Technical evaluation of RETS : required reports for Fort St. Vrain Nuclear Generating Station PDF Download
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Author: T. E. Young
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Languages : en
Pages : 0
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Author: T. E. Young
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Languages : en
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A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 6 refs.
Author: T. E. Young
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: T. E. Young
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: T. E. Young
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: T. E. Young
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: T. E. Young
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Category : Power resources
Languages : en
Pages : 586
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Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
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Languages : en
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The eight fuel test elements proposed for inclusion into Segment 7 (first reload) of the Fort St. Vrain Nuclear reactor are described. It also presents the results of the analysis of the effects of the test elements on plant normal operation and plant safety. Since the eight test elements represent a very small percentage of the core (0.4 percent), the analysis confirms that the test elements have a very small effect on the operation of the core underall conditions. The test elements will be manufactured from near-isotropic H-451 graphite in place of the needle-coke H-327 used in reference reload elements. This results in structurally stronger and superior heat transfer and dimensional change characteristics over the standard reload elements. One major difference between the test elements and the reference fuel is the use of ''cured-in-place'' fuel rods as opposed to the reference fuel rods which are cured prior to insertion into the fuel element. The new process has obvious manufacturing advantages, but also has performance advantages, e.g., improved thermal conductivity. Another difference is that several coated fuel variations which are potential alternatives for future FSV reloads or for application in large HTGRs have been included in the test. These include weak acid resin derived (WAR) TRISO fissile particles and TRISO and BISO oxide fertile particles. The fuel test element program is an important step towards the fullscale demonstration of safe and economic fuel and fuel element manufacturing technologies for the HTGR and will greatly increase the experimental data on the performance of HTGR fuel and graphite candidate materials under realistic power reactor operating conditions.
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Category : Power resources
Languages : en
Pages : 676
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