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Title: Integral fast reactor safety features

The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents.
Authors:
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Publication Date:
OSTI Identifier:
5155906
Report Number(s):
CONF-880506-12
ON: DE88010012
DOE Contract Number:
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: Safety of next generation power reactors, Seattle, WA, USA, 1 May 1988
Research Org:
Argonne National Lab., IL (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; IFR REACTOR; REACTOR SAFETY; DESIGN BASIS ACCIDENTS; ECONOMICS; FISSION PRODUCT RELEASE; FUEL CANS; FUEL ELEMENTS; LMFBR TYPE REACTORS; MITIGATION; NEUTRON ABSORBERS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; ACCIDENTS; BREEDER REACTORS; COOLING SYSTEMS; ENERGY SYSTEMS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; ZERO POWER REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors; 210500 -- Power Reactors, Breeding