Published October 2012 | Version v1
Miscellaneous

Verification of the procedure to generate the homogenized multi group cross section for VHTR fuel block using McCARD

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

McCARD/CAPP code system for designing Very High Temperature Gas Cooled Reactor (VHTR) core has been developed in the Korea Atomic Energy Research Institute (KAERI). McCARD/CAPP code system carry out a neutronic analysis for VHTR through the generation of a homogenized cross section using McCARD (Monte Carlo Code for Advanced Reactor Design) and the few group diffusion analysis using CAPP (Core Analyzer for Pebble and Prismatic type VHTRs). The previous procedure using HELIOS has the limits of not considering the axial heterogeneity and the double heterogeneity which is the unique characteristics of VHTR fuel block. However, McCARD based on Monte Carlo Method has the function of handling the double heterogeneity. In addition, Seoul National University (SNU) recently implemented the module to generate the multi-group cross section table-sets into McCARD. Thus, in this study, we carried out the verification calculations of the procedure to generate the homogenized multi-group cross section for VHTR fuel block using McCARD and investigated the feasibility of the McCARD/CAPP code system

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2012 autumn meeting of the KNS
Dates
24-26 Oct 2012
Place
Kyoungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44062588
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CROSS SECTIONS; FEASIBILITY STUDIES; M CODES; REACTOR CORES; VERIFICATION; VHTR REACTOR
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS

Optional Information

Notes
4 refs, 3 figs, 1 tab