Published May 2003 | Version v1
Report Metadata-only

Issues of lead coolant technology

Creators

  • 1. State Scientific Center of Russian Federation (SSC RF), Institute for Physics and Power Engineering (IPPE), Obninsk (Russian Federation)

Description

Starting from 1989 with the BREST-OD-300 reactor design development, some experimental studies related to lead coolant have been performed to provide feasibility of using liquid lead as a coolant in the closed circuit. Further comprehensive analytical and experimental studies are required to develop lead coolant technology for the BREST-OD-300 reactor design. General work program for justification of lead coolant technology are planned aiming at not only getting the information on the components required for the technology realization and their design features but also revealing the possibility of use of data obtained in the course of lead-bismuth circuit operation for the lead circuits. The main results performed so far for justification of BREST-OD-300 reactor coolant technology are presented in this paper. The results confirmed the possibility of using the experience gained on lead-bismuth coolant justification on the stage of the BREST-OD-300 reactor design development. In addition, the results provided directions for further justification of lead coolant technology based on experience gained on lead-bismuth coolant. (author)

Part of:
Power reactors and sub-critical blanket systems with lead and lead-bismuth as coolant and/or target material. Utilization and transmutation of actinides and long lived fission products

Additional details

Identifiers

URL
http://www-pub.iaea.org/MTCD/publications/PDF/te_1348_web.pdf; http://www-pub.iaea.org/MTCD/publications/publications.asp;

Publishing Information

ISBN
92-0-101503-8
Imprint Title
Power reactors and sub-critical blanket systems with lead and lead-bismuth as coolant and/or target material. Utilization and transmutation of actinides and long lived fission products
Imprint Pagination
221 p.
Journal Page Range
p. 95-98
ISSN
1011-4289
Report number
IAEA-TECDOC--1348

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
34087439
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
DESIGN; EXPERIMENTAL DATA; LEAD; LIQUID METALS; LMFBR TYPE REACTORS; REACTOR COOLING SYSTEMS; TECHNOLOGY ASSESSMENT
Descriptors DEC
BREEDER REACTORS; COOLING SYSTEMS; DATA; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUIDS; INFORMATION; LIQUID METAL COOLED REACTORS; LIQUIDS; METALS; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS
Proposed descriptors and Free-text terms
BREST-300 reactor

Optional Information