Published April 2017 | Version v1
Book

Effect of sub-pin feedback in coupled MCNP6/CTF

  • 1. Department of Nuclear Engineering, North Carolina State University, 2500 Stinson Drive, 3140 Burlington Engineering Labs, Raleigh, NC 27695 (United States)

Description

There has been a trend towards coupled Monte Carlo (MC) neutronic and Thermal Hydraulic (TH) subchannel codes to be used to create reference solutions. Typically the pin average feedback assumption is used to decrease the computational requirements. The pin average feedback assumption is where the fuel region in the neutronics code is modeled as a single region. In this paper the number of sub-pin fuel regions are varied in a coupled MC neutronics and TH subchannel code to get a measure of their effect on a coupled solution as well as to verify the pin average feedback assumption. The pin average feedback assumption was found to give errors of over 100 pcm and over 15% in the fuel centerline temperature. For most of the cases, decreasing the number of sub-pin regions in MCNP6 gave conservative results, while decreasing the number of sub-pin regions in CTF gave non conservative results, with an exception of the eigenvalue. The effect on the eigenvalue was reversed. (authors)

Additional details

Publishing Information

Publisher
Korean Nuclear Society - KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Pagination
7 p.

Conference

Title
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017
Acronym
M and C 2017
Dates
16-20 Apr 2017
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
France
INIS RN
53074317
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; EIGENVALUES; ERRORS; FEEDBACK; FUEL PINS; MONTE CARLO METHOD; NUCLEAR FUELS; THERMAL HYDRAULICS
Descriptors DEC
CALCULATION METHODS; ENERGY SOURCES; FLUID MECHANICS; FUEL ELEMENTS; FUELS; HYDRAULICS; MATERIALS; MECHANICS; REACTOR COMPONENTS; REACTOR MATERIALS; SIMULATION

Optional Information

Notes
9 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses