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Anticipated & Abnormal Plant Transients in Light Water Reactors by D Majumdar HC
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Libro que se ha leído pero que está en buen estado. Daños mínimos en la tapa, incluidas rozaduras, pero sin roturas ni agujeros. Es posible que no incluya sobrecubierta para tapas duras. Tapa muy poco desgastada. La mayoría de las páginas están en buen estado con muy pocas arrugas o roturas. El texto subrayado a lápiz es prácticamente inexistente, no hay texto resaltado ni anotaciones en los márgenes. No faltan páginas. Consulta el anuncio del vendedor para obtener más información y la descripción de cualquier posible imperfección.
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Recogida:
Recogida local gratis en Woburn, Massachusetts, Estados Unidos.
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USD4,40 (aprox. 3,77 EUR) USPS Media MailTM.
Ubicado en: Woburn, Massachusetts, Estados Unidos
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Entrega prevista entre el lun. 18 ago. y el sáb. 23 ago. a 94104
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N.º de artículo de eBay:395250648951
Características del artículo
- Estado
- ISBN
- 9780306417184
Acerca de este producto
Product Identifiers
Publisher
Springer
ISBN-10
0306417189
ISBN-13
9780306417184
eBay Product ID (ePID)
1200229
Product Key Features
Book Title
Anticipated and Abnormal Plant Transients in Light Water Reactors
Number of Pages
Xxviii, 724 Pages
Language
English
Publication Year
1984
Topic
Life Sciences / Botany, Power Resources / Nuclear
Illustrator
Yes
Genre
Technology & Engineering, Science
Format
Hardcover
Dimensions
Item Weight
52.7 Oz
Additional Product Features
Intended Audience
Trade
LCCN
84-013262
Dewey Edition
19
Number of Volumes
1 vol.
Dewey Decimal
621.48/35
Synopsis
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.", 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.
LC Classification Number
TK9001-9401
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