Published November 1986
| Version v1
Journal article
IVV-2M fuel assembly
Creators
Description
A design of an improved fuel assembly (FA) of the IVV-2 water cooled and moderated research reactor is described. The results of neutron-physical, thermal hydraulic and post-reactor studies of fuel assemblies are presented. The FA consists of five hollow three-layer hexagonal fuel elements with cermet fuel (uranium dioxide dispersed in an aluminium matrix). An aluminium alloy is used for the fuel can. In view of the change-over to the new FA the IVV-2M reactor power has increased 1.5 times (up to 15 MW), that has considerably widened its experimental potentialities. The maximum therma neutron flux density has reached 5x1014 cm-2 x s-1
Additional details
Additional titles
- Subtitle (English)
- Design and experience of application
- Original title (Russian)
- Тепловыделяющая сборка IVV-2M
- Original subtitle (Russian)
- Razrabotka i opyt ispol'zovaniya.
Publishing Information
- Journal Title
- At. Ehnerg.
- Journal Volume
- 61
- Journal Issue
- 5
- Series
- At. Ehnerg.
- Journal Page Range
- 344-346
- ISSN
- 0004-7163
- CODEN
- AENGA
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 19013656
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALUMINIUM; COOLANTS; DIAGRAMS; DISPERSION NUCLEAR FUELS; FLOW RATE; FLUX DENSITY; FUEL CANS; FUEL ELEMENT CLUSTERS; HOLLOW FUEL RODS; IRT-2000 MOSCOW REACTOR; MATRIX MATERIALS; MODIFICATIONS; NEUTRON FLUX; PRESSURE DROP; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION; THERMAL NEUTRONS; URANIUM DIOXIDE; WATER
- Descriptors DEC
- ACTINIDE COMPOUNDS; BARYONS; CHALCOGENIDES; DISTRIBUTION; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FERMIONS; FUEL ASSEMBLIES; FUEL ELEMENTS; FUEL RODS; FUELS; HADRONS; HYDROGEN COMPOUNDS; INFORMATION; MATERIALS; METALS; NEUTRONS; NUCLEAR FUELS; NUCLEONS; OXIDES; OXYGEN COMPOUNDS; POLAR SOLVENTS; POOL TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; SOLVENTS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS