Published June 1994
| Version v1
Journal article
Characteristics of radiation from fuel fragments in graphite moderator after put out of action uranium-graphite reactor
Creators
Description
Calculational-experimental methodology for effective determination of radionuclides characteristics, mass and places of fuel dispersed particles and fragments localization in uranium-graphite reactor cladding, fuel assemblies subjected to accidents and decommissioned ones. 4 refs
Additional details
Additional titles
- Original title (Russian)
- Радиационные характеристики остатков топлива в кладках снятых с эксплуатации уран-графитовых реакторов
Publishing Information
- Journal Title
- Atomnaya Ehnergiya
- Journal Volume
- 78
- Journal Issue
- 6
- Journal Page Range
- p. 396-400.
- ISSN
- 0004-7163
- CODEN
- AENGAB
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 27051696
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DECOMMISSIONING; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; GRAPHITE MODERATED REACTORS; MASS; NEUTRON PROBES; SENSITIVITY
- Descriptors DEC
- PROBES; REACTOR COMPONENTS; REACTORS