ML042260050
| ML042260050 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/25/2004 |
| From: | Bourdon S, Chatelard P, Grandjean C, Guillard V Govt of France, Institute for Radiological Protection & Nuclear Safety (IRSN) |
| To: | Office of Nuclear Reactor Regulation |
| Byrdsong A T | |
| References | |
| 50-413-0LA, 50-414-OLA, ASLBP 03-815-03-OLA, Catawba-Intervenor-F, RAS 8292 | |
| Download: ML042260050 (13) | |
Text
-OA e ~c~27 DOCKETED USNRC August 9, 2004 (11:45AM)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF EXHIBIT F NUCLEAR REGULATORY COMMISSION Docket No. 5pLaI3/P4 -0Lk OffaIl Exh.No. 3° _
In the matter of Puke Grfawiu Staff IDENTIED 7/i i Applicant _ RECEIVED _ ___ ___
Intervenor V REJECTED_
Conf'g Of V' Contractor __ -. DATE Other_ Witne__ _
Reporter F4&, i.A d
/Iz- ec ,' o se-6CY-O-0
SEGFSM Topical Meeting on LOCA Issues Argonne National Laboratory, May 25-26, 2004.
USE OF CATHARE2 REACTOR CALCULATIONS TO ANTICIPATE RESEARCH NEEDS V. Guillard', C. Grandjean, S. Bourdon, P. Chatelard Institut de Radioprotection et de Sfret6 Nuclaire IRSN/DPAM: BP3 - 13115 St Paul-Lez-Durance, France valia.guillardO~irsn.fr ABSTRACT To analyze the consequences of the introduction, in Nuclear Power Plants, of advanced fuels at high bum-up, decided by most of the utilities in western countries in order to reduce the fuel cycle costs, IRSN has initiated a research program focused on the study of such PWR fuel behavior in LOCA conditions.
A first step of this program, comprising analytical and experimental parts, has been to identify the main physical phenomena, linked with thermomechanical behavior of irradiated rods in bundle geometry, to be taken into account in reactor safety analysis: cladding deformation and flow section restriction in bundle geometry, mechanical interaction between neighbor rods or structures, axial extension of balloons ; cladding oxidation and secondary hydriding ; fuel fragmentation and relocation, balloons filling rate and FP release ; fuel rods thermal behavior in bundle geometry during reflooding conditions, rewetting of the claddings around ballooned regions with fuel relocation mechanical resistance of irradiated claddings in post-quench conditions.
This paper summarizes an analysis of sensitivity calculations performed with CATHARE2 "Best-Estimate" code, used in France in the frame of realistic methodology to evaluate safety margins.
The objective of these calculations is to point out, among parameters affecting last-mentioned phenomena, those for which taking into account basic uncertainties lead to important uncertainty on global code response (Peak Cladding Temperature, oxidation rate ...). That is the case of fuel relocation phenomena, whose impact is highly dependent on parameters such as, in the example of LB LOCA transient, cladding radial and axial deformations in bundle geometry, burst criteria, balloon filling rate, thermalhydraulics around balloons. A lack of knowledge on theses parameters for irradiated U02 and particularly MOX fuel may lead to reduce safety margins.
This study may provide some elements to identify future research needs to complement present experimental data base, reduce uncertainties and develop more realistic calculation models, which may better fit the thermomechanical behavior of advanced irradiated fuels.
' Corresponding author
?SEGS TPCLETNONLA ISSUE AroneNtonlLboaoyMy25-27,2004 MEET 4"'..'
USE OF CATHARE2 REACTOR CALCULATIONS TO ANTICIPATE RESEARCH NEEDS V. GUILLARD, C. GRANDJEAN, S. BOURDON, P. CHATELARD Institute for Radiological Protection and Nuclear Safety (IRSN)
Major Accident Prevention Division I Fuel in Accident Situations Department BP3 - 13115 St-Paul-Lez-Durance Cedex - France Content of the presentation
> Introduction
> Main physical phenomena to be modeled
> Main hypotheses of the calculations
> Main results of the LB LOCA calculations
> Conclusion and perspectives fia0ITTHMP May 2527, 2004 ANLOn
^ vala~qullar@.irn~frANL, May 25-27, 2004
,. U,;,
. .' 111 tQ General Background
~ oemanagemnjotJ.-1 StudyV'f-PWR eatr stuie Jqs Kfue Thterals th~m omechnicI bh'avior withCATHAE M CATHARE2
> French thermalhydraulics system code with CATHACOMB fuel module 0 Objectives
- ..j.. ... L..f ._ __ __ I_ __ r_ _ _ ._ _ 1i, suture researcn needs Tor new generation of tuels
,s..
