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Title: Initial Requirements for Gas-Cooled Fast Reactor (GFR) System Design, Performance, and Safety Analysis Models

The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radio toxicity of both its own fuel and other spent nuclear fuel, and for extending/utilizing uranium resources orders of magnitude beyond what the current open fuel cycle can realize. In addition, energy conversion at high thermal efficiency is possible with the current designs being considered, thus increasing the economic benefit of the GFR. However, research and development challenges include the ability to use passive decay heat removal systems during accident conditions, survivability of fuels and in-core materials under extreme temperatures and radiation, and economical and efficient fuel cycle processes. Nevertheless, the GFR was chosen as one of only six Generation IV systems to be pursued based on its ability to meet the Generation IV goals in sustainability, economics, safety and reliability, proliferation resistance and physical protection.
Authors:
;
Publication Date:
OSTI Identifier:
911212
Report Number(s):
INEEL/EXT-04-02242
TRN: US0704463
DOE Contract Number:
DE-AC07-99ID-13727
Resource Type:
Technical Report
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
DOE - NE
Country of Publication:
United States
Language:
English
Subject:
21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; AFTER-HEAT REMOVAL; ECONOMICS; ENERGY CONVERSION; FAST REACTORS; FUEL CYCLE; NUCLEAR FUELS; PHYSICAL PROTECTION; PROLIFERATION; REACTORS; RELIABILITY; SAFETY; SAFETY ANALYSIS; THERMAL EFFICIENCY; TOXICITY; URANIUM; SPENT FUELS gas-cooled fast reactor