Published October 2012 | Version v1
Miscellaneous Metadata-only

A study on Monte Carlo depletion options for a hybrid reactor design

Creators

  • 1. Kyung Hee Univ., Seoul (Korea, Republic of)

Description

Reliable methods for an isotopic depletion simulation are one of the crucial steps in a conceptual design of a fusion fission hybrid reactor. MCNPX and MONTEBURNS are most commonly used and available tools. BURN card is a new module in MCNPX2.6 which integrates the CINDER90 code in MCNPX for depletion calculations. MONTEBURNS couple the ORIGIN with MCNP 4C for depletion calculations. The choice of time step in BURN card is analyzed by choosing different lengths of burn time steps and their calculation results were compared with MONTEBURNS for Waste Transmutation Hybrid Reactor (WT Hyb) design

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
44062607
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
C CODES; COMPUTER CALCULATIONS; DESIGN; HYBRID REACTORS; M CODES; MONTE CARLO METHOD; O CODES
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES

Optional Information

Notes
5 refs, 7 figs