J iuerXITy
> Improve knowledge, models and calculation methodologies
- OApproach used to reach this objective
> Identify physical phenomena involved in thermo-mechanical behavior of advanced irradiated rods in bundle geometry (State Of the Art by C. Grandjean & G. Hache)
> Take them into account in the modeling
> Quantify basic uncertainties (CIRCE tool and sensitivity calculations)
> Evaluate global uncertainty on CATHARE2 code response (SUNSET tool)
E usdiboundary conditionsfor further more precise lu ations and analysis: under LOCA conditions
- V auillard(cirsn fr yal.a ANL, May 25-27, 2004 I.
MAI PHY;SIC-AL PHENOM ENA TOEBE MODELED;`
~; liked-ith' the use ofavanted fesa ihbri-p Reference C. GRANDJEAN &GIACHE "LOCA Issues Related to Ballooning, Relocation, Flow Blkagte and Coblabiity.:
Main Findings from a Review of Past p tlgrn Temperatures ('C) ifit- Fuel i '-Clad TYPICAL LB LOCA TRANSIENT EASY NOTSO EASY Fuel f ragmentation Ox datin kiec and....
-seonar hydrid' 4ng<
(debris size,10 granulometry, porosity)
Clad coolability 800 around ballooned regions Clad ballooning
.,Fi with fuel relocation jel rods thermal behavior iring ref looding conditions Mechanical
: interactions Ar0 Flowrestrion dL between neighboT"'
rods or structures Post-quench Axial extension (instant of -occurrence, *.V residual ductility of balloon balloons fillin ti) 50 100 150 Time (s)
Fuel Clad Bundle Haua rrES Meet. oi LOcA issues Vcatiaqau a dis~rANL, May 25-27, 2004 o.-
I, .CAThAE2CLCLAINS Man ypothess Xl Calculation of several transients including Large & Intermediate breaks LOCA i l Use of standard CATHARE2 versions (V1.3L, V2.5) o Basic uncertainties on CATHARE2 models taken into account
> Consistent with PIRT implications El Zry-4 cladding without hydrogen uptake effect on mechanical properties Q Hypothesis linked with the use of irradiated fuel at high burn-up
> Modification of thermal properties
. conductivity and thermal capacity laws from SCANAIR code
- > Deletion of protective effect of initial oxide layer on transient oxidation
- outcome from experimental ANL and TAGCIR program analysis on irradiated Zry
> Introduction of Baker-Just correlation to calculate oxidation rate O Initial state of irradiated rods given by METEOR code
> Gap width and pressure, radial and axial fuel power profile, external cladding oxidation profile, cladding thickness ...
.kI2- Exam)le: I ofthe ct of irradiated fuel relocation ditcndiions on a PWR9OOMwe U.e Of calcuiations han.e.s GFSM va~i~pui~ar~ir~~frANL, May 25-27, 2004 to
CATHR2LL ~AcLT ON S "
Siml b 4afeigcatitn!O phenomena U Main hypothesis Balloon filling rate Rel o mh by relocalized fragments
- Relocation mesh g m90
= burst location mesh filled by fuel debris 80 U from upper meshes
- Filling ratio of the balloon
= function (balloon size) 60 A A
Balloon size derived from 50 CATHACOMB calculation of o mean elongation 0 PBFILOC-gammascanning 040 U PBFILOC-micrographies Basic calculation value = 61.5 %
- Modification of the power factor E 30 A F12 and the fuel mass in the X -Upper bound relocation mesh 20 0 EdF calculation K IRSN reference calculation
- Considering relocated fuel as 10 + IRSN sensitivity calculation a porous medium (Imura-Yagi model for the conductivity calculation) 0 20 30 40 50 60 70 80
- Flow blockages: impact on T/H Ballooning (%)
and fuel cooling not taken into account t SEGES pMt, Asues
-uillardO<irsnfr ANL, May 25-27, 2004 r .
CATHARE LB A CALCLTION LI High sensitivity of the relocation impact on PCT
> Burst at 24 s on stress criterion deduced from EDGAR experiments
(£ at rupture = 57.5%)
LB LOCA - Irradiated U02 Hot rodcklddihg feinpEreturC orburtjpnecsh 1200.0 1100.0 Yl rel~o~ctation impact depends on:
1000.0 bUrstttime, which determines the energy 900.0 ~ re-di6tributionJin the burst mesh 800.0 o ifilling ratio, 5'
700.0 which d~terrines relocated fuel mass 600.0 a.
E 500.0
,O-.
400.0 300.0 200.0 100.0 3:O to 150 C on PCT
- z , dbaoonfilling. ratio 61.5 to 70%)
flme Ls]
WaiaaIlardc~irsn. r ANL, May 25-27, 2004 I.
