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 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 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 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 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 88 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 Energy Research Abstracts written by and published by . This book was released on 1993 with total page 354 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Westinghouse owners group report reactor coolant pump seal performance following a loss of all ac power written by C. H. Campen and published by . This book was released on 1986 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of the Reactor Coolant Small Break PWR written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Thermal hydraulics of Nuclear Reactors written by Mati Merilo and published by . This book was released on 1983 with total page 760 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Publications of Los Alamos Research written by Los Alamos National Laboratory and published by . This book was released on 1984 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Analysis of a Four Inch Small break Loss of coolant Accident in a Westinghouse Pressurized Water Reactor Using TRAC PF1 MOD1 written by Kimberley I. R. Knippel and published by . This book was released on 1988 with total page 324 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Advanced Concepts In Nuclear Energy Risk Assessment And Management written by Tunc Aldemir and published by World Scientific. This book was released on 2018-04-25 with total page 554 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past 30 years, numerous concerns have been raised in the literature regarding the capability of static modeling approaches such as the event-tree (ET)/fault-tree (FT) methodology to adequately account for the impact of process/hardware/software/firmware/human interactions on nuclear power plant safety assessment, and methodologies to augment the ET/FT approach have been proposed. Often referred to as dynamic probabilistic risk/safety assessment (DPRA/DPSA) methodologies, which use a time-dependent phenomenological model of system evolution along with a model of its stochastic behavior to model for possible dependencies among failure events. The book contains a collection of papers that describe at existing plant level applicable DPRA/DPSA tools, as well as techniques that can be used to augment the ET/FT approach when needed.

Download or read book NUREG CR written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1980 with total page 854 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1983 with total page 974 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Title List of Documents Made Publicly Available written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1980 with total page 520 pages. Available in PDF, EPUB and Kindle. Book excerpt: