Published 1997 | Version v1
Book Metadata-only

Performance of uranium-plutonium mixed carbide fuel under irradiation

Creators

  • 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

Description

The irradiation behavior of uranium-plutonium mixed carbide fuel, which is a candidate of advanced fast reactor fuels, was investigated. Nine encapsulated carbide fuel pins cladded with SUS316 tubes were irradiated at JRR-2 and JMTR up to the maximum burnup of 4.7%FIMA at the heating rates of 42-64kW/m. No pin failure was observed in any pin examined. It is confirmed from the tests that the fission gas release may depend on open porosity as well as burnup. Furthermore, the irradiation behavior such as restructuring, distribution of FPs and actinide elements, fuel-clad chemical interaction and mechanical interaction were investigated. (author)

Part of:
International conference on future nuclear systems. Challenge towards second nuclear era with advanced fuel cycles. Proceedings

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
International conference on future nuclear systems. Challenge towards second nuclear era with advanced fuel cycles. Proceedings
Imprint Pagination
1588 p.
Journal Page Range
p. 522-527

Conference

Title
International conference on future nuclear systems
Acronym
Global '97
Dates
5-10 Oct 1997
Place
Yokohama (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
29037440
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CESIUM; FBR TYPE REACTORS; FISSION PRODUCTS; FUEL CANS; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; IRRADIATION; JMTR REACTOR; KRYPTON; MIXED CARBIDE FUELS; PALLADIUM; POST-IRRADIATION EXAMINATION; RADIONUCLIDE MIGRATION; STAINLESS STEEL-316; VOIDS; XENON
Descriptors DEC
ALKALI METALS; ALLOYS; AUSTENITIC STEELS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; ENVIRONMENTAL TRANSPORT; EPITHERMAL REACTORS; FAST REACTORS; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; ISOTOPES; MASS TRANSFER; MATERIALS; MATERIALS TESTING REACTORS; METALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NONMETALS; NUCLEAR FUELS; PLATINUM METALS; RADIOACTIVE MATERIALS; RARE GASES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Published in 2 volumes