Published 2002 | Version v1
Report Metadata-only

Operational experience and upgrading program of the experimental fast reactor JOYO

Creators

  • 1. Japan Nuclear Cycle Development Institute, Experimental Reactor Division, Oarai Engineering Center, lbaraki (Japan)
  • 2. Japan Nuclear Cycle Development Institute, Experimental Reactor Division, Oarai Engineering Center, lbaraki (JP)

Description

Twenty years of successful operations at the experimental fast reactor JOYO provide a wealth of experience covering core management, chemical analysis of sodium and cover gas for impurity control, natural convection tests, upgrade of fuel failure detection system, corrosion product measurement, development of operation and maintenance support system, and replacement of major components in the cooling systems. Some of the data obtained is stored in a database to preserve the related knowledge. This experience and accumulated data will be useful for the design of future fast reactors. (author)

Part of:
Technical meeting on 'Operational and decommissioning experience with fast reactors'. Working material

Additional details

Publishing Information

Imprint Title
Technical meeting on 'Operational and decommissioning experience with fast reactors'. Working material
Imprint Pagination
780 p.
Journal Page Range
p. 66-187
Report number
IAEA-TM--25332

Conference

Title
IAEA-TWGFR technical meeting on 'Operational and decommissioning experience with fast reactors'
Dates
11-15 Mar 2002
Place
Cadarache (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
34029222
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORROSION; FUEL ELEMENT FAILURE; FUEL MANAGEMENT; JOYO REACTOR; LEARNING; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR MAINTENANCE; SODIUM
Descriptors DEC
ALKALI METALS; BREEDER REACTORS; CHEMICAL REACTIONS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MAINTENANCE; MANAGEMENT; METALS; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS

Optional Information

Notes
20 refs, 28 figs, 5 tabs
Secondary number(s)
TWG-FR--109