Criticality safety evaluation for TWR-S fuel assembly transportation using TK-S16 containers
Creators
- 1. The VINCA Institute of Nuclear Sciences, Belgrade (Yugoslavia)
Description
Criticality safety issues, concerning transportation of fresh high-enriched uranium fuel elements (TWR-S fuel assembly type) with Russian containers TK-S16, are objects of study in this paper. Three-dimensional (3D) models of fuel element and container were made, based upon their well-known geometry and material structure. The way to pack fuel elements in a bundle inside of the container is proposed. Calculations were done by MCNP4B2 computer code. This Monte Carlo criticality code determined the effective multiplication factor from the cross-section data and specific geometry data. This evaluation demonstrated the subcriticality of a single package and an array of packages during normal conditions of transport and various hypothetical accident conditions. (author)
Availability note (English)
Also available from Institute of Nuclear Sciences VINCAFiles
41124641.pdf
Files
(329.1 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:eaa80c5f7616da4a164063ac111cb03a
|
329.1 kB | Preview Download |
Additional details
Publishing Information
- Publisher
- Institute of Nuclear Sciences VINCA, Belgrade, Yugoslavia
- Imprint Place
- Belgrade (Yugoslavia)
- ISBN
- 86-7306-062-1
- Imprint Pagination
- 4 p.
- Report number
- INIS-RS--1370
Conference
- Title
- 4. International Yugoslav Nuclear Society Conference
- Original Conference Title
- Konferencija Jugoslovenskog nuklearnog drustva (YUNSC-2002)
- Acronym
- YUNSC-2002
- Dates
- 30 Sep - 4 Oct 2002
- Place
- Belgrade (Yugoslavia)
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Serbia
- INIS RN
- 41124641
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CALCULATIONS; CONTAINERS; CRITICALITY; CROSS SECTIONS; EXPERIMENTAL DATA; FUEL ASSEMBLIES; FUEL ELEMENT CLUSTERS; HIGHLY ENRICHED URANIUM; M CODES; MONTE CARLO METHOD; MULTIPLICATION FACTORS; PACKAGING; R-A REACTOR; SAFETY ANALYSIS; THREE-DIMENSIONAL CALCULATIONS; TRANSPORT REGULATIONS
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; COMPUTER CODES; DATA; DIMENSIONLESS NUMBERS; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; LAWS; MATERIALS; METALS; NUMERICAL DATA; REACTORS; REGULATIONS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM
Optional Information
- Notes
- 8 refs., 3 figs., 2 TABS., This record replaces 36000099; This record replaces 39077396