Regulatory approaches in mitigating chemical degradation of zirconium alloys in the design and operation of light water reactors

P. Wiringgalih, Y. Pramono
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Abstract

Zirconium alloys are the materials of choice for nuclear fuel cladding due to low thermal neutron absorption, with excellent thermal and mechanical properties. As part of defence in depth concept, zirconium-based cladding shall be able to maintain its integrity and prevent the release of fission products to the reactor core. In particular, chemical degradation, due to corrosion, hydriding and pellet-cladding interaction, can compromise the fundamental safety functions of fuel cladding. Due to the risks of such chemical degradation of zirconium alloys, various countries undertake divergent regulatory approaches to ensure the integrity of fuel cladding. This research paper is the first attempt to review these regulatory approaches and to provide a technical basis for future regulation development for the safety of nuclear power plants. This research comprises of literature review of various factors that cause fuel failures in the operation of light water reactors as well as the prevalent international safety standards and regulations developed by several countries. Corrosion can cause oxide layer build-up that reduce heat transfer during accident condition. Excessive hydrogen uptake can cause embrittlement during loss-of-coolant accident. Pellet-cladding interaction causes fuel failure during normal operation of nuclear reactors. The research on chemical degradation of zirconium cladding remains intensive that continues to enhance the protection of fuel cladding. Based on the available knowledge in nuclear research community, the International Atomic Energy Agency (IAEA) has established international standards to ensure the highest reliability of fuel cladding, from operation to accident conditions. Regulatory bodies around the world aspire to adopt these internationally agreed standards. However, they also implement the national codes and standards in addition to these international standards that are relevant to their existing nuclear fleet. There is no unique regulatory approach in ensuring the integrity of fuel claddings from chemical degradation, but all reflect the strong commitment of the international community to the highest level of nuclear safety. Bapeten and other regulatory bodies need to review such varying regulatory approaches and adopt the most sensible and reliable regulatory regimes that are relevant to their domestic needs, circumstances, and capabilities.
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轻水反应堆设计和运行中减轻锆合金化学降解的调控方法
锆合金热中子吸收率低,具有优良的热学性能和力学性能,是核燃料包壳的首选材料。作为纵深防御概念的一部分,锆基包层应能够保持其完整性,并防止裂变产物向反应堆堆芯释放。特别是,由于腐蚀、氢化和颗粒包壳相互作用导致的化学降解会损害燃料包壳的基本安全功能。由于锆合金的这种化学降解的风险,各国采取不同的监管方法,以确保燃料包壳的完整性。本研究是对这些监管方法的首次尝试,旨在为未来核电厂安全监管的发展提供技术基础。本研究包括对轻水堆运行中导致燃料失效的各种因素的文献综述,以及一些国家制定的现行国际安全标准和法规。腐蚀会导致氧化层积聚,减少事故条件下的传热。在失去冷却剂事故中,过量的氢吸收会导致脆性。在核反应堆正常运行过程中,球团-包壳相互作用会导致燃料失效。对锆包壳化学降解的研究仍在深入进行,不断提高燃料包壳的防护能力。根据核研究界现有的知识,国际原子能机构(IAEA)制定了国际标准,以确保燃料包壳从运行到事故条件的最高可靠性。世界各地的监管机构都渴望采用这些国际商定的标准。然而,除了这些国际标准外,它们还执行与现有核舰队相关的国家规范和标准。在确保燃料包壳不受化学降解的完整性方面,没有独特的管理办法,但都反映了国际社会对最高水平核安全的坚定承诺。Bapeten和其他监管机构需要审查这些不同的监管方法,并采用与其国内需求、环境和能力相关的最明智、最可靠的监管制度。
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