Published 1999
| Version v1
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The shield efficiency for the Shelter fuel-containing materials
Description
The reasonable detailed quantitative estimations of the radiation shielding materials, which will most probably be used in the fabrication of the Shelter fuel contained materials shelf, are performed. The Monte Carlo calculations was carry out by the software Micro Shield 4.00 serial 4.00-00283, which make it possible correctly to account for the radiation shielding geometry, the radiation sources geometry, the radiation sources spectrums and the processes of the gamma-rays multi scattering in ''thick'' shielding. Results presented in the tables and graphics. 3 refs., 19 tab., 38 figs
Availability note (English)
Available from INIS in electronic formFiles
32020572.pdf
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Additional details
Additional titles
- Original title (Russian)
- Эффективност' защиты от излучений топливосодержащих материалов обьекта 'Укрытиеь
Publishing Information
- Imprint Pagination
- 64 p.
- Report number
- MNTTs-Ukrytie--99-6
INIS
- Country of Publication
- Ukraine
- Country of Input or Organization
- Ukraine
- INIS RN
- 32020572
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CHERNOBYLSK-4 REACTOR; EVALUATION; LAVA; MONTE CARLO METHOD; NUCLEAR FUELS; REACTOR ACCIDENTS; REACTOR SAFETY; SAFETY ANALYSIS; SHELTERS; SIMULATION
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; GRAPHITE MODERATED REACTORS; IGNEOUS ROCKS; LWGR TYPE REACTORS; MATERIALS; POWER REACTORS; REACTOR MATERIALS; REACTORS; ROCKS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS