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Title: MCNP Super Lattice Method for VHTR ORIGEN2.2 Nuclear Library Improvement Based on ENDF/B-VII

The advanced Very High Temperature gas-cooled Reactor (VHTR) achieves simplification of safety through reliance on innovative features and passive systems. One of the VHTRs innovative features is the reliance on ceramic-coated fuel particles to retain the fission products under extreme accident conditions. The effect of the random fuel kernel distribution in the fuel prismatic block creates a double-heterogeneous lattice, which needs to be addressed through the use of the newly developed prismatic super Kernel-by-Kernel Fuel (KbKF) lattice model method. Based on the new ENDF/B-VII nuclear cross section evaluated data, the developed KbKF super lattice model was then used with MCNP to calculate the material isotopes neutron reaction rates, such as, (n,?); (n,n’); (n,2n’); (n,f); (n,p); (n,?). Then, the MCNP-calculated results are rearranged to generate a set of new libraries “VHTRXS.lib,” for the ORIGEN2.2 isotopes depletion and build-up analysis code. The libraries contain one group cross section data for the structural light elements, actinides, and fission products that can be applied in the VHTR related fuel burnup and material transmutation analysis codes. The efficiency and ease of use of the MCNP method to generate and update the ORIGEN2.2 one-group spectrum weighed cross section library for VHTR was demonstrated.
Authors:
;
Publication Date:
OSTI Identifier:
993169
Report Number(s):
INL/CON-10-17838
TRN: US1007976
DOE Contract Number:
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: SNA + MC2010, Joint International Conference on Supercomputing In Nuclear Applications + Monte Carlo,Tokyo, Japan,10/17/2010,10/22/2010
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
DOE - NE
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ACCIDENTS; ACTINIDES; BURNUP; CROSS SECTIONS; DISTRIBUTION; EFFICIENCY; FISSION PRODUCTS; FUEL PARTICLES; GAS COOLED REACTORS; NEUTRON REACTIONS; SAFETY; TRANSMUTATION ENDF-BVII; MCNP; MCWO; ORIGEN; super lattice; VHTR