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Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1

机译：韩国核电站1号反应堆压力容器的中子通量减少程序

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摘要

The objective of this work is to implement various fast neutron flux reduction programs on the beltline region of the reactor pressure vessel to reduce the increasing rate of reference temperature for pressurized thermal shock (RT_(PTS)) for Korea Nuclear Unit 1. A pressurized thermal shock (PTS) event is an event or transient in pressurized water reactors (PWRs) causing severe overcooling (thermal shock) concurrent with or followed by significant pressure in the reactor vessel. A PTS concern arises if one of these transients acts in the beltline region of a reactor vessel where a reduced fracture resistance exists because of neutron irradiation. Generally, the RT_(PTS) value is continuously increasing according to the fast neutron irradiation during the reactor operation, and it can reach the screening criterion prior to the expiration of the operating license. To reduce the increasing rate of RT_(PTS), various neutron flux reduction programs can be implemented, which are focused on license renewal. In this paper, neutron flux reduction programs, such as low leakage loading pattern strategy, loading of neutron absorber rods, and dummy fuel assembly loading are considered for Korea Nuclear Unit 1, of which the RT_(PTS) value of the leading material (circumferential weld) is going to reach the screening criterion in the near future. To evaluate the effects of the neutron flux reduction programs, plant and cycle specific forward neutron transport calculations for the various neutron flux reduction programs were carried out. For the analysis, all transport calculations were carried out by using the DORT 3.1 discrete ordinate code and BUGLE-96 cross-section library.
机译：这项工作的目的是在反应堆压力容器的传送带区域实施各种快速中子通量降低程序，以降低韩国核电站1的加压热冲击（RT_（PTS））的参考温度的上升速度。冲击（PTS）事件是压水反应堆（PWR）中的事件或瞬变，导致严重的过冷（热冲击），同时或随后在反应堆容器中产生巨大压力。如果这些瞬变之一作用于反应堆容器的腰线区域，在该区域中由于中子辐照而导致的抗裂性降低，就会出现PTS问题。通常，RT_（PTS）值在反应堆运行期间根据快速中子辐照而持续增加，并且可以在运行许可证到期之前达到筛选标准。为了降低RT_（PTS）的增加率，可以实施各种中子通量降低程序，这些程序着重于许可证的更新。在本文中，考虑了韩国核电站1的中子通量降低程序，例如低泄漏负荷模式策略，中子吸收棒的负荷以及虚拟燃料组件的负荷，其中前导材料的RT_（PTS）值（周向）焊缝）将在不久的将来达到筛选标准。为了评估中子通量减少程序的效果，针对各种中子通量减少程序进行了工厂和循环特定的正向中子输运计算。为了进行分析，所有运输计算均使用DORT 3.1离散纵坐标代码和BUGLE-96截面库进行。

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