Published 2020 | Version v1
Miscellaneous

An investigation on the control rod homogenization method for next-generation fast reactor cores

  • 1. Japan Atomic Energy Agency, Oarai Research and Development Institute, Oarai, Ibaraki (Japan)

Description

Japanese next-generation fast reactor core design adopts the reaction rate ratio preservation (RRRP) method for control rod homogenization with a super-cell model in which a control rod is surrounded by fuel assemblies. The former study showed the RRRP method with the conventional super-cell model could estimate the control rod worth (CRW) of a 750-MWe large fast reactor core within the analytical uncertainty of 1.5 %. The analytical uncertainty of CRW affects the estimation of radial power distribution (RPD) especially for large fast reactor cores with the control rod inserted. In order to eliminate the radially-dependent analytical uncertainty of CRW and RPD, this study refined the super-cell model in the RRRP method with the help of Monte-Carlo simulations. As a result, the refinement significantly decreased the radially-dependent analytical uncertainty; the analytical uncertainty of CRW turned to be negligible and that of RPD became below 0.35 %. (author)

Part of:
Proceedings of SNA + MC2020: Joint international conference on supercomputing in nuclear applications + Monte Carlo 2020

Additional details

Publishing Information

Imprint Title
Proceedings of SNA + MC2020: Joint international conference on supercomputing in nuclear applications + Monte Carlo 2020
Imprint Pagination
[433 p.]
Journal Page Range
p. 92-96

Conference

Title
Joint international conference on supercomputing in nuclear applications + Monte Carlo 2020
Acronym
SNA+MC 2020
Dates
18-22 May 2020
Place
Chiba (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
53079594
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONTROL ELEMENTS; CONTROL ROD WORTHS; CROSS SECTIONS; DATA COVARIANCES; FAST REACTORS; FUEL ASSEMBLIES; G CODES; HOMOGENIZATION METHODS; MONTE CARLO METHOD; NEUTRON PHYSICS; POWER DISTRIBUTION; REACTOR CORES
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; EPITHERMAL REACTORS; PHYSICS; REACTOR COMPONENTS; REACTORS

Optional Information

Notes
Available as PDF format, Paper ID: SNA02-3.pdf; 4 refs., 5 figs., 1 tab. Imprint:Available as a PDF file, issued by collecting articles only, along with conferring neither in a place nor online, failing to hold on 18-22 May 2020.