中文介紹,英文介紹,
中文介紹
WASH-1400是美國原子能委員會1975年發表的《核電站風險報告》，用了70人/年的工作量，耗資300萬美元，相當於建造一座1000兆瓦核電站投資的1%。
1974年美國原子能委員會在沒有核電站事故先例的情況下，套用系統安全工程分析方法，提出了著名的《核電站風險報告》（WASH-1400），並被以後發生的核電站事故所證實。
當前，大多數工業已開發國家已將安全評價作為工廠設計和選址、系統設計、工藝過程、事故預防措施及制訂應急計畫的重要依據。
英文介紹
Englisn Introduction
WASH-1400, '(The) Reactor Safety Study' was a report produced in 1975for the USNRCby a committee of specialists under Professor Norman Rasmussen. It is thus often referred to as the Rasmussen Report. It considered the course of events which might arise during a serious accident at a (then) large modern Light water reactor. It estimated the radiological consequences of these events, and the probability of their occurrence, using a fault tree/event tree approach. This technique is called Probabilistic Risk Assessment(PRA).
The report concluded that the risks to the individual posed by such stations were acceptably small, compared with other tolerable risks. Specifically, the report concluded that the probability of a complete core meltdown is about 1 in 20,000 per reactor per year.
The study was peer-reviewed by the 'Lewis Committee' in 1977, which broadly endorsed the methodology as the best available, but cautioned that the risk figures were subject to large uncertainty.
The methods used were comparatively simple and overly-pessimistic by today's standards, and based on early understanding of key phenomenology. Following a period of intensive (and expensive) research and discussion, inspired in part by Three Mile Island, WASH-1400 was replaced in due course first by NUREG-1150and now by a new study being performed by the Nuclear Regulatory Commission. Specific Studies were also made of two plants at Zion and Indian Point - the so called Z/IP Study.
The PRA methodology became generally followed as part of the safety-assessmentof all modern nuclear power plants. In the 1990s, all US nuclear power plants submitted PRAs to the NRC under the Individual Plant Examination program *, and five of these were the basis for the 1991 NUREG-1150.
WASH-1400 is now NUREG-75/014.
