Published March 2000
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Assessment of radiation safety of the spent nuclear fuel dry storage cask
- 1. Lithuanian Nuclear Power Inspectorate (VATESI), Vilnius (Lithuania)
- 2. Institute of Physics, Vilnius (Lithuania)
Description
Assessment of radiation safety of the spent nuclear fuel dry storage cask CASTOR RBMK-1500 has been performed by means of the computer modelling (computer codes SAS2H and DORT) and by measurements of the dose rate. The estimated values do not exceed the limited ones. The measured values are several times smaller than the calculated ones due to the conservative approach. (author)
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Additional details
Publishing Information
- Imprint Title
- International conference on the safety of radioactive waste management. Contributed papers
- Imprint Pagination
- 447 p.
- Journal Page Range
- p. 188-191
- Report number
- IAEA-CN--78
Conference
- Title
- International conference on the safety of radioactive waste management
- Dates
- 13-17 Mar 2000
- Place
- Cordoba (Spain)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31016230
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMERICIUM ISOTOPES; CURIUM ISOTOPES; DOSE RATES; ISOTOPE RATIO; PLUTONIUM ISOTOPES; RADIATION PROTECTION; RADIOACTIVITY; SPENT FUEL CASKS; SPENT FUEL STORAGE; URANIUM ISOTOPES
- Descriptors DEC
- CASKS; CONTAINERS; ISOTOPES; STORAGE
Optional Information
- Notes
- 3 refs, 4 figs, 3 tabs
- Secondary number(s)
- IAEA-CN--78/46