstructural investigations of the clad-
- s. .
ding material (section 4.2). this factor could have been overpredicted for test rods using the thermocouple version A. In this case, some of the data points have to be shifted to somewhat lower temperatures in the diagram.
Oak Ridge National Laboratory, Oak Ridge, Tennessee (U.S.A.)
- Post-Test Examination 2-135
JUL- 12-2004 12:04 Linda Hall Library 816 926 8785 P'6 Cladding Deformation Profiles The axial strain profiles obtained with test series F (20,000 HWd/t O.
. . burwnp) are given in Fig. 4. The claddings exhibit deformation on the.
- t entire length (500 mm). The ballo6ned parts of the rods are located.. etweei 20 and 400 S above; thb bottom df fuel stack, i.e. 'within the instfumented
. . . _. i
.... j section of the rod.. Fibg 4 shows also the normalized -:xialpower profiles,:
R ,.
2 :
ifor each of the F-Tests. The position of maximum strain is usually at or close to the position 'of maximum rod poiwer. However, the relatively ,tat n':
poeir profile may have allowed other parameters, e.0g. wall thickness ftuel:
ectentticity, increase.of cl adding riass- and heat transfet surface byTC
- A:.
I,.
¢ ! v lead ,:t6 have influenced the position of mixi6m, strain. t 5 uni rLnes. ;
this stateeinthin demonstrating the rindom distribution of the pos-it1n of.
maxIixnum strait under conditions of ext emely flit rod power profileS
- < (". ;,, -' ', -, ':' .t'i..
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- deformation extending to the 67 % limit at a length
'cladding :
'_ i-i, Asout1 10 cm was obtained with Test Rod E5. The strain profile atd t4, post-f . .: .
test Teiotron adiogreph'of this rod are given in Fig,'6. An extensi 'of the ballooning above 67 Z was prevented by the shroud suroinding the -test rbd suth that the cladding had to continue its ballooning into the axial dite-..tion. The deformation behavior of this test may be explained by the atyic.al test conduct (reactor scram at the onset of ballooning in contrast to The ocher tests) resulting in a cladding temperature decrease during the-nEitt part of the deformation and a delayed pressure release through a pin-hole opening in the cladding.
ruel Condition
- . .7 All tests with previously irradiated rods exhibited a fuel condition di f nent from the expeiments with unirradiated rods. As in commercial . I - I:.. I .
fuel Iods the pellets-in the test rods were cracked during operation power and the fragmentawere held in place by the cladding. When, duriug the transient test, the cladding moved away from the fuel due to radiAl defsr=.tion, the pellet fragments filled the thus generated additional spae: This led to a complete loss of pellet shape in the ballooned seac-tix: rid, for rods with larger deformation, to a significant reduction of tho p;>-. et stack height.
There was essentially no additional cracking of the fuel during the trat.arnt tests. This fact was clearly demonstrated by particle size analy.e'z which resulted in similar size distributions for rods exposed to a transient and rods not exposed to such conditions after irradiation.
Fig. I ptesentS the results from the sieve Analyses of the GI fuel s aples (bur-top 35,000 HWd/tu). The data of the reference rods not being exposed to e tranlsient lie in the band' of all other samples. The mean fragment' size - measured to be about 0.3 cm.
Trom two tests (E3 and B4) it was learned that the fuel movement (pVIt. fragmentation) it the rod occurs in the moment of large deformation and ;.;re of the cladding. Fig. 8 presents the cladding temperature and internal pressure histories during Test E4 and the special thermocouple instrumantation. Three thermocouples (T 137 through T 139) in these two tests were mounted at the upper end of the fuel stack in order to monitor the _.olapse of the pellet column. At the time of burst the three lower (J_)
2-136
JLL-12-2004 12:05 Linda Hall Library Si6 926 8785 P.837 therm6couples T 131 through T 133 behave as usual: A moderate tempeatures reductiontindicates thee increase of Sap xJidth and a flow of reiativIy cold "V:
) . plenum gas past the T locations.
The severe temperature drops of the TCs T 137 through T 139 however, are a clear indication for the fuel movement Ieading-to a,reduhrion of ihe fuel btack of about 50 a8mcould be evaluated from the 'pottest neatton radiographs.
