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Safety Analysis of IFR Fuel Processing in the Argonne National Laboratory Fuel Cycle Facility

Conference ·
OSTI ID:10185441
 [1];  [1];  [2];  [2]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
  2. Argonne National Lab. (ANL), Idaho Falls IL (United States)
+ Show Author Affiliations
The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL's Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed.
Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States); Argonne National Lab. (ANL), Idaho Falls IL (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Technology Support Programs
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
10185441
Report Number(s):
ANL/RE/CP--79630; CONF-930913--41; ON: DE93040234
Country of Publication:
United States
Language:
English

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Related Subjects

050800
054000
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
ACCIDENTS
ANL
Blanket Fuel Materials
CRITICALITY
DEMONSTRATION PROGRAMS
Discharged Core
EBR-2 REACTOR
FUEL CYCLE CENTERS
Fuel Cycle Facility (FCF)
HEALTH AND SAFETY
IFR REACTOR
Integral Fast Reactor (IFR)
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
BREEDING
PROBABILITY
SAFETY
SAFETY ANALYSIS
SPENT FUELS REPROCESSING
Safety Analysis Report
Safety Exhaust System (SES).