ML042260037
| ML042260037 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/31/2004 |
| 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-OLA, 50-414-OLA, ASLBP 03-815-03-OLA, Catawba-Applicant-5, RAS 8251 | |
| Download: ML042260037 (14) | |
Text
eDA-S Firv 0,6I DOQCIETED 0
August 9, 2004 (11:45AM)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF Exhibit 5 NUCLEAR REGULATORY WOvmijSS,;iY Docket No.65-413 /I11u -MOA_ Official Exh. No. 5 In the matter of _ _ _ _ _ _ _ _ _ _ _ _
Staff - IDENTIFIED 7/'41o4 Ar*)ica'~: ________- RECEIVED In crverncx ____ REJECTED Cc,,t'g Ott _
Contractor DATE Other - Witness v7eA p a7 6 C / c9 '
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Exhibit 5 Guillard, V., et. al., "Use of CATHARE2 Reactor Calculations to Anticipate Research Needs," SEGFSM Topical Meeting on LOCA Issues, Argonne, May 2004
SEOFSM Topical Meeting on LOCA Issues Argonnc National Laboraory, May 25.26,20.
USE OF CATHARE2 REACTOR CALCULATIONS TO ANTICIPATE RESEARCH NEEDS V.GuUlard', C. Grandjean, S.Bourdon, P. Chatelard Institut de Radioprotection et de Sflret6 Nucl6aire IRSN/DPAM: BP3 - 131 IS St Paul-Lez-Durance, France valia.guillard~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 defornations 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
. A C G S U P
"" ' USE OF CATHARE2 REACTOR CALCULATIONS
. .:.TO ANTICIPATE BP3-111 StPa' -eWDrac RESEARCHCeex- NEEDS rac V. GUILLARD, C. GRANDJEAN, S. BOURDON., P. CHATELARD Institute for Radiological Protection and Nuclear Safety (IRSN)
MaJor Accident Prevention Division / Fuel In Accident Situations Department BP3 - 131 15 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 vaLia.aullardEIrsn.fr ANL, May 25-27, 2004
.O General Background
. ie 4A, 74. '
- 7..' L condition .
0 CATHARE2 N-`C-rga
> French thermalhydraulics system code with CATHACOMB fuel module A Objectives t R_
> Identify future research needs for new generation of fuels
> Improve knowledge, models and calculation methodologies 0 Approach 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)
,oundary conditions for further more precise
.lculabons and analysis under LOCA conditions vaglalguIlard(irsn.fr ANL, May 25-27, 2004
"LOCA Issues Related to Ballooning, Relocation, Flaw I Main Findings from a Review of Past Expeime dm ,
Temperatures (°C)
-Fuel
. -Clad TYPICAL LB LOCA TRANSIENT EASY NOT SO EASY Oxidation kinetics Fuel fragmentation and secondary hydriding (debris size, 1200 granulometry, porosity)
Clad coolability 800 .around ballooned regions with fuel relocation Clad Fuel rods thermal behavior ballooning *'... . Flow restriction during ref looding conditions Mechanical interactionsA~
between neighbo°° Burst criterion rods or structures Fuel relocation Post-quench Ailetnin(instant of occurrence, residual ductility of balloon J N balloons filling ratio) S TS, 50 100 150 Time (s)
- Fuel U Clad U Bundle valla.gulllard~irsn fr ANL, May 25-27, 2004
0 Calculation of several transients including Large & intermediate breaks LOCA 0 Use of standard CATHARE2 versions (V1.3L, V2.5)
- O Basic uncertainties on CATHARE2 models taken into account
> Consistent with PIRT Implications 03 Zry-4 cladding without hydrogen uptake effect on mechanical properties 0 Hypothesis linked with the use of irradiated fuel at high bum-up
> Modification of thermal properties 9 conductivity and thermal capacity laws from SCANAIR code
> Deletion of protective effect of initial oxide layer on transient oxidation e 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 ...
Example: ofihe impact of irradiated fuel relocation E4 ot Btk ditions on a PWR900Mwe valla.gufflard(Rlrsn.fr ANL, May 25-27, 2004
0 Main hypothesis i
Balloon filling rate by relocalized fragments
- Relocation mesh on.
= burst location mesh I Upper bound value filled by fuel debris 80 from upper meshes 70*
- Filling ratio of the balloon U 0 A 0 0 x A
= function (balloon size) 60 A
- Balloon size derived from e 50 ft..
CATHACOMB calculation of 0 mean elongation % 40- o PBFILOC-gammascanning
- PBFILOC-micrographies Basic calculation value = 61.5 %
- Modification of the power factor _ 30 A FR2 and the fuel mass in the ._ -Upper bound relocation mesh 20 ° EdF calculation x IRSN reference calculation
- Considering relocated fuel as 10 + IRSN sensitivity calculation a porous medium (Imura-Yagi model for the conductivity calculation) nI 20 30 40 50 60 70 80
- Flow blockages: Impact on T/H Ballooning (%)
and fuel cooling not taken Into account TO, F7TI ;ij EI F S M~I valla.auillard~jirsn~r ANL, May 25-27, 2004
O High sensitivity of the relocation impact on PCT
> Burst at 24 s on stress criterion deduced from EDGAR experiments (Fat rupture = 57.5%)
1.
