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 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 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 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 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 Analysis of a Small break Loss of coolant Accident in a Pressurised Water Reactor written by Nikos C. Markatos 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 Analysis of a Small break Loss of coolant Accident in a Pressurised Water Reactor by the Laura Version of Phoenics written by Stephen M. Rawnsley and published by . This book was released on 1982 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Small Break Loss of Coolant Accident Analyses in Light Water Reactors written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1981 with total page 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 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 Anticipated and Abnormal Plant Transients in Light Water Reactors written by Pamela Lassahn and published by Springer Science & Business Media. This book was released on 2013-11-11 with total page 725 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the last 30 years, reactor safety technology has evolved not so much from a need to recover from accidents or incidents, but primarily from many groups in the nuclear community asking hypo thetical, searching (what if) ~uestions. This ~uestioning has indeed paid off in establishing preventive measures for many types of events and potential accidents. Conditions, such as reactivity excursions, large break, loss of coolant, core melt, and contain ment integrity loss, to name a few, were all at one time topics of protracted discussions on hypothesized events. Historically, many of these have become multiyear, large-scale research programs aimed at resolving the "what ifs. " For the topic of anticipated and abnormal plant transients, how ever, the searching ~uestions and the research were not so prolific until the mid-1970s. At that time, probabilistic risk methodolo gies began to tell us we should change our emphasis in reactor safety research and development and focus more on small pipe breaks and plant transients. Three Mile Island punctuated that message in 1979. The plant transient topic area is a multidisciplinary subject involving not only the nuclear, fluid flow, and heat transfer technologies, but also the synergistics of these with the reactor control systems, the safety s;,"stems, operator actions, maintenance and even management and the economic considerations of a given plant.
Download or read book The calculated Loss of coolant Accident written by L. J. Ybarrondo and published by . This book was released on 1972 with total page 106 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 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 Nuclear fuel behaviour in loss of coolant accident LOCA conditions written by and published by . This book was released on 2009 with total page 373 pages. Available in PDF, EPUB and Kindle. Book excerpt:
