Current and prospective safety issues at the HFBR Page: 1 of 8
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BNL-62638
CURRENT AND PROSPECTIVE SAFETY ISSUES AT THE HFBR
Paul R. Tichler
Reactor Division
Brookhaven National Laboratory
Upton, New York RECEIVED
MAR 19 1998
Introduction O S T t
The Brookhaven High Flux Beam Reactor (HFBR) was designed
primarily to produce external neutron beams for experimental
research. It is cooled, moderated and reflected by heavy water and
uses MTR-ETR type fuel elements containing enriched uranium. The
reactor power when operation began in 1965 was 40 MW, was raised to
60 MW in 1982 after a number of plant modifications, and operated
at that level until 1989. Since that time safety questions have
been raised which resulted in extended shutdowns and a reduction in
operating power to 30 MW. This paper will discuss the principle
safety issues, plans for their resolution and return to 60 MW
operation. In addition, radiation embrittlement of the reactor
vessel and thermal shield and its affect on the life of the
facility will be briefly discussed.
Core Thermal Hydraulics Issue
During normal operation, the primary system is pressurized
(200 psig) and the coolant flow direction is downward through the
DISTR BUTON O T OCYENIM A STER
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Tichler, P.R. Current and prospective safety issues at the HFBR, article, March 1, 1996; Upton, New York. (https://digital.library.unt.edu/ark:/67531/metadc672685/m1/1/: accessed April 24, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.