Transient hydride fuel behavior in LWRs

被引：12

作者：

Terrani, Kurt A. ^{[1
]}

Seifried, Jeffrey E. ^{[1
]}

Olander, Donald R. ^{[1
]}

机构：

[1] Univ Calif Berkeley, Dept Nucl Engn, Berkeley, CA 94720 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2009年 / 392卷 / 02期

关键词：

ZIRCONIUM HYDRIDE; ALLOYS;

D O I：

10.1016/j.jnucmat.2009.03.010

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The transient response of a uranium zirconium hydride (U(0.31)ZrH(1.6)) fuel element to conditions typical of a light water reactor reactivity insertion accident has been studied. Hydrogen diffusion within the fuel is treated as a function of the time-dependent temperature profile. Temperature and hydrogen concentration dependence of thermal properties of the fuel is also considered. The set of coupled equations describing the transient conduction of heat and diffusion of hydrogen are solved with a Crank-Nicolson discretization scheme for heat diffusion and an explicit Euler scheme for hydrogen diffusion. Published by Elsevier B.V.

引用

页码：192 / 199

页数：8

共 17 条

[1]

[Anonymous], 2004, CHEM THERMODYNAMICS

[2] A practical method for numerical evaluation of solutions of partial differential equations of the heat-conduction type [J].

Crank, J ;

Nicolson, P .

ADVANCES IN COMPUTATIONAL MATHEMATICS, 1996, 6 (3-4) :207-226

[3]

FINK J, 2000, ZIRCALOY THERMAL CON

[4]

GANDA F, 2005, P GLOB 05 TSUK JAP O

[5]

Huang J, 2000, J NUCL SCI TECHNOL, V37, P887, DOI [10.1080/18811248.2000.9714969, 10.3327/jnst.37.887]

[6] Liquid-metal-bonded gap for light water reactor fuel rods [J].

Kim, YS ;

Olander, DR ;

Yagnik, SK .

NUCLEAR TECHNOLOGY, 1999, 128 (03) :300-312

[7]

MAJER G, 1994, J PHYS CONDENS MATT, P2935

[8] Hydride fuel behavior in LWRs [J].

Olander, DR ;

Ng, M .

JOURNAL OF NUCLEAR MATERIALS, 2005, 346 (2-3) :98-108

[9]

RUST H, 1979, POWER PLANT ENG, P393

[10] THE U-ZRHX ALLOY - ITS PROPERTIES AND USE IN TRIGA FUEL [J].

SIMNAD, MT .

NUCLEAR ENGINEERING AND DESIGN, 1981, 64 (03) :403-422

← 1 2 →