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Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results
STANDARD published on 1.6.2013
Designation standards: ASTM E853-13
Note: WITHDRAWN
Publication date standards: 1.6.2013
SKU: NS-48262
The number of pages: 9
Approximate weight : 27 g (0.06 lbs)
Country: American technical standard
Category: Technical standards ASTM
Keywords:
damage exposure parameter, dpa, embrittlement, LWR, pressure vessel, reactor surveillance, surveillance capsule, ICS Number Code 27.120.20 (Nuclear power plants. Safety)
Significance and Use | ||||||||||||||||||||||||||||||
3.1 The objectives of a reactor vessel surveillance program are twofold. The first requirement of the program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region resulting from exposure to neutron irradiation and the thermal environment. The second requirement is to make use of the data obtained from the surveillance program to determine the conditions under which the vessel can be operated throughout its service life. 3.1.1 To satisfy the first requirement of 3.1.2 To satisfy the second requirement of 3.2 The objectives and requirements of a reactor vessel's support structure's surveillance program are much less stringent, and at present, are limited to physics-dosimetry measurements through ex-vessel cavity monitoring coupled with the use of available test reactor metallurgical data to determine the condition of any support structure steels that might be subject to neutron induced property changes (1, 29, 44-58, 65-70). |
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1. Scope | ||||||||||||||||||||||||||||||
1.1 This practice covers the methodology, summarized in 1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods (see Master Matrix E706) 1.3 This practice is restricted to direct applications related to surveillance programs that are established in support of the operation, licensing, and regulation of LWR nuclear power plants. Procedures and data related to the analysis, interpretation, and application of test reactor results are addressed in Practice E1006, Guide E900, and Practice E1035. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. |
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2. Referenced Documents | ||||||||||||||||||||||||||||||
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Historical
1.11.2008
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1.1.2013
Historical
1.10.2010
Historical
1.10.2010
Historical
1.6.2009
Historical
1.10.2010
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