Comparison of Serpent and HELIOS-2 as applied for the PWR few-group cross section generation
Creators
- 1. Helmholz-Zentrum Dresden-Rossendorf, POB 51 01 19, Dresden, 01314 (Germany)
- 2. VTT Technical Research Centre of Finland, POB 1000, FI-02044 VTT (Finland)
- 3. Studsvik Scandpower, Inc., 504 Shoup Ave., Idaho Falls, ID (United States)
Description
This paper discusses recent modifications to the Serpent Monte Carlo code methodology and related to the calculation of few-group diffusion coefficients and reflector discontinuity factors The new methods were assessed in the following manner. First, few-group homogenized cross sections calculated by Serpent for a reference PWR core were compared with those generated 1 commercial deterministic lattice transport code HELIOS-2. Second, Serpent and HELIOS-2 fe group cross section sets were later employed by nodal diffusion code DYN3D for the modeling the reference PWR core. Finally, the nodal diffusion results obtained using the both cross section sets were compared with the full core Serpent Monte Carlo solution. The test calculations show that Serpent can calculate the parameters required for nodal analyses similar to conventional deterministic lattice codes. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-700-2
- Imprint Title
- Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
- Imprint Pagination
- 3016 p.
- Journal Page Range
- p. 693-703
Conference
- Title
- 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
- Acronym
- M and C 2013
- Dates
- 5-9 May 2013
- Place
- Sun Valley, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 45033706
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CROSS SECTIONS; DIFFUSION; H CODES; MATHEMATICAL SOLUTIONS; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; PWR TYPE REACTORS; SIMULATION
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs.