Developing a generalized flaw distribution for reactor pressure vessels

Author:

Jackson Deborah A,Doctor Steven R,Schuster George,Simonen Fred

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference14 articles.

1. American Society of Mechanical Engineers, 1998. ASME Boiler and Pressure Vessel Code. American Society of Mechanical Engineers, New York, NY.

2. Chapman, O.J.V., Simonen, F.A., 1998. RR-PRODIGAL — Model for Estimating the Probabilities of Defects in Reactor Pressure Vessel Welds. NUREG/CR-5505. US Nuclear Regulatory Commission, Washington, DC.

3. Chapman, O.J.V., Khaleel, M.A., Simonen, F.A., 1996. A simulation model for estimating probabilities of defects in weld. ASME PVP 323, 375–391.

4. Simulation of defects in weld construction;Chapman,1993

5. Dickson, T.L., 1994. FAVOR — Fracture Analysis Code for Nuclear Reactor Pressure Vessels, Preliminary Users Guide, February 1994 and FAVOR Release 9501, September 1995. Oak Ridge National Laboratory, US Nuclear Regulatory Commission, Public Document Room, Oak Ridge, TN.

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