Published 1991 | Version v1
Book

Development of production processes for mixed (U-Pu) oxides suitable for fast and thermal reactor fuel

  • 1. Vsesoyuznyj Nauchno-Issledovatel'skij Inst. Neorganicheskikh Materialov, Moscow (USSR)

Description

The paper discusses the results of studies aimed at developing production processes for fast and thermal reactor mixed U-Pu fuel: sol-gel spheres; granular oxides through ammonia precipitation; oxides through carbonate precipitation. The merits and disadvantages of the methods are considered. The features of the process implementation are discussed. The developments have reached the level of semi-commercial testing in the course of which large batches of mixed fuel have been produced; pilot fuel assemblies have been fabricated for the fast reactor BN-600. (author)

Additional details

Publishing Information

Publisher
Japan Atomic Industrial Forum.
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of the third international conference on nuclear fuel reprocessing and waste management, RECOD'91
Imprint Pagination
1186 p.
Journal Page Range
p. 213-216.

Conference

Title
3. international conference on nuclear fuel reprocessing and waste management, RECOD'91.
Dates
14-18 Apr 1991.
Place
Sendai (Japan).

Optional Information

Notes
Imprint:Composed of two volumes.