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Title: A 100 MWe advanced sodium-cooled fast reactor core concept

An Advanced sodium-cooled Fast Reactor core concept (AFR-100) was developed targeting a small electrical grid to be transportable to the plant site and operable for a long time without frequent refueling. The reactor power rating was strategically decided to be 100 MWe, and the core barrel diameter was limited to 3.0 m for transportability. The design parameters were determined by relaxing the peak fast fluence limit and bulk coolant outlet temperature to beyond irradiation experience assuming that advanced cladding and structural materials developed under US-DOE programs would be available when the AFR-100 is deployed. With a de-rated power density and U-Zr binary metallic fuel, the AFR-100 can maintain criticality for 30 years without refueling. The average discharge burnup of 101 MWd/kg is comparable to conventional design values, but the peak discharge fast fluence of {approx}6x10{sup 23} neutrons/cm{sup 2} is beyond the current irradiation experiences with HT-9 cladding. The evaluated reactivity coefficients provide sufficient negative feedbacks and the reactivity control systems provide sufficient shutdown margins. The integral reactivity parameters obtained from quasi-static reactivity balance analysis indicate that the AFR-100 meets the sufficient conditions for acceptable asymptotic core outlet temperature following postulated unprotected accidents. Additionally, the AFR-100 has sufficient thermal margins bymore » grouping the fuel assemblies into eight orifice zones. (authors)« less
Authors:
; ;  [1]
  1. Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States)
Publication Date:
OSTI Identifier:
22105676
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 17 refs.
Publisher:
American Nuclear Society - ANS; La Grange Park, IL (United States)
Research Org:
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BUILDING MATERIALS; CLADDING; CONTROL SYSTEMS; DESIGN; FAST REACTORS; FERRITIC STEELS; FUEL ASSEMBLIES; IRRADIATION; MARTENSITIC STEELS; NEUTRONS; PEAKS; REACTIVITY; REACTIVITY COEFFICIENTS; REACTOR CORES; REACTOR SHUTDOWN; SODIUM COOLED REACTORS; URANIUM; US DOE; ZIRCONIUM