Analysis of tungsten gray rods critical experiments using PARAGON with ultra-fine energy mesh methodology
Creators
- 1. Nuclear Fuel, Westinghouse Electric Company LLC, Cranberry Township, PA (United States)
- 2. Toshiba Corp., Power and Industrial Systems R and D Center, Kawasaki, Kanagawa (Japan)
Description
New critical experiments using gray control rods with tungsten were recently performed at the Toshiba NCA critical facility. This paper presents analyses of these experiments using both stochastic and deterministic codes. We used the continuous energy Monte Carlo code MCNP and the Westinghouse lattice physics code PARAGON. The basic nuclear data source for the cross-sections is ENDF/B-VII.1. First, the tungsten data is validated against Monte Carlo calculations. The ultra-fine energy mesh with 6064 group cross-sections library was used in PARAGON to extend the validation of the methodology to the cold temperature conditions. Comparisons focused on reactivity and the measured fission rate distributions. The results show that the ENDF/B-VII.1 data adequately reproduces the measured tungsten gray rod reactivity worth. Also, the energy mesh and the methodology used in PARAGON are seen to be adequate in predicting the reactivity and fission rate distributions for these challenging and highly heterogeneous experiments. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 13 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042625
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTROL ELEMENTS; CONTROL ROD WORTHS; CRITICALITY; FISSION; HETEROGENEOUS REACTOR CORES; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; NUCLEAR REACTION KINETICS; REACTOR KINETICS; REACTOR LATTICES; TOSHIBA REACTOR
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; KINETICS; NUCLEAR REACTIONS; POOL TYPE REACTORS; REACTION KINETICS; REACTOR COMPONENTS; REACTOR CORES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; TRAINING REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1101855.pdf; 8 refs., 5 figs., 2 tabs.