- ESULTS OF DESTRUCTIVE PTE Analysis of Deformation of Zircaloy-4 Cladding To describe quantitatively the complex nature of Zircaloy-4 de rma-tion the method of the localization parameter l is used, where 0 ' W:" 1.
Small values indicate uniform and high values lotalized deformation..-
The radial-strain localization parameter W introduced by H.L. Chung and T.F, Kassner 5 as calculated for series A, B, and F shows the same W Iex correlation (Fig. 9) as the pertinent Afl data5 for directlj heated chadsig tubes. However, the We values of the in-pile tests are 5 to 15 2 higher than the ANL data. .
A comparison of the axial-strain localization parameter Wz between the in-pile tests of series A, B, and F and out-of-pile tests6 with direct-heating of the cladding is shown in Fig. 10. Wz is plotted versus burst time. For tOCA test conditions, i.e. short times to burst, in-pile as well as out-of-pile tests result 'in Wl above 0.5. This means axially localized ballooning. - - -
Microstructural Evaluation of the Cladding Temperature The Zircaloy-4 microstructure appearance was interpreted in order to estimate the local maximum cladding temperatures reached during the. w-t
-pile LOCA transients and to quantify azimuthal temperature differences.
For the rods of test series A and B (fresh rods) and the pre-irradiated rods of the test series F evaluated to date, the assessment of the maximum cladding temperature showed good agreement with the TC measurement uising type B thermocouples and about 30 to 40 K lower temperatures than type A TCs. Thus the correction value added for the type A TCs seems too high.'
Azimuthal temperature variations between 0 and 80 K were found.
Cladding Tube Oxidation The microstructure of the cladding outer surface showed the oxide scale to be dense, adherent, and axially cracked due to clad deformation.
Only large deformation led to partial oxide spalling. The continued oxidation after the burst of the cladding formed crack-free, smooth oxide sublayers.
In Fig. 11 the local oxide thickness of the samples from the A, B series and F series (pre-irradiated) is plotted versus the pertinent maxi-mum cladding temperature. The ZrO 2 layer thickness varied between 2 and Z-1 37
At- l SUL 12-2004 12:05 Linda Hall Library -816 926 8785 P.O6 8 sm for both, fresh and pre-irradiated rods. This extent of oxidatin at,
.: -:5 . vi - the outer cladding surface is comparable to out-of-pile- results. ' .,
-- s:- -'.:
At the inner surface the oxide Uyer thickness decreasets ith i; .:
creasing distance from the burst opening. The oxidation of the Innetitube surfice isimainly pauSed by1steem access Via the burst opedig. Nooiide ;
- twae foik;d mre than '100mii bpart" from the burst ibeation. The oxide'iit the inner tlid surface apptired smobthand without the strain-induced crack pattern typical for the outer layers. Close to the burst opening the (thick-ness of the inner oxide layer is slightly smaller than the thickness.of the outer layer, for fresh rodsl.However, the pre-irradiated rods of thejfSfries F exhibited significantly thicker internal. oxide layers compared to-the 0: external layer. -
Chemical Behavior of the Fuel and 'the Fission Products In the in-pile test rods no pronounced chemical interaction between-UO0 fuel and the Zry cliadding (internal claddint oxidation by the fuel) occurred during the LOCA transient. Also no influence of fission products, e.g. iodine, on the deformation and rupture behavior has so far been ob-served. Possibly the iodine was not present in the fuel rod in the proper chemical state since neither preconditioning nor substantial preirradiation of the fuel immediately before the transient were performed. But, the imore likely reason could be that in particular iodine is not present at the inner cladding surface at a sufficiently high concentration. The many'incip-.
ient cracks detected at the inner cladding surface hold for this assumption.
A similar crack formation was observed-in laboratory tests when the iodine concentration was too low. 9 The critical iodine concentration depends strongly on temperature. As laboratory tests demonstrated a significant in-fluence of iodine on the burst strain occurs at temperatures below 800 0 C only. 9 But for temperatures above 700 OC the critical iodine concentration required for a low-ductility failure of the Zry tubing due to iodine kCC (stress-corrosion cracking) seems too high to be-reached in the in-piIe test rods, even under the assumption of acomplete iodine release from the high burnup fuel. Since alltested high burnup fuel rods (35,000 MWd/tu) btst :
at temperatures above 700C (730 - 900 0 C) the probablity 8r a low-, . l ductility failure of the cladding due to SCC is rather low. I Fission Gas Release and Fuel Swelling The fission gas release from UO9 and the fuel swelling were determined at the test rods after the pre-irradtation, i.e. without LOCA transient testing, and at the pre-irradiated rods being exposed to the transients.
