Reactor Stability in the SPERT IV Facility PDF Download
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Author: J. G. Crocker
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 76
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Book Description
Author: J. G. Crocker
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 76
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Author:
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Category :
Languages : en
Pages :
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The Special Power Excursion Reactor Test IV (Spert IV) reactor is a swimming-pool type nuclear research reactor which was constructed to provide a facility for conducting reactor kinetic behavior and safety investigations especially in the field of reactor stability. The facility was designed to incorporate a wide range of flexibility in flow rates and direction of flow, and has a heat removal capacity of 1 Mw thermal in addition to the heal sink capacity of the reactor pools. The engineering features of the reactor and support ing process equipment as constructed at the National Reactor Testing Station are described. (auth).
Author: J. G. Crocker
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 102
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Author: F. L. Bentzen
Publisher:
ISBN:
Category : Nuclear reactor accidents
Languages : en
Pages : 74
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Author: United States. A.E.C. Idaho Operations Office
Publisher:
ISBN:
Category :
Languages : en
Pages : 7
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Author:
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Category :
Languages : en
Pages :
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Spert IV is a large pool-type experimental facility for reactor kinetic studies. These studies will include power excursion and instability tests for a variety of reactor designs. Since the Spert IV experimental program requires the performance of tests which will approach, and may exceed the threshold of reactor destruction, the probability of occurrence of the maximum possible accident is not negligible compared with that of other possible accidents. The maximum possible accident for this facility is considered to be a severe nuclear excursion which results in the destruction of the reactor building and the release of 100% of the accumulated fission product inventory of the atmosphere in a steam cloud. The fission product source assumed in the analysis of this accident is an upper limit in view of the nature of the tests to be performed and the heat removal capacity of the system. This postulated accident is independent of the details of core and control system design and is valid for all cores anticipated for use in the experimental program. The major hazards present in the operation of this facility, the precautions to be taken to reduce the probability of an accident, and the consequences of the maximum possible accident are discussed. It is concluded that the proposed method of operation will minimize the hazard to operating personnel, and that the site location will make possible the operation of the Spent IV facility without hazard to the general public. (auth).
Author:
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Category :
Languages : en
Pages :
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Author:
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Category :
Languages : en
Pages :
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The Spert IV facility, the initial critical experiment, the initial core, the operational core loading, and core parameter measurements (void and temperature coefficients, control rod worth, neutron flux distributions, etc.) made before initiation of the kinetics testing program are described. (auth).
Author: R. E. Heffner
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 152
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