ASTM E2005

This guide describes approaches for using neutron fields with well known characteristics to perform calibrations of neutron sensors, to intercompare different methods of dosimetry, and to corroborate procedures used to derive neutron field information from measurements of neutron sensor response.

This guide discusses only selected standard and reference neutron fields which are appropriate for benchmark testing of light-water reactor dosimetry. The Standard Fields considered are neutron source environments that closely approximate the unscattered neutron spectra from ²⁵²Cf spontaneous fission and ²³⁵U thermal neutron induced fission. These standard fields were chosen for their spectral similarity to the high energy region (E > 2 MeV) of reactor spectra. The various categories of benchmark fields are defined in Terminology E 170.

There are other well known neutron fields that have been designed to mockup special environments, such as pressure vessel mockups in which it is possible to make dosimetry measurements inside of the steel volume of the “vessel.” When such mockups are suitably characterized they are also referred to as benchmark fields. A variety of these engineering benchmark fields have been developed, or pressed into service, to improve the accuracy of neutron dosimetry measurement techniques. These special benchmark experiments are discussed in Guide E 2006, and in Refs (1)³ and (2).

1. Scope

1.1 This guide covers facilities and procedures for benchmarking neutron measurements and calculations. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to calibrate integral neutron sensors; the use of certified-neutron-fluence standards to calibrate radiometric counting equipment or to determine interlaboratory measurement consistency; development of special benchmark fields to test neutron transport calculations; use of well-known fission spectra to benchmark spectrum-averaged cross sections; and the use of benchmarked data and calculations to determine the uncertainties in derived neutron dosimetry results.

2. Referenced Documents

E1297 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
E170 Terminology Relating to Radiation Measurements and Dosimetry
E2006 Guide for Benchmark Testing of Light Water Reactor Calculations
E261 Practice for Determining Neutron Fluence Rate, and Spectra by Radioactivation Techniques
E263 Test Methods for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
E264 Test Methods for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
E265 Test Methods for Measuring Fast-Neutron Reaction Rates by Radioactivation of Sulfur-32
E266 Test Methods for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
E343 Test Methods for Measuring Reaction Rates by Analysis of Molybdenum 99 Activity from Fission Dosimeters
E393 Test Methods for Measuring Reaction Rates by Analysis of Barium-140 from Fission Dosimeters
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
E523 Test Methods for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
E526 Test Methods for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium
E704 Test Methods for Measuring Fast-Neutron Reaction Rates by Radioactivation of Uranium-238
E705 Test Methods for Measuring Fast-Neutron Reaction Rates by Radioactivation of Neptunium-237
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706 (IIIB)
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

Index Terms

activation dosimetry; benchmark neutron field; certified-neutron-fluence standards; fluence-transfer; neutron dosimetry; radiometric dosimetry; reference neutron field; standard neutron field; uncertainties; ICS Number Code 27.120.10

Citing ASTM Standards

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