首页> 外文会议>American Nuclear Society;International Nuclear Fuel Cycle Conference;Light Water Reactor Fuel Performance Conference >MITIGATING THE EFFECTS OF BAFFLE-RELATED WEAR IN BABCOCK AND WILCOX NUCLEAR POWER REACTORS
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MITIGATING THE EFFECTS OF BAFFLE-RELATED WEAR IN BABCOCK AND WILCOX NUCLEAR POWER REACTORS

机译:减轻BABCOCK和WILCOX核动力反应器中与花篮有关的磨损的影响

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Baffle-related wear phenomena are a historicreliability concern in commercial nuclear power reactors.When Fuel Assemblies operate at the core periphery(adjacent to the core baffle or shroud), complex coreflows can cause such Fuel Assemblies to physicallycontact the baffle wall, which causes wear. This wear cannegatively affect both the Fuel Assembly structuralcomponents such as spacer grids, and the fuel rodcladding. The wear reduces performance margins and ithas led to fuel rod failures and prematurely shortenedFuel Assembly lifespan.While baffle-related wear is not a new industryphenomenon, evidence exists to suggest that as the coreinternals of commercial nuclear reactors age, theassociated risk to the reliability and performance of fuelcan also increase. To minimize this risk, fuel users haveadopted various mitigating design strategies. The mostcommon of these strategies is the pre-emptive armoring ofFuel Assemblies operating in known high wear corelocations with inert fuel rods. While effective in mitigatingthe potential for resulting fuel failures, such a strategycomes at a cost, both directly as well through a negativeimpact on fuel utilization.Framatome has been actively working with commercialnuclear customers to monitor the effects of baffle-wearand develop fuel solutions to mitigate the effects of baffleaging while minimizing the impact on fuel utilization. Incollaboration with Entergy, Framatome will be deployinglead PROtect Cr-cladding fuel rods at Arkansas NuclearOne, Unit 1 in 2019 that have been developed withincreased wear resistance. These fuel rods include a thincoating of chromium applied via physical vapordeposition to the underlying zirconium matrix of the fuelrod cladding, creating a highly adherent and wearresistantsurface that has been proven in out-of-piletesting. These wear-resistant rods are being placed instrategic locations within the reactor so as to operateadjacent to known high-wear baffle locations duringCycle 29 and 31. Poolside examinations of these rods areplanned to demonstrate their in-pile wear resistancefollowing 1 x and 3 x 18-month cycles of operation.
机译:与挡板有关的磨损现象是历史性的 商业核动力反应堆的可靠性问题。 当燃料组件在核心外围运行时 (与核心挡板或导流罩相邻),复杂的核心 流动会导致此类燃料组件物理上 接触挡板壁,导致磨损。这穿可以 对燃料组件的结构造成负面影响 隔离栅和燃油杆等组件 覆层。磨损会降低性能裕度,并且 导致燃料棒故障并过早缩短 燃料组件的使用寿命。 尽管与挡板相关的磨损不是新兴产业 现象,有证据表明该现象是核心 商用核反应堆的内部部件老化, 与燃料可靠性和性能相关的风险 也可以增加。为了最大程度地减少这种风险,燃料使用者 采用了各种缓解设计策略。最多 这些策略的共同点是先发制人的装甲 在已知高磨损芯中运行的燃料组件 带有惰性燃料棒的位置。虽然有效缓解 导致燃油故障的可能性,这种策略 通过负数直接或间接地付出代价 对燃料利用率的影响。 Framatome一直积极与商业合作 核客户监测挡板磨损的影响 并开发燃料解决方案以减轻挡板的影响 老化,同时将对燃油利用率的影响降至最低。在 与Entergy合作,将部署Framatome 阿肯色核电站的PROtect Cr包层燃料棒中的铅 一,与2019年一起开发的单元1 增加耐磨性。这些燃料棒包括一根细 通过物理蒸气施加的铬涂层 沉积到燃料的基本锆基中 杆面熔覆,具有高度的附着力和耐磨性 已在桩外被证明的表面 测试。这些耐磨棒被放置在 反应堆内的重要位置,以便运行 与已知的高磨损挡板位置相邻 循环29和31。 计划展示其桩内耐磨性 随后的1 x和3 x 18个月的运行周期。

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