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Title: Conceptual design of module fast reactor of ultimate safety cooled by lead-bismuth alloy

During past time all basic problems arisen during working-out of NPP with lead-bismuth coolant were solved: physics and thermal physics of the cores, heat transfer and hydrodynamics, corrosion resistance of the structural materials and coolant technology, radiation and nuclear safety, investigations of emergency situations, development of fuel elements and absorbing elements of the reactor, equipment of the primary circuit and other circuits. A powerful experimental base equpped by unique rigs is made. A series of ship and test NPP has been constructed whereat repair of the plants and reactor refuelling are developed. Highly-skilled groups of investigators, designers and operation personnel capable of performing the development of the reactor plant with MFR within short terms have been formed. In this case MFR with lead-bismuth coolant may become the initial step in development of large-scale nuclear power engineering with fast reactors cooled by liquid lead.
Authors:
; ; ; ; ; ; ; ;  [1]
  1. and others
Publication Date:
OSTI Identifier:
107284
Report Number(s):
CONF-920957-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 95:021013
Resource Type:
Journal Article
Resource Relation:
Journal Name: Transactions of the American Nuclear Society; Journal Volume: 67; Journal Issue: Suppl.1; Conference: 3. annual Nuclear Society International (NSI) meeting: nuclear technology tomorrow, St. Petersburg (Russian Federation), 14-18 Sep 1992; Other Information: PBD: 1993
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; LIQUID METAL COOLED REACTORS; DESIGN; BISMUTH; CORROSION RESISTANCE; FAST REACTORS; FUEL ELEMENTS; HEAT TRANSFER; HYDRODYNAMICS; LEAD; DIAGRAMS; AFTER-HEAT REMOVAL; REACTOR CORES