Standard Guide for Application of ASTM Evaluated Cross Section Data File,Matrix E706 (IIB)
适用范围：<p>The ENDF/B library in the United States and similar libraries elsewhere, such as JEF <span class="bold">(9)</span>, JENDL <span class="bold">(7)</span>, and BROND <span class="bold">(8)</span>, prov...
Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
适用范围：<p>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 corroborat...
Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics
适用范围：<p>Because of the wide variety of materials being used in neutron-activation measurements, this guide is presented with the objective of bringing improved uniformity to the specific field of interest h...
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance,E706 (IID)
适用范围：<p><span class="italic"><span class="italic">General</span>: </span> <p>The methodology recommended in this guide specifies criteria for validating computational methods and outlines procedures applica...
Standard Practice for Determining Neutron Fluence,Fluence Rate,and Spectra by Radioactivation Techniques
适用范围：<p><span class="italic"><span class="italic">Transmutation Processes</span>8212;</span>The effect on materials of bombardment by neutrons depends on the energy of the neutrons; therefore, it is importa...
Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
适用范围：<p>Prediction of neutron radiation effects to pressure vessel steels has long been a part of the design and operation of light water reactor power plants. Both the federal regulatory agencies (see 2.2)...
Standard Test Method for Nondestructive Assay of Nuclear Material in Scrap and Waste by Passive-Active Neutron Counting Using 252Cf Shuffler
适用范围：<p>This test method is used to determine the U and Pu content of scrap and waste in containers. Active measurement times have typically been 100 to 1000 s. Passive measurement times have typically been...
Standard Practice for Conducting Irradiations at Accelerator-Based Neutron Sources
适用范围：<p id="s00002">1.1 This practice covers procedures for irradiations at accelerator-based neutron sources. The discussion focuses on two types of sources, namely nearly monoenergetic 14-MeV neutrons fro...
Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance,E 706 (IIA)
适用范围：<p>Adjustment methods provide a means for combining the results of neutron transport calculations with neutron dosimetry measurements (see Test Method E 1005<astmref rid="a00021"> and NUREG/CR-5049) in...
Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results,E706(IA)
适用范围：<p>The objectives of a reactor vessel surveillance program are twofold. The first requirement of the program is to monitor changes in the fracture toughness properties of ferritic materials in the rea...
Standard Practice for Measurement of Mechanical Properties During Charged-Particle Irradiation
适用范围：<p id="s00002">1.1 This practice covers the performance of mechanical tests on materials being irradiated with charged particles. These tests are designed to simulate or provide understanding of, or bo...
Standard Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation
适用范围：<p>A characteristic advantage of charged-particle irradiation experiments is precise, individual, control over most of the important irradiation conditions such as dose, dose rate, temperature, and qua...
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