ISO 18077:2018 对压水堆重新启动的物理测试

标准编号：ISO 18077:2018

中文名称：对压水堆重新启动的物理测试

英文名称：Reload startup physics tests for pressurized water reactors

发布日期：2018-03

标准范围

ISO 18077:2018适用于要求进行核设计计算的压水堆换料或其他堆芯改造后进行的反应堆物理试验。本文件不涉及商用压水堆初始堆芯的物理测试计划[1]。ISO 18077:2018规定了最低可接受启动反应堆物理试验程序，以确定堆芯的运行特性是否与设计预测一致，从而确保堆芯能够按设计运行。本文件不涉及运行期间反应堆物理参数的监督或其他要求的试验，如系统部件的机械试验（例如落棒时间试验）、燃料组件加载的目视验证要求，或仪器或控制系统的校准（尽管这些测试是确保堆芯按设计运行的整体计划的组成部分）。ISO 18077:2018假设在反应堆堆芯设计和启动试验预测中使用相同的先前接受的分析方法。它还假设堆芯的预期运行将在为电厂和/或姐妹电厂建立的历史数据库内。当核心设计发生重大变化时，应审查测试计划，以确定是否需要进行更广泛的测试。可能属于这一类别的典型变化包括新燃料循环设计的初始使用、燃料浓度的重大变化、燃料组件设计变化、可燃吸收体设计变化，以及计划外短循环导致的堆芯。此类变更可能导致在工厂经验数据库之外的区域运行，因此可能需要扩展测试程序。[1] 本文件中讨论的良好实践应考虑用于商业压水堆初始堆芯的物理测试计划。提供有用信息（无需额外测试时间）的一项测试是热零功率到热满功率的反应性测量。

ISO 18077:2018 applies to the reactor physics tests that are performed following a refuelling or other core alteration of a PWR for which nuclear design calculations are required. This document does not address the physics test program for the initial core of a commercial PWR[1].ISO 18077:2018 specifies the minimum acceptable startup reactor physics test program to determine if the operating characteristics of the core are consistent with the design predictions, which provides assurance that the core can be operated as designed. This document does not address surveillance of reactor physics parameters during operation or other required tests such as mechanical tests of system components (for example the rod drop time test), visual verification requirements for fuel assembly loading, or the calibration of instrumentation or control systems (even though these tests are an integral part of an overall program to ensure that the core behaves as designed).ISO 18077:2018 assumes that the same previously accepted analytical methods are used for both the design of the reactor core and the startup test predictions. It also assumes that the expected operation of the core will fall within the historical database established for the plant and/or sister plants.When major changes are made in the core design, the test program should be reviewed to determine if more extensive testing is needed. Typical changes that might fall in this category include the initial use of novel fuel cycle designs, significant changes in fuel enrichments, fuel assembly design changes, burnable absorber design changes, and cores resulting from unplanned short cycles. Changes such as these may lead to operation in regions outside of the plant's experience database and therefore may necessitate expanding the test program.[1] The good practices discussed in this document should be considered for use in the physics test program for the initial core of a commercial PWR. One test that provides useful information (without additional test time) is the hot-zero-power to hot-full-power reactivity measurement.

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