A method for 3D simulation of internal gas effects on thermal-mechanical behaviors in nuclear fuel elements

NUCLEAR ENGINEERING

A method for 3D simulation of internal gas effects on thermal-mechanical behaviors in nuclear fuel elements

JIANG Yijie，

CUI Yi，

HUO Yongzhong，

DING Shurong

Nuclear Science and Techniques

Vol.22, No.3

pp.185-192

Published in print 20 Jun 2011

DOI：10.13538/j.1001-8042/nst.22.185-192

37300

A new method for three-dimensional simulation of the interaction between the gas and the solid around is developed. The effects of the gas on the thermal-mechanical behaviors within the surrounded solid are performed by replacing the internal gas with an equivalent solid in the modeling, which can make it convenient to simulate the thermal-mechanical coupling effects in the solid research objects with gases in them. The applied thermal expansion coefficient, Young's modulus and Poisson's ratio of the equivalent solid material are derived. A series of tests have been conducted; and the proposed equivalent solid method to simulate the gas effects is validated.

Gas conductivityGas pressureEquivalent solid methodNumerical simulationNuclear fuel elementsThermal-mechanical behaviorsFission gas release

References

[1]

Marchal N, Campos C,Garnier C. Comp Mater Sci, 2009, 45: 821-826.

[2]

Soba A, Denis A. J Nucl Mater, 2008, 374: 32-43.

[3]

Denis A, Soba A. Nucl Eng Des, 2003, 223: 211-229.

[4]

Mathews J. Advances in Nuclear Science and Technology. New York (USA): Academic Press, 1972.

[5]

Struzik C, Moyne M, Piron J P. ANS International Topical Meeting on Light Water Reactor Fuel Performance, Portland, 1997, 126-132.

[6]

Feltus M A, Lee K. Ann Nucl Energy, 1996, 23: 553-565.

[7]

Michel B, Sercombe J, Thouvenin G. Nucl Eng Des, 2008, 238: 1612-1628

[8]

Newman C, Hansen G, Gaston D. J Nucl Mater, 2009, 392: 6-15.

[9]

Miller G K, Burkes D E, Wachs D M. Mater Des, 2010, 31: 3234-3243.

[10]

Lu M W, Luo X F. Basis of elasticity theory (2nd Edition). Beijing (China), Tsinghua University's Press, 2001.

[11]

Wang Q M, Yan X Q, Ding S R, et al. J Nucl Mater, 2010, 400: 157-174.

[12]

Ding S R, Wang Q M, Huo Y Z. J Nucl Mater, 2010, 397: 80-91.

[13]

MATPRO-09, A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior, USNRC TREE NUREG-1005, 1976.

[14]

Lucuta P G, Matzke H S, Hastings I J. J Nucl Mater, 1996, 232: 166-180.

[15]

Fisher E S, Renken C J. Phys Rev, 1964, 135: 482-494.