Published 1990 | Version v1
Book

Loss of coolant analysis for the tower shielding reactor II

  • 1. Research Reactors Div., Oak Ridge National Lab., Oak Ridge, TN (United States)

Description

The operational limits of the Tower Shielding Reactor-II (TSR-II) have been revised to account for placing the reactor in a beam shield, which reduces convection cooling during a loss-of-coolant accident (LOCA). This paper reports on a detailed heat transfer analysis performed to set operating time limits which preclude fuel damage during a LOCA. Since a LOCA is survivable, the pressure boundary need not be safety related, minimizing seismic and inspection requirements. Measurements of reactor component emittance for this analysis revealed that aluminum oxidized in water may have emittances much higher than accepted values, allowing higher operating limits than were originally expected. These limits could be increased further with analytical or hardware improvements

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (United States)
Imprint Title
The safety, status and future of non-commercial reactors and irradiation facilities
Imprint Pagination
830 p.
Journal Page Range
p. 131-138.

Conference

Title
American Nuclear Society (ANS) topical meeting on the safety, status and future of non-commercial reactors and irradiation facilities.
Dates
30 Sep - 4 Oct 1990.
Place
Boise, ID (United States).

Optional Information

Secondary number(s)
CONF-900917--.