Published 1996 | Version v1
Miscellaneous

Depletion calculation of two recycled alternative fuels in PWR

  • 1. Minas Gerais Univ., Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear

Description

The Alternative Reprocessed Methods, with lower characteristics of decontamination and coextraction of uranium and plutonium, have been proposed with the goal of recycle fissile material from PWR. Some neutronics studies are shown the possibility of utilization of these fuels without modification in the design and operational conditions. In this work we present an evaluation of the performance of the AIROX and Coprocessed fuels after two recycles of 33.000 MWd/T. The burnup of the fuel and the buildup of the fission products are studied by the code ORIGEN2.1 to verify their influence in the multiple recycles of these fuels. (author)

Availability note (English)

Available from the library of the Brazilian Nuclear Energy Commission, Rio de Janeiro

Additional details

Additional titles

Original title (Portuguese)
Calculo de deplecao de combustiveis alternativos bi-reciclados em PWR

Publishing Information

Imprint Pagination
5 p.

Conference

Title
6. General congress on nuclear energy
Original Conference Title
6. Congresso geral de energia nuclear
Dates
27 Oct - 1 Nov 1996
Place
Rio de Janeiro, RJ (Brazil)

Optional Information

Notes
4 refs., 5 figs.; claubia at oraculo.lcc.ufmg.br