' 1. ,
ULB LOCA - Irradiated U02
- ffar rodt ckdricf rencPJ flacif burjr rneirh 120SD.0. . ..
Fu-lelreloation impact depends on:
1000.0t . ,burst:i iX ;which determines the energy 00tr tn ln dthe busnt mesh L.700which1d.ternines relocated fuel mass 400.0 0
< LD BURST FUEL RELOCATION 4 ZDD.C - Whout mekratbn
- Wth robkbn Piling rntlDo: 61.3%) ' 110C to 150C on PCT 100.0 -- Wlh mIakabn Cfllng ratlo: 700%)
(depend ig.on balloon filling ratio: 61.5 to 70%)
0.0 0.0 200. 4060 0 80.0 10M0 120. 1400 150.0 160.0 20 .0 valiaaMuillard0irsn.fr ANL, May 25-27, 2004
O Fuel relocation impact on ECR and residual f3-layer
> Burst at 24 s on stress criterion deduced from EDGAR experiments (£ at rupture = 57.5%)
LB LOCA - Irradiated U02 LB LOCA - Irradiated U02 flar rxl oxhkoIon rise isbfrwrninesh Nor rod beizi-&iyer rhickniers ut burrr,nmes 20.0 500.0 -i--
- .. 550.0 .
15.0 500.0 15.0 450.0 14.0 400.0 12.0 350.0 -
t X 10.0 8 2fD.D .
250.0 5.0 200.0 -
6.0 150.0 4 .0 - Wthout reocaxon
- Wth reolon pfilhig ratb G1) 100.0 -
-- ftm btatIon flIIh;;rutb:70.0%)
2.0 50.0- -
0.0 - - .- - - - -
0.ID 20.0 40.0 6D.0 50.0 100.0 120.0 140.0 150.0 150.0 200.0 0.0 20.0 .0 650.0 0.0 100.0 120Q0 TIme l[] Time []
- :%to7% ? on ECR -: 50gm to 67.m on residual P3-layer thickness
'.pn.n balloon filling ratio: 61.5 to 70%) -(djn,'dingon.balloon filling ratio: 61.5 to 70%)
valia auillard(Mlrsn.fr ANL, May 25-27, 2004
0 Fuel relocation impact on PCT
. Burst at 18 s on stress criterion deduced from EDGAR experiments (£ at rupture = 58.7 %)
ER T.aVA - T. dintwl MON Hot rod c&dtWhg temperautreatbuvi'tme Er I
20 i :IEnhnce .of fuel relocation impact 9-
+160 °C on PCT lime ([s Eli1vaIIa.guJIIardO.Irsn.fr ANL, May 25-27, 2004
O Fuel relocation impact on ECR and residual 13-layer
> Burst at 18 s on stress criterion deduced from EDGAR experiments (£at rupture = 58.7 %)
LB LOCA - [rradiated MOX LB LOCA - Irradiated MOX Hot PoJ oJtiazion 0 rec cit burst snesh Hor rod bewj-lcerfe a t Micknas es burst Mesh rldit 7A
- Whhoti reloctign - Wthout rebcation With relocatin - With reobcation TimneIs] -m Is;Tll1]
l.~ge uncertainty me)
.herimpact ro take effect Ndto reduce EC nd residual P-layer O bntca properties d rtalntles IRSN veaulardO@-Irsn.fr ANL, May 25-27, 2004
l O Use of CATHARE2 code for high bum-up fuel analysis under LOCA conditions
> Example of Large Break transient
> Emphasis on fuel relocation phenomena impact
> Main results: PCT and ECR increased 0 High uncertainty on global code response due to identified lack of knowledge
> Instant of fuel movement HALDEN4?-
imposed as burst time inthe simulation
- depends on clad ballooning/deformation and burst criterion
> Balloon size - HALDENS?.
- which is also linked with ballooning/deformation model
> Filling ratio 4- FR2, PBF, HALDEN?
> Relocated fuel properties
- fragments size, granulometry, porosity, conductivity, . ANL, HALDEN?
> Bundle effects -- Need of integral test
- Axial extension of balloon
- Flow blockages
- Clad coolability around ballooned regions with fuel relocation vaa.9uiIard@irsn.fr ANL, May 25-27, 2004
3OPerspectives
> Modification of clad mechanical properties to take into account hydrogen uptake effect
> Study to be complemented by calculations using CATHARE / FRETA
- 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 Ett!(C taijean; . G; &G. Hache) + Analytical studies
> - >itinficatiat of knowldge improvements
- dated r"oc behavior under LOCA conditions v' D oi on of fuel and bundle models gaan new margins valia.auillard~Irsn.fr ANL, May 25-27, 2004 I