Reactor materials program: LBB assessment - heat exchangers

Technical Report · Fri Apr 15 04:00:00 EDT 1988

OSTI ID:7175983

Sindelar, R L

A credible Loss-of-Coolant Accident (LOCA) for the Savannah River Production Reactors is being defined through studies of the failure mechanisms in the components of the process water (PW) system. A component that can exhibit leakage or cracking that is readily detected prior to a large-break failure demonstrates a Leak-Before-Break (LBB) capability and would allow safe reactor shutdown well in advance of a large break. A related sequence which encompasses LBB is the Detect-Before-Break (DBB) assessment which considers inspection of the component and crack detection by leakage or visual methods to ensure integrity of the pressure boundary of the component. The LBB capability of the PW system is performed by assessing the pressure boundary integrity and determining the ability to exhibit leakage prior to an unacceptably large break for each component of the system. It has been demonstrated that pipe weldments will not fail causing a sudden double-ended-guillotine break (DEGB) in the PW system. The LBB and DBB ability of the flanges, valves and pumps has also been demonstrated. The subject of this report is the demonstration of the LBB/DBB capability of the heat exchangers in the SRP process water system. 10 figs.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Plant
• DOE Contract Number: AC09-76SR00001
• OSTI ID: 7175983
• Report Number(s): DPST-88-472; ON: DE88011671
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
HEAT EXCHANGERS
HEAT TRANSFER
LEAKS
LOAD ANALYSIS
LOSS OF COOLANT
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAVANNAH RIVER PLANT
STRESS ANALYSIS
US AEC
US DOE
US ERDA
US ORGANIZATIONS