Effect of sub-pin feedback in coupled MCNP6/CTF
Creators
- 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