Published March 2000 | Version v1
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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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International conference on the safety of radioactive waste management. Contributed papers

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