ASTM-E1006 › Historical Revision Information
Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
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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.
discrete ordinates; dosimetry; Monte Carlo; neutron exposure parameters; radiation transport; test reactor; ICS Number Code 17.240 (Radiation measurements)
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Oct. 31, 1988