During the steady-state preirradiation of the fuel rods the fission ga's release was always below 10:t. During the LOCA transient the additional fission gas release was smaller than 6 %. The release is primarily caused by microcrack formation without the fuel. The various fission gas frac-tions, i.e. the released gas, the gas in pores, and the gas in the matrix, in fuel samples of the test series F after different treatment are given in Fig. 12. The fuel density increased during irradiation up to about 3 X burnup. This is due-to a volume-averaged -swelling rate of about I % per %
burnup and an irradiation-induced densification to about 2 Z residual po-rosity. There was no noticeable Swelling during the LOCA-tests.
C()
2-138
'1
JUL-12-2e04 12:05 Linda Hall Library 816 926 8785 P.,b9 MAJOR RESULTS ANID CONCLUSION Frot the test rod data evaluated to date the following results-are summarized:
- All pressu'rized rods ruptured dirlnk the heagup phase. .
- All ballooned rods exhibit circumferential strains over their etih e heated length. theaefo6rtation profile was influenced by the'xl power profile and locally by -the thermocouples. -'
AllI specimens burst at; the location of maximum strain and this tiaximum dr-fo rmation-is- located 'at or near the-peak power position. - X..
burst data, {e. burst temperature, burst pressure, and burst strain eThe are similar to results from various out-of-pile tests..No influence of burtup on the burst data was detected.
The tests with pre-irradiated rods resulted in fragmented fuel pellets in the rod sections with major deformation. The pellet fragments relocated outward and downward filling the space in the fuel rod created by the redial clad deformation..
Fuel pellet fragmentation does not seem to have affected the cladding deformation process.
- The evaluated data of the radial-strain-and axial-strain localization parameter are comparable for fresh andypreirradiated fuel rods.
- Microstructural evaluation of the maximum cladding temperature indicated azimuthal temperature differences between 0 and 80 K.
- StArn oxidation of the cladding outer surface is comparable to ou{t-of-
-pile results, Enhanced local oxidation was observed in some cases with pre-irradiated fuel rods.
- The internal oxide layers observed near the burst position were caused by the steam access via the rupture opening and exhibit a similar-thick-rnes compared to the outer surface. Preirradiated tubes show thicker ox.i0de layers on the inside surface compared to unirradiated specimens.
- K) influence of fission products on the burst strain of the tubing has sa far been detected.
- ne- fission gas release during the LOCA transient was detected to.-be xmnaller than 6 Z. It is primarily caused by microcrack formation in the fuel. The swelling of the fuel was negligible.
With respect to the test objectives it may be concluded tentatively that the results available at this time do not indicate a systematic in-flu.mncr of the nuclear environment on fuel behavior under the conditions of reise tests.
2-139
JUL ;n12 20C4 L-:6 . Winda 0HaU Library. 816 92 8785:
Q P.
- 4 CHAPMAN, "Mu'lirod Burst Test Program Progress", Report
.aniary - March 1978, NUREG I CR -- 0225, ORNL / NUREG iguSt 1978
/ TM-217, f't-
- 2.t. F.£fRMCHER,;
r "Verhalten der Brennelementcebbiui Ktiblmittelveruust-rra Altl und lech3elwirkung mit dei Krp-no-tlUhlung",: j 1(6'691 Sept 19- .-
I.:
i ay ruel Claidin NEiITZELi-'~ +/-dZ,1Jrlt ~hNis
`.>
-in alOCa Inteation ;with the Emergenty
--'re Cooling, t4anS Am. $JSZ So:.., 31:336-339 (1979) 4 A. MuskR et al., "Evaluating Strength and Ductility of Irradiati 'a
- taloy", Quarterly Progress Report January - March, 1978, r-tG f CR-0085, BMI-2000, June 1978
- ,. '.. tHUNG and T.P. KASSNER, -"Deforimation Characteristics of Zirciloy
- -addrag in Vacuum under Steam and Transient Heating conditions1 , -.
