Published December 1990 | Version v1
Report Metadata-only

Calculated and experimental justification of vibropac fuel pins utilization in thermal power reactors

Creators

  • 1. Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)

Description

At present a marked progress has been achieved in the development of methods for uranium and uranium-plutonium dioxide granulation at RIAR. In the period from 1978 till 1987 a complex of pilot-plants has been operated, including a plant for fabrication of granulated MOX fuel and an automated remotely controlled line for production of vibropac fuel pins and assemblies for the BOR-60 reactor. A complex of calculated and experimental investigations on vibropac oxide fuel pins utilization in the thermal neutron reactors has been carried out. On the whole positive results offer wide opportunities for development of pins with serviceability up to the highest burnups under load-following conditions and available for automated remote production. (author). 7 figs, 3 tabs

Part of:
Recycling of plutonium and uranium in water reactor fuels

Additional details

Publishing Information

Imprint Title
Recycling of plutonium and uranium in water reactor fuels
Imprint Pagination
340 p.
Journal Page Range
p. 150-158.
Report number
IWGFPT--35

Conference

Title
Technical committee meeting on recycling of plutonium and uranium in water reactor fuels.
Dates
13-16 Nov 1989.
Place
Cadarache (France).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
22049847
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOR-60 REACTOR; FEASIBILITY STUDIES; FUEL PINS; MICROSTRUCTURE; MIXED OXIDE FUELS; PELLETIZING; PERFORMANCE TESTING; REMOTE CONTROL; USSR
Descriptors DEC
BREEDER REACTORS; CONTROL; CRYSTAL STRUCTURE; DEVELOPED COUNTRIES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EUROPE; EXPERIMENTAL REACTORS; FABRICATION; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MOLDING; NUCLEAR FUELS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; SOLID FUELS; TESTING

Optional Information