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Fast reactors in nuclear power

Journal Article:

Abstract

The possible applications are discussed of fast reactor nuclear power plants. Basic differences are explained in fast and thermal reactors, mainly with a view to nuclear fuel utilization. Discussed in more detail are the problems of nuclear fuel reproduction and the nost important technical problems of fast reactors. Flow charts are shown of heat transfer for fast reactors BN-350 (loop design) and BN-600 (integral coolant circuit design). Main specifications are given for demonstration and power fast reactors in operation, under construction and in project-stage.
Authors:
Publication Date:
Feb 01, 1981
Product Type:
Journal Article
Reference Number:
AIX-12-642359; EDB-82-028809
Resource Relation:
Journal Name: Veda Tech. SSSR; (Czechoslovakia); Journal Volume: 9:1
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BELOYARSK-3 REACTOR; BN-1600 REACTOR; BN-350 REACTOR; NUCLEAR ENERGY; NUCLEAR FUELS; NUCLEAR POWER PLANTS; BREEDER REACTORS; DESALINATION REACTORS; ENERGY; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SODIUM COOLED REACTORS; THERMAL POWER PLANTS; 210500* - Power Reactors, Breeding
OSTI ID:
6051864
Country of Origin:
Serbia and Montenegro
Language:
Czech
Other Identifying Numbers:
Journal ID: CODEN: VDTCA
Submitting Site:
INIS
Size:
Pages: 4-11
Announcement Date:

Journal Article:

Citation Formats

Kazachkovskii, O. Fast reactors in nuclear power. Serbia and Montenegro: N. p., 1981. Web.
Kazachkovskii, O. Fast reactors in nuclear power. Serbia and Montenegro.
Kazachkovskii, O. 1981. "Fast reactors in nuclear power." Serbia and Montenegro.
@misc{etde_6051864,
title = {Fast reactors in nuclear power}
author = {Kazachkovskii, O}
abstractNote = {The possible applications are discussed of fast reactor nuclear power plants. Basic differences are explained in fast and thermal reactors, mainly with a view to nuclear fuel utilization. Discussed in more detail are the problems of nuclear fuel reproduction and the nost important technical problems of fast reactors. Flow charts are shown of heat transfer for fast reactors BN-350 (loop design) and BN-600 (integral coolant circuit design). Main specifications are given for demonstration and power fast reactors in operation, under construction and in project-stage.}
journal = {Veda Tech. SSSR; (Czechoslovakia)}
volume = {9:1}
journal type = {AC}
place = {Serbia and Montenegro}
year = {1981}
month = {Feb}
}