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 perform...
Temperature gradient on the thick Reactor Pressure Vessel (RPV), caused by sudden overcooling events...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
The current federal regulations to insure that nuclear reactor pressure vessels (RPVs) maintain thei...
Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the...
This paper describes a NRC-sponsored research project formed to help confirm the technical basis for...
Graduation date: 2002Improved methods of determining temperature transients in reactor systems are \...
In the early 1980s, attention focused on the possibility that pressurized thermal shock (PTS) events...
In the early 1980s, attention focused on the possibility that pressurized thermal shock (PTS) events...
One of the key safety issues currently addressed by the Pressurized Water Reactor (PWR) industry is ...
The pressurized-thermal-shock (PTS) issue is concerned with the possibility of failure of pressurize...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...
Pacific Northwest Laboratory (PNL) provided a technical critique of the draft report, NRC Staff Eval...
The current federal regulations to insure that nuclear reactor pressure vessels (RPVs) maintain thei...
Commission (NRC) sponsorship a PWR main steam line break (MSLB) benchmark against coupled system the...
The pressurized thermal shock( PTS) event poses a potentially significant challenge to the structura...
Temperature gradient on the thick Reactor Pressure Vessel (RPV), caused by sudden overcooling events...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
The current federal regulations to insure that nuclear reactor pressure vessels (RPVs) maintain thei...
Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the...
This paper describes a NRC-sponsored research project formed to help confirm the technical basis for...
Graduation date: 2002Improved methods of determining temperature transients in reactor systems are \...
In the early 1980s, attention focused on the possibility that pressurized thermal shock (PTS) events...
In the early 1980s, attention focused on the possibility that pressurized thermal shock (PTS) events...
One of the key safety issues currently addressed by the Pressurized Water Reactor (PWR) industry is ...
The pressurized-thermal-shock (PTS) issue is concerned with the possibility of failure of pressurize...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...
Pacific Northwest Laboratory (PNL) provided a technical critique of the draft report, NRC Staff Eval...
The current federal regulations to insure that nuclear reactor pressure vessels (RPVs) maintain thei...
Commission (NRC) sponsorship a PWR main steam line break (MSLB) benchmark against coupled system the...
The pressurized thermal shock( PTS) event poses a potentially significant challenge to the structura...
Temperature gradient on the thick Reactor Pressure Vessel (RPV), caused by sudden overcooling events...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
The current federal regulations to insure that nuclear reactor pressure vessels (RPVs) maintain thei...