Impact of reducing sodium void worth on the severe accident response of metallic-fueled sodium-cooled reactors
Conference
·
OSTI ID:10130944
Analyses have performed on the severe accident response of four 90 MWth reactor cores, all designed using the metallic fuel of the Integrated Fast Reactor (IFR) concept. The four core designs have different sodium void worth, in the range of {minus}3$ to 5$. The purpose of the investigation is to determine the improvement in safety, as measured by the severe accident consequences, that can be achieved from a reduction in the sodium void worth for reactor cores designed using the IFR concept.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10130944
- Report Number(s):
- ANL/RA/CP-80012; CONF-940402-10; ON: DE94007653
- Resource Relation:
- Conference: International topical meeting on the safety of advanced reactors,Pittsburgh, PA (United States),18-20 Apr 1994; Other Information: PBD: [1994]
- Country of Publication:
- United States
- Language:
- English
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