Zircaloy-4 fuel pin failure under simulated loss-of-coolant-accident conditions: Oxygen embrittlement

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2024-10-13 DOI:10.1016/j.pnucene.2024.105485
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Abstract

An extensive experimental investigation was performed to study the oxygen embrittlement of the Indian Pressurized Heavy Water Reactor (PHWR) fuel pin under simulated Loss-of-Coolant Accident (LOCA) conditions. Zircaloy fuel cladding experiences creep and corrosion simultaneously during service and LOCA conditions. Zircaloy-4 fuel pins were pre-oxidized to attain different oxide layer thicknesses, achieving in-service conditions. These pre-oxidized tubes were then subjected to burst tests in the steam environment to mimic the LOCA scenario. The present study aims to improve the understanding of the effect of oxidation on the cladding microstructure and the mechanical response of the fuel pin in a LOCA scenario by accounting for the cross-influence, during transient heating, of oxidation and deformation on the behavior of the clad in the LOCA domain. The oxide layer morphology in pre- and post-burst samples was studied using FESEM, XRD, and Raman spectroscopy. In some cases, the inner oxide layer grew faster than the outer oxide layer when the fuel pin was heated in steam during the burst test. The evolution during transient heating of radial and circumferential crack growth in the oxide layer and the occurrence of delamination facilitated faster oxygen and hydrogen uptake. The hydrogen uptake in pre and post-burst samples was related to the oxygen uptake. The hydrogen concentration increases with the oxygen concentration in the pre-oxidized samples. Small oxygen and hydrogen concentrations were found in the post-burst as-received samples due to the formation of a protective oxide layer. The high-temperature oxide layer was formed at extremely high heating rates.

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Zircaloy-4 燃料销在模拟失壳事故条件下失效:氧脆性
为了研究印度压水重水反应堆(PHWR)燃料销在模拟失去冷却剂事故(LOCA)条件下的氧脆性,进行了广泛的实验研究。锆合金燃料包壳在使用和 LOCA 条件下同时经历蠕变和腐蚀。对 Zircaloy-4 燃料栓进行预氧化处理,以达到不同的氧化层厚度,从而实现在役条件。然后在蒸汽环境中对这些预氧化管进行爆裂试验,以模拟 LOCA 情况。本研究旨在通过考虑瞬态加热过程中氧化和变形对 LOCA 域中包层行为的交叉影响,加深对氧化对 LOCA 情景下包层微观结构和燃料引脚机械响应的影响的理解。使用 FESEM、XRD 和拉曼光谱对爆前和爆后样品中的氧化层形态进行了研究。在某些情况下,当爆燃试验期间燃料销在蒸汽中加热时,内部氧化层的生长速度快于外部氧化层。在瞬态加热过程中,氧化层径向和圆周裂纹的增长以及分层的发生都加快了氧气和氢气的吸收。爆破前和爆破后样品的氢吸收与氧吸收有关。在氧化前的样品中,氢浓度随氧浓度的增加而增加。由于形成了保护性氧化层,爆破后的样品中氧气和氢气浓度较小。高温氧化层是在极高的加热速率下形成的。
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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