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Providing Effective International Safeguards for Light-water Small Modular Reactors

机译:为轻水小型模块化反应堆提供有效的国际保障

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The possibility of realizing Small Modular Reactors (SMRs) in the United States is increasing as the technology matures through the licensing process and inevitably is introduced to the nuclear energy market. As this technology is approved in the United States, a Nuclear Weapons (NW) State, certain nuclear safeguard differences must be taken into consideration if the technology were exported abroad to a Non-Nuclear Weapons (NNW) State that requires International Atomic Energy Agency (IAEA) oversight under the Nuclear Non-Proliferation Treaty (NPT). The concept of safeguards-by-design (SBD) has gained traction with new designs of conventional large reactors, however, the current light-water reactor SMRs that are most likely to get licensed have not mentioned taking into account SBD in their preliminary designs. Due to the modularity, fuel life, storage of spent fuel, and other attributes of these SMR designs, the conventional method of safeguarding light-water reactors must be rethought. This paper discusses these IAEA nuclear safeguards considerations for the specific category of light-water SMRs by taking into account the four major reactor designs being pushed through the Nuclear Regulatory Commission (NRC) and addressing the unique aspect of SMRs that can cause deviation from conventional IAEA inspection practices for light-water reactors. In particular, inspection and containment and surveillance requirements become stressed if multiple SMRs are located at one site with continuous refueling taking place in series from one reactor to the next. Some of these new designs are very compact making access to spent fuel pools or reactor vessel seals more difficult. Potential changes in either IAEA inspection regimes or recommendations on how to implement existing requirements are provided for the case of light-water SMRs under IAEA safeguards. These results must be evaluated closely in order for SMRs to be exported widely to other countries.
机译:随着技术在许可过程中的成熟以及不可避免地被引入核能市场,在美国实现小型模块化反应堆(SMR)的可能性正在增加。由于这项技术已在美国的核武器国家(NW)批准,因此,如果将该技术出口到需要国际原子能机构(NFA)的非核武器国家(NNW)国外,则必须考虑某些核保障差异。原子能机构)根据《不扩散核武器条约》(《不扩散核武器条约》)进行监督。设计保障措施(SBD)的概念已在常规大型反应堆的新设计中获得关注,但是,当前最有可能获得许可的轻水反应堆SMR在其初步设计中并未提及SBD。由于这些SMR设计的模块化,燃料寿命,乏燃料存储以及其他属性,因此必须重新考虑保护轻水反应堆的常规方法。本文通过考虑通过核监管委员会(NRC)推动的四项主要反应堆设计并解决可能导致与常规IAEA偏离的SMR的独特方面,讨论了针对轻水SMR特定类别的这些IAEA核保障考虑因素。轻水反应堆的检查方法。特别是,如果多个SMR位于一个地点,并且从一个反应堆到下一个反应堆连续加油,则检查,密闭和监视要求变得尤为重要。这些新设计中的某些非常紧凑,这使得进入乏燃料池或反应堆容器密封件的访问更加困难。对于在IAEA保障下的轻水SMR,提供了IAEA检查制度的潜在变化或关于如何执行现有要求的建议。为了使SMR广泛出口到其他国家,必须仔细评估这些结果。

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