Author: L. B. MarshPublisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages : 132
Book Description
Evaluation of Steam Generator Tube Rupture Events
Author: L. B. MarshPublisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages : 132
Book Description
Title List of Documents Made Publicly Available
Author: U.S. Nuclear Regulatory CommissionPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 580
Book Description
Federal Register
Author: Publisher:
ISBN:
Category : Delegated legislation
Languages : en
Pages : 484
Book Description
Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting
Author: Power Reactor Events
Author: Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 192
Book Description
Annual Report
Author: U.S. Nuclear Regulatory CommissionPublisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 454
Book Description
Anticipated and Abnormal Plant Transients in Light Water Reactors
Author: Pamela LassahnPublisher: Springer Science & Business Media
ISBN: 1468447998
Category : Technology & Engineering
Languages : en
Pages : 725
Book Description
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.
Guidebook to Light Water Reactor Safety Analysis
Author: P. B. AbramsonPublisher: CRC Press
ISBN: 9780891162629
Category : Technology & Engineering
Languages : en
Pages : 418
Book Description
The Guidebook to Light Water Reactor Safety Analysis brings together government and expert researchers entrusted with maintaining the safety of reactors, preventing incidents, and for creating the guidelines for responding appropriately to emergency situations. It includes an overview presented by the U.S. Nuclear Regulatory Commission. One of the most relevant compendiums of its time, it's a volume of both historical and scientific significance and well worth the consideration of those currently involved with maintaining reactor safety..
News Releases
Author: Probabilistic Safety Assessment of WWER440 Reactors
Author: Zoltan KovacsPublisher: Springer
ISBN: 3319085484
Category : Technology & Engineering
Languages : en
Pages : 323
Book Description
The aim of this book is to summarize probabilistic safety assessment (PSA) of nuclear power plants with WWER440 reactors and demonstrate that the plants are safe enough for producing energy even in light of the Fukushima accident. The book examines level 1 and 2 full power, low power and shutdown PSA, and summarizes the author’s experience gained during the last 35 years in this area. It provides useful examples taken from PSA training courses the author has lectured and organized by the International Atomic Energy Agency. Such training courses were organised in Argonne National Laboratory (Chicago, IL, USA), Abdus Salaam International Centre for Theoretical Physics (Trieste, Italy), Malaysia, Vietnam and Jordan to support experts from developing countries. The role of PSA for the plants is an estimation of the risks in absolute terms and in comparison with other risks of the technical and the natural world. Plant-specific PSAs are being prepared for the plants and being applied for detection of weaknesses, design improvement and backfitting, incident analysis, accident management, emergency preparedness, prioritization of research and development and to support the regulatory activities. There are three levels of PSA, being performed for full power and low power operation and shutdown operating modes of the plants: level 1, 2 and 3 PSA. The nuclear regulatory authorities do not require the level 3 PSA for the plants in the member countries of the European Union. This means that only a limited number of NPPs in Europe have the level 3 PSA available. However, in the light of the Fukushima accident the performance of such analyses is strongly recommended in the future. This book is intended for professionals working in the nuclear industry, researchers and students interested in safety of operational plants.