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现行 ASTM E2971-16(2020)
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Standard Test Method for Determination of Effective Boron-10 Areal Density in Aluminum Neutron Absorbers using Neutron Attenuation Measurements 使用中子衰减测量法测定铝中子吸收剂中有效硼-10面积密度的标准测试方法
发布日期: 2020-12-01
1.1 本试验方法旨在定量测定有效硼-10( 10 B) 面密度(单位面积的质量) 10 B、 通常以克计- 10 B/cm 2. )在铝中子吸收器中。将通过铝中子吸收器传输的热中子束的衰减与校准标准的衰减值进行比较,以确定有效辐射 10 B面积密度。该测试通常在实验室环境中进行。此方法仅在以下条件下有效: 1.1.1 吸收器包含 10 B在铝或铝合金基体中。 1.1.2 一次中子吸收器是 10 B 1.1.3 试样厚度均匀。 1.1.4 试样的测试表面积至少是热中子束表面横截面积的两倍。 1.1.5 均匀成分的校准标准跨越了测量的面密度范围。 1.1.6 面积密度在0.001和0.080克之间 10 B/cm 2. . 1.1.7 热化中子束来自裂变反应堆、亚临界组件、加速器或中子发生器。 1.2 以国际单位制表示的数值应视为标准值。本标准不包括其他计量单位。 1.3 本标准并非旨在解决与其使用相关的所有安全问题(如有)。本标准的用户有责任在使用前制定适当的安全、健康和环境实践,并确定监管限制的适用性。 1.4 本国际标准是根据世界贸易组织技术性贸易壁垒(TBT)委员会发布的《关于制定国际标准、指南和建议的原则的决定》中确立的国际公认标准化原则制定的。 ====意义和用途====== 5.1 本试验方法的典型用途是测定 10 B用于控制系统临界性的铝中子吸收体材料的面密度,例如:乏核燃料干式储存罐、转移/运输核燃料容器、乏核燃料池和新鲜核燃料运输容器。 5.2 面密度测量也用于研究 10 B空间分布。 5.3 本标准的预期用户包括设计人员、供应商、中子吸收器用户、测试实验室和核临界分析领域的顾问。 5.4 另一种已知方法用于确定 10 铝中子吸收器中的硼是实践中提到的一种分析化学方法 C1671 . 然而,分析化学方法不能测量“有效” 10 B中子衰减测量的面密度。
1.1 This test method is intended for quantitative determination of effective boron-10 ( 10 B) areal density (mass per area of 10 B, usually measured in grams- 10 B/cm 2 ) in aluminum neutron absorbers. The attenuation of a thermal neutron beam transmitted through an aluminum neutron absorber is compared to attenuation values for calibration standards allowing determination of the effective 10 B areal density. This test is typically performed in a laboratory setting. This method is valid only under the following conditions: 1.1.1 The absorber contains 10 B in an aluminum or aluminum alloy matrix. 1.1.2 The primary neutron absorber is 10 B. 1.1.3 The test specimen has uniform thickness. 1.1.4 The test specimen has a testing surface area at least twice that of the thermal neutron beam’s surface cross-sectional area. 1.1.5 The calibration standards of uniform composition span the range of areal densities being measured. 1.1.6 The areal density is between 0.001 and 0.080 grams of 10 B per cm 2 . 1.1.7 The thermalized neutron beam is derived from a fission reactor, sub-critical assembly, accelerator or neutron generator. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ====== 5.1 The typical use of this test method is determination of 10 B areal density in aluminum neutron absorber materials used to control criticality in systems such as: spent nuclear fuel dry storage canisters, transfer/transport nuclear fuel containers, spent nuclear fuel pools, and fresh nuclear fuel transport containers. 5.2 Areal density measurements are also used in the investigation of the uniformity in 10 B spatial distribution. 5.3 The expected users of this standard include designers, suppliers, neutron absorber users, testing labs, and consultants in the field of nuclear criticality analysis. 5.4 Another known method used to determine areal density of 10 B in aluminum neutron absorbers is an analytical chemical method as mentioned in Practice C1671 . However, the analytical chemical method does not measure the “effective” 10 B areal density as measured by neutron attenuation.
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归口单位: E07.05
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