Actions for SSC analysis of the GEMs for reactivity control in PRISM [electronic resource].

Email RIS file
Bookmark
Report an Issue

SSC analysis of the GEMs for reactivity control in PRISM [electronic resource].

Published
Rockville, Md. : U.S. Nuclear Regulatory Commission, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
16 pages : digital, PDF file
Additional Creators
Brookhaven National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online

Availability

I Want It
I Want It

Finding items...

Restrictions on Access
Free-to-read Unrestricted online access
Summary
The performance of three Gas Expansion Modules (GEMS) utilized the Advanced Liquid Metal Reactor (ALMR) concept, PRISM, was analyzed using the computer code, SSC. GE has submitted the PRISM design for a Preapplication Safety Evaluation Report (PSER). The draft PSER indicated a potential weakness in the Unscrammed Loss of Flow (ULOF) event, and GE modified the design by adding three GEMs. The PRISM design was analyzed by SSC for two cases. First, the design`s original response to a ULOF where one Electro Magnetic (EM) pump fails to produce a coastdown was analyzed. Then the revised design with the GEMs included was analyzed. The original design had little or no safety margin for this case. The peak fuel temperature in the hot channel was predicted to be 1358K, which is above the solidus temperature of the fuel. However, after the GEMs were added, the loss of one EM pump coastdown became a benign event. The GEM feedback was predicted by SSC to dominate the other reactivity feedbacks and the GEMS, essentially, responded like passive control rods. The fuel temperature quickly dropped below operating temperatures, while the margin to sodium boiling was predicted to be greater than 350K.
Report Numbers
E 1.99:bnl-nureg--47978
E 1.99: conf-921007--17
conf-921007--17
bnl-nureg--47978
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
12/31/1992.
"bnl-nureg--47978"
" conf-921007--17"
"DE93007280"
20. water reactor safety information meeting,Bethesda, MD (United States),21-23 Oct 1992.
Slovik, G.C.; Rodnizki, J.
Funding Information
AC02-76CH00016
View MARC record | catkey: 14365337