Published 1999 | Version v1
Miscellaneous Open

Nuclear reactor fuel cycle technology with pyroelectrochemical processes

Creators

  • 1. GNTs RF Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dmitrovgrad (Russian Federation)

Description

A group of dry technologies and processes of vibro-packing granulated fuel in combination with unique properties of vibro-packed FEs make it possible to implement a new comprehensive approach to the fuel cycle with plutonium fuel. Testing of a big number of FEs with vibro-packed U-Pu oxide fuel in the BOR-60 reactor, successful testing of experimental FSAs in the BN-600 rector, reliable operation of the experimental and research complex facilities allow to make the conclusion about a real possibility to develop a safe, economically beneficial U-Pu fuel cycle based on the technologies enumerated above and to use both reactor-grade and weapon-grade plutonium in nuclear reactors with a reliable control and accounting system

Abstract (Russian)

Совокупность сухих технологий и процессов виброуплотнения гранулированного топлива в сочетании с уникальными свойствами виброуплотненного твэла позволяют реализовать новый комплексный подход к проблеме топливного цикла с использованием плутониевого топлива. Массовые испытания твэлов с виброуплотнением уран-плутониевым оксидным топливом в реакторе БОР-60, успешные испытания экспериментальных ТВС в реакторе БН-600, надежная работа установок опытно-исследовательского комплекса позволяют сделать вывод о реальной возможности создания безопасного, экономически выгодного уран-плутониевого топливного цикла на основе перечисленных технологий, а также о реальной возможности утилизации с обеспечением надежгой системы учета и контроля как энергетического так и оружейного плутония в ядерных реакторах

Files

32037326.pdf

Files (208.5 kB)

Name Size Download all
md5:990bc76371526ea20b17aede05b884f5
208.5 kB Preview Download

System files (17.3 kB)

Name Size Download all
Part of:
Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants

Additional details

Additional titles

Original title (Russian)
Технологии топливного цикла ядерных реакторов с использованием пироэлектрохимических процессов

Publishing Information

Publisher
Gosudarstvennyj Nauchnyj Tsentr RF - Fiziko-Ehnergeticheskij Inst. im. akademika A.I. Lejpunskogo
Imprint Place
Obninsk (Russian Federation)
Imprint Title
Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants
Imprint Pagination
250 p.
Journal Page Range
p. 246-251
Report number
INIS-RU--455

Conference

Title
Nuclear Material Accounting and Control at Radiochemical Plants
Original Conference Title
Uchet i kontrol' yadernykh materialov na radiokhimicheskikh ustanovkakh
Dates
2-6 Nov 1998
Place
Obninsk (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
32037326
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BELOYARSK-3 REACTOR; BOR-60 REACTOR; ELECTROLYSIS; FUEL ELEMENTS; MOLTEN SALTS; NUCLEAR MATERIALS MANAGEMENT; PLUTONIUM DIOXIDE; PLUTONIUM RECYCLE; PRECIPITATION; RADIOACTIVE WASTES; URANIUM DIOXIDE; URANIUM RECYCLE
Descriptors DEC
ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL CYCLE; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; LYSIS; MANAGEMENT; MATERIALS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SALTS; SEPARATION PROCESSES; SODIUM COOLED REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; WASTES

Optional Information

Notes
3 tabs. Imprint:Trudy trekhstoronnego seminara Uchet i kontrol' yadernykh materialov na radiokhimicheskikh ustanovkakh