3D thermo-chemical-mechanical simulation of power ramps with ALCYONE fuel code

被引:39
作者
Baurens, B. [1 ]
Sercombe, J. [1 ]
Riglet-Martial, C. [1 ]
Desgranges, L. [1 ]
Trotignon, L. [2 ]
Maugis, P. [3 ]
机构
[1] CEA, DEN, DEC SESC, F-13108 St Paul Les Durance, France
[2] CEA, DEN, DTN STRI, F-13108 St Paul Les Durance, France
[3] Aix Marseille Univ, IM2NP, UMR CNRS 7334, F-13397 Marseille, France
关键词
PELLET-CLADDING INTERACTION; HIGH-TEMPERATURE EQUILIBRIA; STRESS-CORROSION CRACKING; NUCLEAR-FUEL; UO2; FUEL; THERMODYNAMIC REPRESENTATION; OXYGEN DIFFUSION; COMPUTER-PROGRAM; BEHAVIOR; IODINE;
D O I
10.1016/j.jnucmat.2014.06.021
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This paper presents the coupling of the fuel performance code ALCYONE with the thermochemical code ANGE and its application to Iodine-Stress Corrosion Cracking (I-SCC). The coupling is illustrated by a 3D simulation of a power ramp. The release of chemically active gases (CsI(g), Te-x(1<x<7)(g), TeI2(g), I-(g), I-2(g)...) is studied. The calculated radial distributions of iodine, cesium, tellurium and inert fission gas in the pellet fragment before and after the power ramp are successfully compared to Secondary Ion Mass Spectrometry (SIMS) measurements. Based on the 3D simulation, the definition of a stress corrosion initiation criterion is discussed. The combination of the hoop stress and of the quantity of reactive iodine (I-(g), I-2(g) and TeI2(g) only) released by the pellet is used to show that the necessary conditions for Pellet Cladding Interaction-Stress Corrosion Cracking (PCI-SCC) initiation, based on out-of-pile I-SCC laboratory tests criteria, are met during the simulated power transient. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:578 / 594
页数:17
相关论文
共 77 条
[1]  
Anghel C., 2010, TOPFUEL ORL US
[2]   Advanced doped UO2 pellets in LWR applications [J].
Arborelius, Jakob ;
Backman, Karin ;
Hallstadius, Lars ;
Limbaeck, Magnus ;
Nilsson, Jimmy ;
Rebensdorff, Bjoern ;
Zhou, Gang ;
Kitano, Koji ;
Loefstroem, Reidar ;
Roennberg, Gunnar .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2006, 43 (09) :967-976
[3]  
Backman K., 2010, IAEATECDOC1654
[4]   FactSage thermochemical software and databases [J].
Bale, C ;
Chartrand, P ;
Degterov, SA ;
Eriksson, G ;
Hack, K ;
Ben Mahfoud, R ;
Melançon, J ;
Pelton, AD ;
Petersen, S .
CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY, 2002, 26 (02) :189-228
[5]   FactSage thermochemical software and databases - recent developments [J].
Bale, C. W. ;
Belisle, E. ;
Chartrand, P. ;
Decterov, S. A. ;
Eriksson, G. ;
Hack, K. ;
Jung, I. -H. ;
Kang, Y. -B. ;
Melancon, J. ;
Pelton, A. D. ;
Robelin, C. ;
Petersen, S. .
CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY, 2009, 33 (02) :295-311
[6]   THE CHEMICAL CONSTITUTION OF THE FUEL CLAD GAP IN OXIDE FUEL-PINS FOR NUCLEAR-REACTORS [J].
BALL, RGJ ;
BURNS, WG ;
HENSHAW, J ;
MIGNANELLI, MA ;
POTTER, PE .
JOURNAL OF NUCLEAR MATERIALS, 1989, 167 :191-204
[7]  
Besmann TM, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 1: BASIC ASPECTS OF RADIATION EFFECTS IN SOLIDS/BASIC ASPECTS OF MULTI-SCALE MODELING, P455
[8]  
CEA, 1981, INTERNAL REPORT
[9]   VOLATILE FISSION-PRODUCT BUBBLE BEHAVIOR IN URANIUM-DIOXIDE [J].
CHKUASELI, VF ;
MATZKE, H .
JOURNAL OF NUCLEAR MATERIALS, 1995, 223 (01) :61-66
[10]  
Cordfunke E.H.P., 1990, THERMOCHEMICAL DATA