Published February 2006 | Version v1
Journal article Metadata-only

Fast-neutron homogeneous nuclear reactor

Creators

  • 1. Natsional'nyj Yadernyj Tsentr Respubliki Kazakhstan, Alma-Ata (Kazakhstan)

Description

A new design of a homogeneous fast reactor (HFR) is proposed. The suspension, consisting of uranium dioxide in the form of powder in the alloy of Bi(52.5%), Pb(32%) and Sn(15.5%) with the melting point of 96 deg C is proposed as the fuel. It is shown that the HFR core design will be simplified and the efficiency of the uranium-thorium fuel using will be increased

Abstract (Russian)

Предложена новая конструкция гомогенного быстрого реактора (ГБР). В качестве топлива предложена взвесь, состоящая из диоксида урана в виде порошка в сплаве Bi(52.5%), Pb(32%) и Sn(15.5%) с температурой плавления 96 град С. Проведенные исследования показывают, что конструкция активной зоны ГБР будет упрощена и повышена эффективность использования уран-ториевого топлива

Additional details

Additional titles

Original title (Russian)
Быстрый гомогенный ядерный реактор

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
100
Journal Issue
2
Journal Page Range
p. 157-159
ISSN
0004-7163
CODEN
AENGAB

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
38055941
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BISMUTH BASE ALLOYS; DESIGN; EFFICIENCY; FAST REACTORS; FEASIBILITY STUDIES; HOMOGENEOUS REACTORS; NUCLEAR FUELS; POWDERS; REACTOR CORES; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ALLOYS; BISMUTH ALLOYS; CHALCOGENIDES; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
6 refs., 2 figs.