1.1 本规程适用于以下剂量当量的计算: 133 核动力反应堆反应堆冷却剂中的氙来自所有惰性气体裂变产物的放射性。 1.2 以英寸-磅为单位的数值应视为标准值。括号中给出的值是到国际单位制的数学转换，仅供参考，不被视为标准值。 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 每个动力反应堆都有一个特定的DEX值，这是它们的技术要求极限。根据电厂通风孔的高度、现场边界的位置、计算出的1%燃料缺陷条件下的反应堆冷却剂活度以及归因于该特定电厂现场的一般大气建模，这些值可能在200到900μCi/g之间变化。 如果DEX测量的放射性超过技术要求极限，电厂将进入LCO，要求操作员对电厂运行采取行动。 5.2 DEX的测定与DEI测定中使用的方法类似，不同之处在于DEX的计算基于全身急性剂量，并考虑了惰性气体 8500万 韩国， 85 韩国， 87 韩国， 88 韩国， 1.31亿 Xe， 1.33亿 Xe， 133 Xe， 1.35亿 Xe， 135 Xe，和 138 Xe对全身剂量的贡献显著。 5.3 值得注意的是，此计算中仅包括裂变气体，并且仅包括 表1 . 例如 8300万 Kr不包括在内，即使其半衰期为1.86小时。其原因是，这种放射性核素无法通过伽马光谱法（32和9 keV的低能X射线）轻松确定，其剂量后果与其他更普遍的氪放射性核素相比非常小。 5.4 来自的活动 41 应收账， 19 F 16 N、 和 11 C、 所有这些在RCS中主要以气体形式存在，不包括在本计算中。 5.5 如果未检测到特定惰性气体放射性核素，则应假设其至少存在- 可检测活性。剂量当量Xe-133的测定应使用EPA第12号联邦指导报告表III.1中列出的空气浸泡的有效剂量转换系数进行， 3. 或ICRP出版物38（“放射性核素转换”）或类似来源中提供的平均γ衰变能量。

1.1 This practice applies to the calculation of the dose equivalent to 133 Xe in the reactor coolant of nuclear power reactors resulting from the radioactivity of all noble gas fission products. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered 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 Each power reactor has a specific DEX value that is their technical requirement limit. These values may vary from about 200 to about 900 μCi/g based upon the height of their plant vent, the location of the site boundary, the calculated reactor coolant activity for a condition of 1 % fuel defects, and general atmospheric modeling that is ascribed to that particular plant site. Should the DEX measured activity exceed the technical requirement limit, the plant enters an LCO requiring action on plant operation by the operators. 5.2 The determination of DEX is performed in a similar manner to that used in determining DEI, except that the calculation of DEX is based on the acute dose to the whole body and considers the noble gases 85m Kr, 85 Kr, 87 Kr, 88 Kr, 131m Xe, 133m Xe, 133 Xe, 135m Xe, 135 Xe, and 138 Xe which are significant in terms of contribution to whole body dose. 5.3 It is important to note that only fission gases are included in this calculation, and only the ones noted in Table 1 . For example 83m Kr is not included even though its half-life is 1.86 hours. The reason for this is that this radionuclide cannot be easily determined by gamma spectrometry (low energy X-rays at 32 and 9 keV) and its dose consequence is vanishingly small compared to the other, more prevalent krypton radionuclides. 5.4 Activity from 41 Ar, 19 F, 16 N, and 11 C, all of which predominantly will be in gaseous forms in the RCS, are not included in this calculation. 5.5 If a specific noble-gas radionuclide is not detected, it should be assumed to be present at the minimum-detectable activity. The determination of dose-equivalent Xe-133 shall be performed using effective dose-conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 3 or the average gamma-disintegration energies as provided in ICRP Publication 38 (“Radionuclide Transformations”) or similar source.