Radial distributions of power and isotopic concentrations in candidate accident tolerant fuel U3Si2 and UO2/U3Si2 fuel pins with FeCrAl cladding

被引：34

作者：

Chen, Shengli ^{[1
,2
]}

Yuan, Cenxi ^{[1
]}

Guo, Daxi ^{[3
]}

机构：

[1] Sun Yat Sen Univ, Sino French Inst Nucl Engn & Technol, Zhuhai 519082, Guangdong, Peoples R China

[2] CEA, Cadarache, DEN DER SPRC LEPh, F-13108 St Paul Les Durance, France

[3] China Nucl Power Technol Res Inst, Shenzhen 518027, Guangdong, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2019年 / 124卷

基金：

中国国家自然科学基金;

关键词：

Radial distribution; Power; ATF; FeCrAl; U3Si2; UO2; BURNUP; PERFORMANCE;

D O I：

10.1016/j.anucene.2018.10.025

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Monte Carlo simulations show similarity on radial distributions of power and isotopic concentrations at any effective full power depletion time among five kinds of fuel-cladding combinations with the same cycle length, including the normal UO2-zircaloy combination, the candidate Accident Tolerant Fuel (ATF) UO2/U3Si2-FeCrAl combination, and three kinds of candidate ATF U3Si2-FeCrAl combinations. An analytical formula f(x,s) including the fuel exposure (s) and the relative radial (x) is proposed to describe the radial properties for all five kinds of fuel-cladding combinations. f(x,s) has the form of the second order polynomial term of s with the exponential type of coefficients depending on x. It is shown that the suggested function f(x,s) gives a nice description on the simulation data with rather small deviations and can immediately provide radial distribution of power, burnup, and isotopic concentrations of U-235, U-238, U Pu-239, and Pu-241 at any fuel exposure and relative radius. It is useful to discuss the fuel temperature through the present analytical formula. The realistic radial power distribution gives flatter radial temperature distribution compared with the uniform power distribution. Because of the different thermal conductivities of fuels and claddings and the different thicknesses of claddings, the present discussed five kinds of fuel-cladding combinations have different radial temperature distributions, although their radial power distributions are quite similar. The present work provides an analytical formula to describe the radial properties of the ATF which is expected to be helpful for further neutronic and multi-physics coupling studies. (C) 2018 Elsevier Ltd. All rights reserved.

引用

页码：460 / 471

页数：12

共 37 条

[1]

Bragg-Sitton Shannon M., 2015, UPD ACC TOL FUEL IAE

[2] Screening of advanced cladding materials and UN-U3Si5 fuel [J].

Brown, Nicholas R. ;

Todosow, Michael ;

Cuadra, Arantxa .

JOURNAL OF NUCLEAR MATERIALS, 2015, 462 :26-42

[3] ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology [J].

Chadwick, M. B. ;

Oblozinsky, P. ;

Herman, M. ;

Greene, N. M. ;

McKnight, R. D. ;

Smith, D. L. ;

Young, P. G. ;

MacFarlane, R. E. ;

Hale, G. M. ;

Frankle, S. C. ;

Kahler, A. C. ;

Kawano, T. ;

Little, R. C. ;

Madland, D. G. ;

Moller, P. ;

Mosteller, R. D. ;

Page, P. R. ;

Talou, P. ;

Trellue, H. ;

White, M. C. ;

Wilson, W. B. ;

Arcilla, R. ;

Dunford, C. L. ;

Mughabghab, S. F. ;

Pritychenko, B. ;

Rochman, D. ;

Sonzogni, A. A. ;

Lubitz, C. R. ;

Trumbull, T. H. ;

Weinman, J. P. ;

Brown, D. A. ;

Cullen, D. E. ;

Heinrichs, D. P. ;

McNabb, D. P. ;

Derrien, H. ;

Dunn, M. E. ;

Larson, N. M. ;

Leal, L. C. ;

Carlson, A. D. ;

Block, R. C. ;

Briggs, J. B. ;

Cheng, E. T. ;

Huria, H. C. ;

Zerkle, M. L. ;

Kozier, K. S. ;

Courcelle, A. ;

Pronyaev, V. ;

van der Marck, S. C. .

NUCLEAR DATA SHEETS, 2006, 107 (12) :2931-3059

[4]

Chen S., 2017, P REACT PHYS AS 2017

[5] Transmutation Study of Minor Actinides in Mixed Oxide Fueled Typical Pressurized Water Reactor Assembly [J].

Chen, Shengli ;

Yuan, Cenxi .

JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2018, 4 (04)

[6] Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl [J].

Chen, Shengli ;

Yuan, Cenxi .

SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2017, 2017

[7]

Core G.M, 2016, Fuel Cycle Research and Development Accident Tolerant Fuels Series 1 (ATF-1) Irradiation Testing FY 2016 Status Report

[8]

Driscoll M.J., 1990, The linear reactivity model for nuclear fuel management

[9] REACTIONS OF URANIUM MONONITRIDE THORIUM MONOCARBIDE AND URANIUM MONOCARBIDE WITH NITRIC ACID AND OTHER AQUEOUS REAGENTS [J].

FERRIS, LM .

JOURNAL OF INORGANIC & NUCLEAR CHEMISTRY, 1968, 30 (10) :2661-&

[10] Thermophysical properties of uranium dioxide [J].

Fink, JK .

JOURNAL OF NUCLEAR MATERIALS, 2000, 279 (01) :1-18

← 1 2 3 4 →