I, ;4 t, XO!'S'"S gs P,4v'29' itX n M;'^.a ,1E :< X_
Fuel relocation impact on ECR and residual P-layer
> Burst at 24 s on stress criterion deduced from EDGAR experiments
{Ss, ;,
(£ at rupture = 57.5%)
,' At'." t ... . s _
<7.,/", LB LOCA - Irradiated U02 LB LOCA - Irradiated U02 Hfot rod oxildatilon rate oabursrron esh 1,34 220.0 Hor rodbetia-&^er tickhuer at burrimei 600.0 1 8.0 i !,,, ,;
!' t:. S.;: ,,:
.. i Vi St.; 550.0
':"'::t:-''^"'"'.'S 1 5.0 500.0
!.:,,:.:.;: X :,
.. : , . .... 1 4.0 f".' " 112.0 U,
., 2 P
E
- r 10.0 0a UJ.
5.0 6.0 -
- 4.0 2.
0.0-o.o . I . .p . I 50.0 50.0 100.0 1200 rime [as Time [s]
+ t 7% on ECR 5o <o.toon residual P-layer thickness (depending on balloon filling ratio: 61.5 to 70%) (dpenin i j<. ba~loon filling ratio: 61.5 to 70%)
R aivaha.qui1ardcrsnr: : ANL, May 25-27, 2004
'<CAHARE2 BQA$CLTQSlt EC Fuel relocation impact on PCT
> Burst at 18 s on stress criterion deduced from EDGAR experiments (s at rupture = 58.7 %)
3t,-i, .,,
3. '3 LB LOCA - Irradiated MOX
-; .K '. Hot rodaedding rempenietu etit butesh n
.. -:E:!
- 'p
, I I . v I . T I ., I ., . I 3 3e,+
\:. ';(2 '
- . .. n4
- e9Enh'ance of fuel relocation impact k ~ii Ms3.-
i~. W 34^
- M4 ..
- ,4, l43 CLAD BURST
~> FUEL RELOCATION
- Withtt rebcatan
- With rebcation l
i
. I. I
°o I. 1 . , . I . . . . . .
+I6O0 on PCT
,.C Time [a]
vat~~auitar~irs~frANL, .May 25-27, 2004
- s ~~~
7 ~
CATHRE2 esiivt LBLOCA to fXe tyes - . MOLATIONS CALCU (2/2)* $S X 0 ':^
El Fuel relocation impact on ECR and residual P-layer
> Burst at 18 s on stress criterion deduced from EDGAR experiments (Eat rupture 58.7 %D)
LB LOCA - Irradiated MOX LB LOCA - Irradiated MOX Hot rod oxiJatioh n-te atburrtrnEs/ Hot rod beta-layer residualthickness at burst inesh
- 4. .,., , I . ,.,.,.,.,.I . .
t
- wCZ FE Time [a]
i,-,"BUT;' Time Is]
uncertainty iL ia;rg Hige riimpact ion: hydrgen uptake effect -' .Need to reduce tonEM-AfidFresidual ,B-layer nd mecanical properties crtain ties depending on clad alloy u s e ~ o, d E F M T p M e, a L c i ~ e 6 6e yalta .guiI ard~irsin .fr ANL, May 25-2 7, 2004 I.
bnt 4 .I -~ r '-.
iL.
. 1,,.Use of CATHARE2 code for high burn-up fuel analysis under LOCA conditions U
> Example of Large Break transient
> Emphasis on fuel relocation phenomena impact El,
> Main results: PCT and ECR increased High uncertainty on global code response due to identified lack of knowledge
> Instant of fuel movement ^- HALD ?
- imposed as burst time in the simulation
- depends on clad ballooning/deformation and burst criterion
> Balloon size HALDE:'i s..~-,s,
- which is also linked with ballooning/deformation model
> Filling ratio - FR2, PBF, HALDEN?
> Relocated fuel properties
- fragments size, granulometry, porosity, conductivity, - ANL, HALING
> Bundle effects - Need of inte tes Axial extension of balloon Flow blockages Clad coolability around ballooned regions with fuel relocation e CUeo ir'Rt J n neec S LAi' U' ~ J varia.guill rd~isa f ANL, -May 25-27, 2004
i1 'KG~~ONPLU IONANDPRPCIE
- 'A.
t U Perspectives S Modification of clad mechanical properties to take into account hydrogen Gi ; N
. uptake effect
> Study to be complemented by calculations using CATHARE / FRETA E rods 3D thermo-mechanics
. rod-to-rod interactions models
- cooling and reflooding models for overall bundle
> Use of NEPTUNE 3D local module for flow blockage cooling calculations
> IRSN plans to develop a new code for fuel LOCA calculations
- Stn. lache) + Analytical studies
~ lentfiatin f'kowedg> mprovement on iradited'rod ehavor uderLOCA cond~itions
.' on, S
> evlp ewgneration offel a'nd blundle moddels Reduce ucin new, margins
-j-p --- _ '
Mrraa'bb ag
,~ se~fCAHAF~2 eacor a~c~at~nso~n~ct at esarc neds~ SEG FSMUW Top.. Meet on J'LQ "s~e
~ I~J Vaia.~it~rd(~irs~frANL, May 25-27, 2004