Impact of reducing sodium void worth on the severe accident response of metallic-fueled sodium-cooled reactors [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1994.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 9 pages : digital, PDF file
- Additional Creators:
- Argonne National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- 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 −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.
- Report Numbers:
- E 1.99:anl/ra/cp--80012
E 1.99: conf-940402--10
- Other Subject(s):
- Published through SciTech Connect.
International topical meeting on the safety of advanced reactors,Pittsburgh, PA (United States),18-20 Apr 1994.
Wigeland, R.A.; Turski, R.B.; Pizzica, P.A.
- Funding Information:
View MARC record | catkey: 14365127