Published October 2000 | Version v1
Journal article Metadata-only

Fuel cycle of BREST reactor

Creators

  • 1. NIKIEhT, Moscow (Russian Federation)
  • 2. GNTs RF - VNIINM im. A.A. Bochvara, Moscow (Russian Federation)

Description

The concept of the fast reactors working in uranium-plutonium closed cycle is discussed. The characteristics of the BREST type reactors with the uranium-plutonium nitride fuel are given. The joint requirements to the technology of the BREST reactors provide plutonium proliferation. The fuel cycle stages of the BREST-OD-300 reactor are examined. The electrochemical regeneration in the molten chloride salts with the reduction of actinides to nitrides takes into account in the BREST-OD-300 project

Abstract (Russian)

Обсуждается концепция быстрых реакторов, работающих в замкнутом уран-плутониевом цикле. Представлены характеристики реакторов типа БРЕСТ с нитридным уран-плутониевым топливом. Общие требования, предъявляемые к технологии топливного цикла реакторов БРЕСТ, обеспечивают нераспространение плутония. Рассмотрены этапы топливного цикла реактора БРЕСТ-ОД-300. В проекте БРЕСТ-ОД-300 принята электрохимическая регенерация в расплаве хлоридных солей с восстановлением актиноидов до нитридов

Additional details

Additional titles

Original title (Russian)
Топливный цикл реакторов БРЕСТ

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
89
Journal Issue
4
Journal Page Range
p. 308-314
ISSN
0004-7163
CODEN
AENGAB

Conference

Title
Scientific conference of Minatom of Russia. Nuclear fuel cycle
Original Conference Title
Nauchnaya konferentsiya Minatoma Rossii. Yadernyj toplivnyj tsikl
Dates
Jun 2000
Place
Moscow (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
34046262
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHLORIDES; ELECTROLYSIS; FAST REACTORS; MIXED NITRIDE FUELS; MOLTEN SALTS; PLUTONIUM NITRIDES; PLUTONIUM RECYCLE; REACTOR CORES; URANIUM NITRIDES; URANIUM RECYCLE
Descriptors DEC
ACTINIDE COMPOUNDS; CHLORINE COMPOUNDS; ENERGY SOURCES; EPITHERMAL REACTORS; FUEL CYCLE; FUELS; HALIDES; HALOGEN COMPOUNDS; LYSIS; MATERIALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; PLUTONIUM COMPOUNDS; PNICTIDES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SALTS; SOLID FUELS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS

Optional Information

Notes
5 refs., 2 figs.