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Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)
Automaticky preložený názov:
Štandardná prax pre analýzu a interpretáciu reaktora surveillance Ľahkovodné Výsledky, E706 ( IA )
NORMA vydaná dňa 10.6.2001
Označenie normy: ASTM E853-01(2008)
Poznámka: NEPLATNÁ
Dátum vydania normy: 10.6.2001
Kód tovaru: NS-48260
Počet strán: 7
Približná hmotnosť: 21 g (0.05 libier)
Krajina: Americká technická norma
Kategória: Technické normy ASTM
Keywords:
damage exposure parameter, dpa, embrittlement, LWR, pressure vessel, reactor surveillance, surveillance capsule, Dosimetry, Fracture testing--nuclear reactors, Neutron flux/fluence, Neutron radiation--nuclear materials/applications, Nuclear reactor vessels--light-water cooled, Nuclear reactor vessels--surveillance, Radiation exposure--nuclear materials/applications, ICS Number Code 27.120.20 (Nuclear power plants. Safety)
1. Scope | ||||||||||||||||||||||||||||||
1.1 This practice covers the methodology, summarized in , to be used in the analysis and interpretation of neutron exposure data obtained from LWR pressure vessel surveillance programs; and, based on the results of that analysis, establishes a formalism to be used to evaluate present and future condition of the pressure vessel and its support structures (1-70). 1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods (see Master Matrix E 706) (1, 15, 13, 48, 49 ). In order to make this practice at least partially self-contained, a moderate amount of discussion is provided in areas relating to ASTM and other documents. Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, and exposure units. Note 1—(Figure 1 is deleted in the latest update. The user is refered to Master Matrix E 706 for the latest figure of the standards interconnectivity).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 E 560, Practice E 1006, Guide E 900, and Practice E 1035. 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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