Deterministic and probabilistic evaluations for uncertainty in pipe fracture parameters in leak-before-break and in-service flaw evaluations

Technical Report · Sat Jun 01 00:00:00 EDT 1996

DOI:https://doi.org/10.2172/256412· OSTI ID:256412

Ghadiali, N; Wilkowski, G ^[1]; Rahman, S ^[2]; Choi, Y H ^[3]

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1. Battelle, Columbus, OH (United States)
2. Univ. of Iowa, Iowa City, IA (United States)
3. Korea Inst. of Nuclear Safety (KINS), Daeduk-danji Taejon (Korea, Republic of)

This report presents new results from deterministic and probabilistic analyses to evaluate the significance of a number of technical aspects that may affect LBB or in-service flaw evaluations. The following summarizes the objectives and results from both the deterministic and probabilistic studies. The reasons for including each technical aspect being evaluated are given first. Then a table is given that summarizes the relative significance of each technical aspect. In most cases there are both deterministic and probabilistic results. The deterministic analyses were conducted independently of the probabilistic analysis, which offered the opportunity to validate conclusions from each of these studies.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering Technology; Battelle Memorial Inst., Columbus, OH (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 256412
• Report Number(s): NUREG/CR-6443; BMI-2191; ON: TI96012372; NC: NONE; TRN: 96:003997
• Resource Relation: Other Information: PBD: Jun 1996
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
36 MATERIALS SCIENCE
NUCLEAR POWER PLANTS
PRIMARY COOLANT CIRCUITS
PIPES
IN-SERVICE INSPECTION
FAILURES
LEAKS
PROBABILISTIC ESTIMATION
P CODES