Development of a transient criticality evaluation method
Creators
- 1. Department of Earth Sciences and Engineering, Imperial College of Science, Technology and Medicine, London (United Kingdom)
- 2. The George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA (United States)
Description
In developing a transient criticality evaluation method we model, in full spatial/temporal detail, the neutron fluxes and consequent power and the evolving material properties - their flows, energies, phase changes etc. These methods are embodied in the generic method FETCH code which is based as far as possible on basic principles and is capable of use in exploring safety-related situations somewhat beyond the range of experiment. FETCH is a general geometry code capable of addressing a range of criticality issues in fissile materials. The code embodies both transient radiation transport and transient fluid dynamics. Work on powders, granular materials, porous media and solutions is reviewed. The capability for modelling transient criticality for chemical plant, waste matrices and advanced reactors is also outlined. (author)
Files
37022085.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the international symposium NUCEF 2005
- Imprint Pagination
- 378 p.
- Journal Page Range
- p. 85-90
- Report number
- JAERI-Conf--2005-007
Conference
- Title
- International symposium NUCEF 2005
- Dates
- 9-10 Feb 2005
- Place
- Tokai, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37022085
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTINUITY EQUATIONS; CRITICALITY; DYNAMICS; F CODES; FINITE ELEMENT METHOD; FISSILE MATERIALS; GRANULAR MATERIALS; MOMENTUM TRANSFER; MULTIPHASE FLOW; NEUTRON FLUX; NEUTRON TRANSPORT; PEBBLE BED REACTORS; POROUS MATERIALS; POWDERS; SOLUTIONS; TRANSIENTS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; DISPERSIONS; EQUATIONS; FISSIONABLE MATERIALS; FLUID FLOW; GAS COOLED REACTORS; HOMOGENEOUS MIXTURES; HOMOGENEOUS REACTORS; MATERIALS; MATHEMATICAL SOLUTIONS; MECHANICS; MIXTURES; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS
Optional Information
- Notes
- 9 refs., 4 figs.