Published September 1993 | Version v1
Journal article Metadata-only

Fuel design method for Demonstration ATR

Creators

  • 1. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works

Description

The design work of MOX fuel for Demonstration ATR (Advanced Thermal Reactor) has been carried out under the agreement between the Electric Power Development Company (EPDC) and the Power Reactor and Nuclear Fuel Development Corporation (PNC). The fuel design method used here is based on that for Prototype ATR 'Fugen'. The method has also been improved by applying the current knowledge from the fuel irradiation test data. The validity of the method has been comfirmed by the good performance of MOX fuels used in 'Fugen'. In this paper the outline of the method is introduced. (author)

Additional details

Publishing Information

Journal Title
Donen Giho
Journal Issue
no.87
Journal Page Range
p. 53-61.
ISSN
0289-6605
CODEN
DOGIEL

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
25028980
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
A CODES; DEMONSTRATION PROGRAMS; DESIGN; FUEL CANS; IRRADIATION; JATR REACTOR; MIXED OXIDE FUELS; PERFORMANCE; STANDARDIZATION; VERIFICATION
Descriptors DEC
COMPUTER CODES; ENERGY SOURCES; FUELS; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; MATERIALS; NATURAL URANIUM REACTORS; NUCLEAR FUELS; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS