Published 1990
| Version v1
Miscellaneous
BN-600 fuel elements and fuel assemblies operating experience
Description
Consideration is given to the data on fuel burnup of standard fuel assemblies of the BN-600 reactor first core charge and that for modified core; data on operation ability of fuel assemblies of the first charge type are given. Data on main results of primary post-irradiation examination of fuel assemblies and fuel elements and maximal values of fuel burnup, achieved in particular fuel assemblies of BN-600 reactor are presented. 4 figs.; 1 tab
Additional details
Additional titles
- Original title (Russian)
- Опыт эксплуатации твэлов и TVS реактора BN-600
Publishing Information
- Imprint Title
- Radiation materials science. V. 4
- Imprint Pagination
- 227 p.
- Journal Page Range
- p. 105-112.
- Report number
- INIS-SU--309/A
Conference
- Title
- International conference on radiation materials science.
- Dates
- 22-25 May 1990.
- Place
- Alushta (Ukraine).
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 23036500
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BELOYARSK-3 REACTOR; BURNUP; ELONGATION; FUEL ASSEMBLIES; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; POWER DENSITY; REACTOR OPERATION; SHROUDS
- Descriptors DEC
- BREEDER REACTORS; COOLING SYSTEMS; DEFORMATION; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR MATERIALS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Notes
- Imprint:Radiatsionnoe materialovedenie. Tom 4.