首页> 外文会议>International Congress on Advances in Nuclear Power Plants >Estimate of Radiation-Induced Steel Embrittlement in the BWR Core Shroud and Vessel Wall from Reactor-Grade MOX/UOX Fuel for the Nuclear Power Plant at Laguna Verde, Veracruz, Mexico
【24h】

Estimate of Radiation-Induced Steel Embrittlement in the BWR Core Shroud and Vessel Wall from Reactor-Grade MOX/UOX Fuel for the Nuclear Power Plant at Laguna Verde, Veracruz, Mexico

机译:在Laguna Verde,Veracruz,墨西哥的核电站BWR核心护罩和血管壁上的辐射造成钢筋脆性钢筋脆性燃料件。

获取原文

摘要

The government of Mexico has expressed interest to utilize the Laguna Verde boiling water reactor (BWR) nuclear power plant for the disposition of reprocessed spent uranium oxide (UOX) fuel in the form of reactor-grade mixed-oxide (MOX) fuel. MOX fuel would replace spent UOX fuel as a fraction in the core from 18 - 30% depending on the fuel loading cycle. MOX fuel is expected to increase the neutron fluence, flux, fuel centerline temperature, reactor core pressure, and yield higher energy neutrons. There is concern that a core with a fraction of MOX fuel (i.e., increased ~(239)Pu wt%) would increase the radiation-induced steel embrittlement within the core shroud and vessel wall as compared to only conventional, enriched UOX fuel in the core. The evaluation of radiation-induced steel embrittlement within the core shroud and vessel wall is a concern because of the potentially adverse affect to personnel and public safety, environment, and operating life of the reactor. The primary conclusion of this research was that the addition of the maximum fraction of 1/3 MOX fuel to the LV1 BWR core did significantly accelerate the radiation-induced steel embitterment such that without mitigation of steel embitterment by periodic thermal annealing or reduction in operating parameters such as, neutron fluence, core temperature and pressure, it posed a potentially adverse affect to the personnel and public safety, environment, and operating life of the reactor.
机译:墨西哥政府表示利益利用LAGUNA VERDE沸水反应堆(BWR)核电站以以反应器级混合氧化物(MOX)燃料的形式进行后处理的废氧化铀(UOX)燃料。根据燃料载荷循环,MOX燃料将在18-30%的核心中取代花费UOX燃料作为核心的分数。预计MOX燃料将增加中子流量,助熔剂,燃料中心线温度,反应堆芯压力,并产生更高的能量中子。担心具有一部分MOX燃料的核心(即,增加〜(239)PU WT%)将增加核心护罩和血管壁内的辐射诱导的钢筋,与常规的富含UOX燃料相比核。在核心护罩和血管壁内的辐射诱导的钢筋的评估是一个问题,因为对人员和公共安全,环境和反应堆的操作寿命可能不利影响。本研究的主要结论是将1/3 Mox燃料的最大分数增加到LV1 BWR核心确实显着加速了辐射诱导的钢制压力机,使得通过定期热退火或减少操作参数减轻钢汞如中子流量,核心温度和压力,它对对抗器的人员和公共安全,环境和运营寿命构成了潜在的不利影响。

著录项

相似文献

  • 外文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号