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Doplňujúce informácie

ASTM E1006-96

Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)

Automaticky preložený názov:

Štandardná prax pre analýzu a interpretáciu fyziky dozimetrie Výsledky pre reaktory na skúšanie, E 706 ( II )

NORMA vydaná dňa 1.1.1996

Jazyk
Prevedenie	Elektronické PDF - 68.00 € Tlačené - 68.00 €
Dostupnosť	SKLADOM
Cena	68.00 € bez DPH
68.00 €

Informácie o norme:

Označenie normy: ASTM E1006-96
Poznámka: NEPLATNÁ
Dátum vydania normy: 1.1.1996
Kód tovaru: NS-40109
Počet strán: 7
Približná hmotnosť: 21 g (0.05 libier)
Krajina: Americká technická norma
Kategória: Technické normy ASTM

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Otázka

Anotácia textu normy ASTM E1006-96 :

Keywords:
discrete ordinates, dosimetry, Monte Carlo, neutron exposure parameters, radiation transport, test reactor, ICS Number Code 17.240 (Radiation measurements)

Doplňujúce informácie

1. Scope

1.1 This practice covers the methodology summarized in Annex A 1 to be used in the analysis and interpretation of physics-dosimetry results from test reactors.

1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods that are in various stages of completion (see Matrix E 706).

1.3 Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, exposure units, and neutron spectrum adjustment methods.

1.4 This practice is directed towards the development and application of physics-dosimetry-metallurgical data obtained from test reactor irradiation experiments that are performed in support of the operation, licensing, and regulation of LWR nuclear power plants. It specifically addresses the physics-dosimetry aspects of the problem. Procedures related to the analysis, interpretation, and application of both test and power reactor physics-dosimetry-metallurgy results are addressed in Practices E 185, E 560, E 853, and E 1035, Matrix E 706(IE), Guide E 900, and Test Method E 646.

1.5 This standard may involve hazardous materials, operations, and equipment. 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.

2. Referenced Documents

E693-23	Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
E1018-20e1	Standard Guide for Application of ASTM Evaluated Cross Section Data File (Includes all amendments and changes 7/2/2020).
E646-16	Standard Test Method for Tensile Strain-Hardening Exponents (n -Values) of Metallic Sheet Materials
E482-22	Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
E900-21	Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
E2006-22	Standard Guide for Benchmark Testing of Light Water Reactor Calculations
E910-18	Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
E854-19	Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance
E853-23	Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
E944-19	Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1005-21	Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
E706-23	Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
E844-18	Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E2005-21	Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
E1035-18(2023)	Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
E185-21	Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

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