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Haskin E., Camp L. Perspectives on Reactor Safety

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Haskin E., Camp L. Perspectives on Reactor Safety
Albuquerque: Sandia National Laboratories, NUREG/CR-6042, SAND93-0971, 1993. – 582 pp.
The U.S. Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. The course text is accompanied by slides and videos during the actual presentation of the course.
The US Nuclear Regulatory Commission (NRC) maintains a technical training center (TTC) at Chattanooga, Tennessee. This TTC is responsible for training and, in part, qualification programs for new employees and, at times, for retraining. Inasmuch as the agency hires about 150 new technical staff per year (due to turnover from retirement or other losses) there is a need to train these new employees for their NRC role. The entering staff have varied backgrounds: fresh from college or university; from Naval Reactors programs; from private industry. In all cases there are some training needs. However, the NRC must cope, in its training programs, with the nationwide deemphasis in nuclear power in the universities. Thus, we see in the incoming interns educational background in other areas, such as chemical or electrical engineering, or else degrees in mathematics or physics or chemistry. This shift in emphasis has placed an added burden on the TTC. In particular, it is seen that the most fundamental concepts in reactor safety, are not readily available to the college student as formal courses. Further, many of the present employees have not had the benefit of formal training in the bases for many of the regulations d.ealing with fundamental safety concepts. In this sense, fundamental concepts include: the design basis loss of coolant accident; the core melt assumptions which are embedded into the siting policy (Part 100); core melt progression and fission product release; fission product inventories and biological effects; atmospheric diffusion and transport; offsite effects; and, historical aspects of important rules such as station blackout.
This one-week course was developed to fill the gap in understanding of reactor safety concepts.
Contents.
Foreword.
Acknowledgements.
English to metric conversion factors.
Historical perspective.
Accident sequences.
Accident progression in the reactor vessel.
Accident progression in the containment.
Accident consequences and emergency plans.
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