Published April 2005 | Version v1
Journal article Metadata-only

Safety of the БОР-60 spend fuel regeneration process by pyroelectrochemical method

Creators

  • 1. GNTs RF - NIIAR, Dimitrovgrad (Russian Federation)

Description

Results of studying the safety of regeneration of 15.5 kg of the BOR-60 spent fuel are presented. The absolute values of radioactive aerosols, transferred into the ventilation system of the pytoelectrochemical plant, are determined. The data on the possibility of realization of the high yield of uranium and plutonium into the finished product at their small content in solid wastes are presented. The production irradiations of the personnel, taking part in all stages of fuel regeneration, are estimated

Abstract (Russian)

Приводятся результаты исследования безопасности регенерации 15.5 кг отработавшего топлива БОР-60. Определены абсолютные значения поступления радиоактивных аэрозолей в вентиляционную систему пироэлектрохимической установки. Приведены данные о возможности реализации высокого выхода урана и плутония в готовый продукт при их незначительном содержании в твердых отходах. Сделаны оценки производственного облучения персонала, задействованного на всех стадиях процесса

Additional details

Additional titles

Original title (Russian)
Безопасност' регенерации отработавшего топлива BOR-60 пироэлектрохимическим методом

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
98
Journal Issue
4
Journal Page Range
p. 280-288
ISSN
0004-7163
CODEN
AENGAB

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
38011358
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Descriptors DEI
BOR-60 REACTOR; ELECTROCHEMISTRY; PERSONNEL DOSIMETRY; PLUTONIUM; PYROCHEMICAL REPROCESSING; RADIATION DOSES; RADIOACTIVE AEROSOLS; RADIOISOTOPES; REGENERATION; SAFETY; SPENT FUELS; URANIUM; VENTILATION SYSTEMS
Descriptors DEC
ACTINIDES; AEROSOLS; BREEDER REACTORS; CHEMISTRY; COLLOIDS; DISPERSIONS; DOSES; DOSIMETRY; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; ISOTOPES; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; REPROCESSING; RESEARCH AND TEST REACTORS; SEPARATION PROCESSES; SODIUM COOLED REACTORS; SOLS; TRANSURANIUM ELEMENTS

Optional Information

Notes
8 refs., 3 figs., 1 tab.