Published 2012 | Version v1
Miscellaneous

Monte Carlo fuel temperature reactivity coefficient calculations by adjoint-weighted correlated sampling method

  • 1. Seoul National Univ., Seoul (Korea, Republic of)

Description

It is very time-consuming to estimate the fuel temperature reactivity coefficient (FTC) with high accuracy based on the subtraction of two reactivity values calculated at different fuel temperatures by a Monte Carlo (MC) neutron transport analysis code. We present a new MC FTC estimation method based on the perturbation techniques. The effectiveness of the new method is examined through the continuous energy MC neutronics calculations for the CANDU lattice problem. It is shown that the proposed method can predict the reactivity change due to the fuel temperature variation efficiently. From its numerical results, the reaction-wise contributions to the FTC are investigated with different resonance scattering models – the free-monatomic-gas models with constant cross section and resonance cross section. (author)

Part of:
Building on our past... building for the future. 33rd Annual Canadian Nuclear Society conference and 36th CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-094
Imprint Title
Building on our past... building for the future. 33rd Annual Canadian Nuclear Society conference and 36th CNS/CNA student conference
Imprint Pagination
189 Megabytes
Journal Page Range
[11 p.]

Conference

Title
33. Annual Canadian Nuclear Society conference; 36. CNS/CNA student conference
Dates
10-13 Jun 2012
Place
Saskatoon, Saskatchewan (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47018025
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; MONTE CARLO METHOD; NEUTRON TRANSPORT; REACTIVITY COEFFICIENTS; REACTOR LATTICE PARAMETERS
Descriptors DEC
CALCULATION METHODS; HEAVY WATER MODERATED REACTORS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS

Optional Information

Notes
14 refs., 3 tabs., 1 fig.