Anticipated and Abnormal Plant Transients in Light Water Reactors: Volume 1Pamela Lassahn, Debu Majumdar, George F. Brockett 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. |
Contents
BANQUET ADDRESS | 1 |
Assessment 963 | 13 |
Management of Plant Transients Opening Address | 15 |
Copyright | |
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Anticipated and Abnormal Plant Transients in Light Water Reactors, Volume 1 Pamela Lassahn No preview available - 2013 |
Common terms and phrases
accident analysis ATWS auxiliary feedwater auxiliary systems boiling water reactor boron calculated caused cold leg components condensation control room cooldown cooling decay heat downcomer effects Electric EPRI evaluation failure feedwater pump Figure flow rate fluid frequency heat removal hot leg HPCI incidents initiated INPO inventory isolation LOCA loop loss of offsite main feedwater main steam natural circulation nuclear power plant Nuclear Regulatory Commission occurred offsite power operating experience operational transients operator actions parameters performed plant data plant transients PORV power supply pressurized water reactor primary system procedures pump trip RCIC RCPs reactor coolant pumps reactor trip reactor vessel RELAP5 relief valve Report RETRAN risk safety injection safety valve scram secondary side sequence shutdown signal significant simulation small break station blackout steam generator tube steam line Taipower thermal shock thermal-hydraulic tube rupture turbine trip utilities