Download or read book Analysis of Delayed Reactor Coolant Pump Trip During Small Loss of Coolant Accidents for Westinghouse Nuclear Steam Supply Systems written by Westinghouse Nuclear Energy Systems and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Generic Assessment of Delayed Reactor Coolant Pump Trip During Small Break Loss of coolant Accidents in Pressurized Water Reactors written by Brian Sheron and published by . This book was released on 1979 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Safety Evaluation Report Related to the Operation of Diablo Canyon Nuclear Power Station Units 1 and 2 Docket Nos 50 275 and 50 323 Pacific Gas and Electric Company written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1980 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Generic Evaluation of Feedwater Transients and Small Break Loss of coolant Accidents in Westinghouse designed Operating Plants written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force and published by . This book was released on 1980 with total page 692 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of the Reactor coolant Pumps During a Small break Loss of coolant Accident written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: TRAC-PD2 calculations indicate that more coolant mass remains in the system when the reactor coolant pumps are left in operation following a small cold-leg break. The analyses were performed for a Westinghouse plant (Zion-1) to help determine whether to trip the pumps at high-pressure injection initiation (the present operator directive), to trip the pumps at some later time in the transient, or to leave the pumps running indefinitely. The loop seals' behavior and the system refill characteristics primarily determined the results. 9 figures.
Download or read book Supplement No 4 to the Safety Evaluation Report by the Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission in the Matter of Public Service Electric and Gas Company Et Al Salem Nuclear Generating Station Unit 2 Docket No 50 311 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1980 with total page 514 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Generic Evaluation of Feedwater Transients and Small Break Loss of coolant Accidents in Combustion Engineering Designed Operating Plants written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force and published by . This book was released on 1980 with total page 364 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book News Releases written by and published by . This book was released on 1980 with total page 788 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effect of Reactor Coolant Pumps Following a Small Break in a Pressurized Water Reactor written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Small-break loss-of-coolant accidents were calculated to help determine whether to trip the reactor-coolant pumps early in the accident when the reactor scrams or to delay the pump trip (pump trip times ranged from 450 s to no trip at all). Four-in.-diam (approximate) cold-leg breaks in Babcock and Wilcox (B and W) and Westinghouse (W) pressurized-water reactors were investigated using the Transient Reactor Analysis Code, TRAC-PD2. The results indicated that for a 4-in.-diam cold-leg break the optimum mode of pump operation is design dependent. In terms of primary system mass depletion, the case with no pump trip was preferable for the W plant, whereas an early pump trip was preferable for the B and W plant. When the pumps were not operating in the W plant, the loop seals plugged with liquid, leading to a pressure buildup in the upper plenum and, consequently, a high liquid flow through the break. The vent valves in the B and W plant mitigated the consequences of the loop seals plugging; the effect was enough to favor an early pump trip.
Download or read book Report of the Bulletins and Orders Task Force written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force and published by . This book was released on 1980 with total page 1114 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Generic Evaluation of Small Break Loss of coolant Accident Behavior in Babcock Wilcox Design 177 FA Operating Plants written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force and published by . This book was released on 1980 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Leak Rate Analysis of the Westinghouse Reactor Coolant Pump written by T. Boardman and published by . This book was released on 1985 with total page 57 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Generic Evaluation of Feedwater Transients and Small Break Loss of coolant Accidents in GE designed Operating Plants and Near team Operating License Applications written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force and published by . This book was released on 1980 with total page 240 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Loss of feedwater Transients in PWRs written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent severe accident sequence analysis (SASA) work in LASL's Multifault Accident Analysis Section has focused on loss-of-feedwater (LOFW) transients at a 4-loop Westinghouse nuclear power reactor. In all transients studied, the initiator was loss of main feedwater and reactor coolant pump (RCP) trip, caused by temporary loss of off-site power. Subsequent automatic actions included reactor scram, closure of the main steam isolation valves, and initiation of auxiliary feedwater (AFW) flow. TRAC-PD2 calculations were designed to study the consequences of AFW delivery rates below the minimum specified in the emergency operating procedures (EOPs) for the reference 4-loop plant. Six types of LOFW scenarios have been studied, including (1) zero AFW availability (nominal case), (2) initially zero AFW but full recovery after 2 h, (3) zero AFW with steam generator (SG) atmospheric relief valve (ARV) malfunction, (4) zero AFW with high pressure charging flow initiated after 2 h, and (5) zero AFW with delay in reactor scram. Additional cases were considered to study the effects of uncertainties in pressurizer heater/spray operation, operator manual initiation of high pressure charging flow, reactor initial conditions, and RCP and power coastdown characteristics. Nominal case results, rationale for selections of other cases, and lessons learned are summarized.
Download or read book Effects of the Reactor Coolant Pumps Following a Small Break in a Westinghouse PWR written by Jan Elliott Koenig and published by . This book was released on 1983 with total page 57 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monthly Catalogue United States Public Documents written by and published by . This book was released on 1981 with total page 876 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 654 pages. Available in PDF, EPUB and Kindle. Book excerpt:
