ASTM E560

1.1 This practice covers analytical and analytical-experimental approaches that can be used to determine the variation in neutron exposure (fluence E > 1.0 MeV, dpa, etc.) and exposure rate and energy spectrum between surveillance locations and points in the pressure vessel wall. Procedures for reporting the results of these analyses with assigned uncertainties are also suggested. This practice deals with the physics-dosimetry aspects of surveillance programs and must be used in conjunction with other Matrix E 706 standards to provide extrapolations based on metallurgical damage correlations.

1.2 The physics-dosimetry relationships determined from this practice may be used to estimate pressure vessel damage through application of Practice E 693 and Guide E 900 standards, using fluence (E > 1.0 MeV), dpa, or damage function derived exposure parameters as independent exposure variables. Supporting the application of these standards is E 944, E 1018, E 1005, and E 854 standards, identified in 2.1.

1.3 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

C859 Terminology Relating to Nuclear Materials
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E706 (IIIA)
E1006 Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E706 (II)
E1018 Guide for Application of the ASTM-evaluated Cross Section Data Files, E706 (IIB)
E1035 Practice for Determining Radiation Exposure for Nuclear Reactor Vessel Support Structures, E706 (IG)
E170 Terminology Relating to Radiation Measurements and Dosimetry
E184 Practice for Effects of High-Energy Neutron Radiation on the Mechanical Properties of Metallic Materials, E706 (IB)
E185 Practice for Conducting Surveillance Tests for Light Water-Cooled Nuclear Power Reactor Vessels, E706 (IF)
E2005 Guide for the Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields, E706 (IIE-1)
E2006 Guide for the Benchmark Testing of LWR Calculations, E706 (IIE-2)
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
E509 Guide for In-Service Annealing of Light-Water Cooled Nuclear Reactor Vessels
E636 Practice for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706 (ID)
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706 (0)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E706 (IIC)
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA)
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706 (IIIB)
E900 Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, E706 (IIF)
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)
E944 Guide for Application of Spectrum Adjustment Methods in Reactor Surveillance E706 (IIA)
Boiler and Pressure Vessel Code, Sections III and XI
Code of Federal Regulations, Chapter 10, Part 50, Appendixes G and H

Index Terms

ICS Number Code 27.120.10

Citing ASTM Standards

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