' ' SI1Lary Ripbrt ANL-77-31, Sulk 1978.
-. ROSE:, C.A. MANN, and E.D. HINDLE, "Axial: distribution of de drma titx in the cladding of pressurized water reactor fuel rods in a Ibes
-"y-coolant accident", Nuct. Technot. 46, 2 (220-227) Dec.
1979
- 7. `LISTIKOW, G. SCHANZ, and H.v. BERG, ' Kinetik und Morphologiec slua isothermen Dampf-Oxidation von-Zircaloy-4 bei 700
- 1300 00", -
A.-. U5P7, March 1978 Q
9 8. .t,, LITlTIKOW, G,.SCHANZ, and H.v. BERG, "Untersuchungen zur tempetitur-tve-.n51ienten Dampfoxidation von Zircaloy-4-Uillmaterial unter hypo-tx r-ti4htjshen DWR-Kuhlmittelverlust-Stcrfallbedingungen",K6K 2810, kPil 1979
- 9. FPJFNLANN, J. SPINO, " Influence of Simulated Fission Products
- -t%ctility and-Time-to-Failure of Zircaloy-4 Tubes in on.<.: .
LWR Than-
-:rs", K6K 3054, 1980 10, -3. KARB et al., "KfK In-pile Tests on LWR Fuel Rod Behavior During .
-w -heatup Phase of a LOCA", K6K 302S, Oct. 1980 2-140
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2-141
I-LL-12-2004- 12:06 Linda Hall Library .E1 926 8'75 P.12
. . - Fw ta F3,FS f1, t..:
Circumferential P2 F P .
to Strain4g, 10 Circumifetentia.I strrains aid Normalized ax al power. protilesa pFl
- l _ , .- / U. - VF t ~: : r through F5; :,,,.,>
i /e F1 0 5 S1T t ,0:
- oo 300 - 200 ioo lmni 500 Distance from Elottom of Fuel Stack
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/A2.1 A2.)S81.1.St.2,5138S,.IB7,B3A5 3Z2 Civcumferential strains and \:-
axial power profilesI A and B tests (unirradiated 1.7 00 1-b0 o - 0 200 .300 400 mmmi500
- _-- Dishtnce from Bottom of Fuel Stack
% I 2I C I~ .- .: .d g 4Y1.---
1 Fig. 6 l\Posttest neutron radiograph and deformation profile E5 C0/Rv,jtvre -
L) T131 T132 T3 T12s T13. 36 1 Distanea from Bottom of Fuet Stack 2-142 Ir
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- r~ueiinceg rod G1.5 ft tra~ijit I
p . 4 I , I0 ~ itt
. I.: I I .. I I ofGo0ls Fuel particle size distriiu- ion,~
. i . . .
sieve atialyses".0fseri~es U
50I~
4or 30fI
'r 5-0 Particle size k LFig . 8 TemrperaCure and internal pressure Histories during test E4 9 lb'irl I
Jo' 111 so Q~SC 5 4 it is Twit I-.
a-Pft sts by ANL te~I Fig.,
LII l tdyI?
hsP, cladeiug)
Comparison of FR2 in-pile tests with ANL out-of-pile data witfh respect to the radial-strain
'i localization parameter.
ftQ: -- ~-.- - t 04 - a05 I 05 r~lyimu.m Circumferential True Strain' Co iie, 2-1 43 w;'-
JL-12~t~3~4Linda 816 926 8785 Hall Library P.:14 o.
Dump.
f.Cb~arii.'ot o6f FRZ- I'Ai pile t4 With out"-of pi.le da a wih.~pc 44 paameter'.
Tim* o*SuS 4Mlu' SymbolI F So~w leist I20O000MWditI k F S Rwwa of tht data oblgatd from~
0O AO a 950Ott0 0 C
- 4 Ij7 Maximum clad, temp. llocdl values estimoted from Microstr'ucturoY)
F3)( Annrealing
. 4~.
Fig. 11 S1I Steamn oxidation of the.
cladding (outer surfac')
.tf ' 7:
7 2 R&I"tSed gi Fission gas fractions Q£ O$in vpow in fuel samnples of the A series F (2OO0O MbWd/itU a S3r?n mm
)
2-144 TOTAL P.14