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IEEE 603 Trial-Use Standard Criteria for Safety Systems for Nuclear Power Generating Stations

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The Institute of Electrical and Electronics Engineers, Inc.

Trial-Use Standard Criteria for Safety Systems for Nuclear Power Generating Stations
 N 603

 

Annotation

 

The criteria contained in this standard establish minimum functional and design requirements for safety systems for nuclear power generating stations. The safety system is the collection of systems required to minimize the probability and magnitude of release of radioactive material to the environment by maintaining plant conditions within the allowable limits established for each design basis event. Safety system functional and design criteria are also contained in other standards.1

Illustration. Fig 1 illustrates the scope of the safety system.

Application

The safety system criteria established herein are to be applied to those systems required to protect the public health and safety by functioning to mitigate the consequences of design basis events. However, this standard does not necessarily apply to all of the safety related systems, structures, and equipment required for complete plant safety. The criteria herein are directed to the power, instrumentation, and control portions of the safety system. To safety these criteria, interface requirements may be imposed on the other portions of the system.

1 Refer to Refs [B1], [B2], [B1], [C1], [C2], [C3], [C4], [C8], [C9], and [C10] in Appendixes Band C.

 

Автоматический перевод:

 

Критерии стандарта испытательного использования систем безопасности для генераторных станций ядерной энергии

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