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  • Open Daily: 10am - 10pm
    Alley-side Pickup: 10am - 7pm

    3038 Hennepin Ave Minneapolis, MN
    612-822-4611

Open Daily: 10am - 10pm | Alley-side Pickup: 10am - 7pm
3038 Hennepin Ave Minneapolis, MN
612-822-4611
Sensitivity Studies of the Probabilistic Fracture Mechanics Model Used in FAVOR

Sensitivity Studies of the Probabilistic Fracture Mechanics Model Used in FAVOR

Eriksonkirk, M.
Dickson, T.
Commission, U. S. Nuclear Regulatory

Paperback

Technology & Engineering

ISBN10: 1500610712
ISBN13: 9781500610715
Publisher: Createspace
Published: Jul 22 2014
Pages: 84
Weight: 0.48
Height: 0.17 Width: 8.50 Depth: 11.02
Language: English
During plant operation, the walls of reactor pressure vessels (RPVs) are exposed to neutron radiation, resulting in localized embrittlement of the vessel steel and weld materials in the core area. If an embrittled RPV had an existing flaw of critical size and certain severe system transients were to occur, the flaw could very rapidly propagate through the vessel, resulting in a through-wall crack and challenging the integrity of the RPV. The severe transients of concern, known as pressurized thermal shock (PTS), are characterized by a rapid cooling (i.e., thermal shock) of the internal RPV surface in combination with repressurization of the RPV. Advancements in our understanding and knowledge of materials behavior, our ability to realistically model plant systems and operational characteristics, and our ability to better evaluate PTS transients to estimate loads on vessel walls led the U.S. Nuclear Regulatory Commission (NRC) to realize that the earlier analysis, conducted in the course of developing the PTS Rule in the 1980s, contained significant conservatisms.

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