Evaluation of the DRAGON code for VHTR design analysis.

Taiwo, T. A. ; Kim, T. K. ; Argonne National Laboratory. Nuclear Engineering Division.

Argonne National Laboratory

关键词: Iaea;    Fuel Elements;    Simulation;    22 General Studies Of Nuclear Reactors;    Design;   

DOI  :  10.2172/929210
RP-ID  :  ANL-GENIV-060
RP-ID  :  DE-AC02-06CH11357
RP-ID  :  929210

美国|其它

来源: UNT Digital Library

【 摘 要 】

This letter report summarizes three activities that were undertaken in FY 2005 to gather information on the DRAGON code and to perform limited evaluations of the code performance when used in the analysis of the Very High Temperature Reactor (VHTR) designs. These activities include: (1) Use of the code to model the fuel elements of the helium-cooled and liquid-salt-cooled VHTR designs. Results were compared to those from another deterministic lattice code (WIMS8) and a Monte Carlo code (MCNP). (2) The preliminary assessment of the nuclear data library currently used with the code and libraries that have been provided by the IAEA WIMS-D4 Library Update Project (WLUP). (3) DRAGON workshop held to discuss the code capabilities for modeling the VHTR.