Quality assurance of PTS thermal hydraulic calculations at BNL. [Pressurized Thermal Shock] [electronic resource].
- Upton, N.Y. : Brookhaven National Laboratory, 1983.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 17 : digital, PDF file
- Additional Creators:
- Brookhaven National Laboratory
United States. Department of Energy. Office of Scientific and Technical Information
- Rapid cooling of the reactor pressure vessel at high pressure has a potential of challenging the vessel integrity. This phenomenon is called overcooling or Pressurized Thermal Shock (PTS). The Nuclear Regulatory Commission (NRC) has selected three plants representing three types of PWRs in use for detailed PTS study. Oconee-1 (B and W), Calvert Cliffs (C.E.), and H.B. Robinson (Westinghouse). The Brookhaven National Laboratory (BNL) has been requested by NRC to review and compare the input decks developed at LANL and INEL, and to compare and explain the differences between the common calculations performed at these two laboratories. However, for the transients that will be computed by only one laboratory, a consistency check will be performed. So far only Oconee-1 calculations have been reviewed at BNL, and the results are presented here.
- Published through SciTech Connect.
11. NRC water reactor safety research information meeting, Gaithersburg, MD, USA, 14 Oct 1983.
Saha, P.; Jo, J.; Rohatgi, U.S.; Pu, J.
- Funding Information:
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