Published 1995
| Version v1
Miscellaneous
Open
Criticality safety of fresh and irradiated fuel of the 6.5 MW heavy water research reactor
Creators
- 1. Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia)
Description
Criticality safety problems, arising in away-from-reactor handling of the 6.5 MW heavy water research reactor fuel, are considered. The present status of fresh and spent fuel storage is described. To calculate criticality parameters of different non-reactor configurations of fresh and irradiated fuel, the well known WIMS code is combined with a few group three dimensional diffusion theory code TRITON. Typical results are presented and discussed. (author)
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCAFiles
38068187.pdf
Files
(907.2 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:a3bf9ef6b86373ebd6091844f02b2671
|
907.2 kB | Preview Download |
Additional details
Publishing Information
- Publisher
- Romanian Nuclear Energy Association 'AREN', University 'Politehnica' of Bucharest
- Imprint Place
- Bucharest (Romania)
- Imprint Pagination
- 5 p.
- Report number
- INIS-RS--0994
Conference
- Title
- SIEN '95 - International symposium on nuclear energy
- Original Conference Title
- Proceeedings of SIEN '95 - International symposium on nuclear energy
- Dates
- 20-21 Oct 1995
- Place
- Bucharest (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Serbia
- INIS RN
- 38068187
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COLLISION PROBABILITY METHOD; CRITICALITY; NEUTRON DIFFUSION EQUATION; R-A REACTOR; SAFETY ANALYSIS; SPENT FUEL STORAGE; T CODES; THREE-DIMENSIONAL CALCULATIONS; W CODES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STORAGE; TANK TYPE REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 2 figs., 3 tabs., 4 refs. This record replaces record 27015769