Published 2005 | Version v1
Book

Development and demonstration of ATR-MOX fuel

  • 1. Japan Nuclear Cycle Development Institute (Japan)

Description

Japan Nuclear Cycle Development Institute (JNC) has developed plutonium and uranium mixed oxide (MOX) fuels for an advanced thermal reactor (ATR) to provide a flexible utilization of plutonium. JNC endeavored to obtain well-homogenized MOX pellets by a ball mill mixing method with a variety of raw powders; one of these powders included MOX powder prepared by a microwave-heating denitration process. A total of 772 MOX fuel assemblies were utilized in the ATR prototype reactor 'FUGEN' with no failures throughout its entire operation period. The adequacy of the fuel fabrication system, including fuel design and quality control, was demonstrated by theses remarkable irradiation results. JNC also developed an advanced MOX fuel assembly for a demonstration ATR. The integrity of the advanced fuel assembly under in-core conditions was proven by various irradiation experiments. The demonstration ATR was unfortunately canceled as part of governmental economy measures, but extensive irradiation data of MOX fuels have contributed to develop LWR-MOX fuels. (authors)

Part of:
The 13th international conference on nuclear engineering abstracts

Additional details

Additional titles

Augmented title (English)
The ATR-MOX is stated for Advanced Thermal Reactor-Mixed OXide

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
7-5022-3400-4
Imprint Title
The 13th international conference on nuclear engineering abstracts
Imprint Pagination
604 p.
Journal Page Range
p. 321

Conference

Title
13. international conference on nuclear engineering
Dates
16-20 May 2005
Place
Beijing (China)

Optional Information