The strainer blockage assessment methodology used
- Science and Engineering Associates, Inc., Albuquerque, NM (United States)
On July 28, 1992 a spurious opening of a safety valve at Barseback Unit 2 in Sweden resulted in clogging of the Containment Vessel Spray System strainers in less than one hour. Instances of ECCS strainer clogging have occurred in U.S. BWRs. Given these precursors the USNRC staff initiated analyses to estimate the potential for loss of NPSH of the ECCS pumps in BWRs due to clogging of suction strainers by a combination of fibrous and particulate material. The BLOCKAGE code was developed in support of NUREG/CR-6224, a probabilistic scoping analysis of a BWR/4 with a Mark 1 containment. This paper addresses the key elements of the methodology used in the BLOCKAGE code to assess head loss across ECCS strainers. The debris generation model, the debris drywell transport, and the suppression pool models are discussed briefly. NUREG/CR-6224 provides in-depth discussions of the models used in BLOCKAGE. Additionally, user interface features of BLOCKAGE are discussed.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States)
- OSTI ID:
- 269678
- Report Number(s):
- NUREG/CP--0149-Vol.3; CONF-9510156--Vol.3; ON: TI96007986
- Country of Publication:
- United States
- Language:
- English
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