ANS 19.6.1-2005
受压水反应堆用再填充启动物理试验

Reload Startup Physics Tests for Pressurized Water Reactors

ANS 19.6.1-2005 发布历史

This standard applies to the reactor physics tests that are performed following a refueling or other core alteration of a PWR for which nuclear design calculations are required. This standard does not address the physics test program for the initial core of a commercial PWR. This standard specifies the minimum acceptable startup reactor physics test program and acceptable test methods to determine if the operating characteristics of the core are consistentconsistent with the design predictions, which provides assurance that the core can be operated as designed. This standard 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!. This standard 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 and0or 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.

ANS 19.6.1-2005由美国核协会 US-ANS 发布于 2005-01-01。

ANS 19.6.1-2005 在中国标准分类中归属于: F69 核反应堆与核电厂核岛设备。

ANS 19.6.1-2005的历代版本如下：

• 1997年 ANS 19.6.1-1997
• 2005年01月01日 ANS 19.6.1-2005 受压水反应堆用再填充启动物理试验
• 2011年01月01日 ANS 19.6.1-2011 压水堆重新装料起动的物理试验

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标准号

ANS 19.6.1-2005

发布日期

2005年01月01日

实施日期

废止日期

无

中国标准分类号

F69

发布单位

US-ANS

代替标准

ANS 19.6.1-2011

适用范围

This standard applies to the reactor physics tests that are performed following a refueling or other core alteration of a PWR for which nuclear design calculations are required. This standard does not address the physics test program for the initial core of a commercial PWR. This standard specifies the minimum acceptable startup reactor physics test program and acceptable test methods to determine if the operating characteristics of the core are consistentconsistent with the design predictions, which provides assurance that the core can be operated as designed. This standard 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!. This standard 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 and0or 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.