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IAEA DESIGN INFORMATION VERIFICATION AUTHORITIES FOR SMALL MODULAR REACTORS: POTENTIAL CHALLENGES AND SOLUTIONS

机译:IAEA设计信息验证机构小型模块化反应堆:潜在的挑战和解决方案

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A key benefit of many small modular reactor(SMR) designs is the ability to construct majorreactor components in a factory setting forsubsequent onsite assembly. However, this approachcould pose challenges for International AtomicEnergy Agency (IAEA) design informationverification (DIV) activities. The IAEA conducts DIVat reactor construction sites in order to verify thatcomponents match the declared facility designsbefore they are fully integrated and becomeinaccessible to inspectors. It is through DIV that theIAEA can design a safeguards approach thateffectively addresses potential diversion and misusescenarios and confirm its continued adequacy overtime. Under Comprehensive Safeguards Agreements,the IAEA’s authority to conduct DIV adheres at“facilities,” defined by either the presence of nuclearmaterial in certain quantities or by certain functionalaspects irrespective of the presence of nuclearmaterial. Power reactors have traditionally beenconstructed and operated in the same location, whereDIV could be conducted throughout. For some SMRdesigns in development, however, certain reactorcomponents may be fully installed at a factory ratherthan the ultimate construction/operation site, raisingthe prospect that some SMRs may be manufactured,fueled, and/or operated in different locations, or evendifferent countries (with different safeguardsagreements and obligations). As a result, locationsother than an SMR’s final site of operation maybecome potentially significant for DIV, while it is asyetunclear whether or how the IAEA’s authority toconduct DIV extends to such locations, particularlyin international supply scenarios.These developments may require the IAEA toadapt the way that it interprets its legal authoritiesand conducts technical verification measures. Twoissues are particularly important. First, the NuclearNon-Proliferation Treaty (NPT) obligates only nonnuclearweapon states under its framework to acceptIAEA safeguards, which include access for IAEAdesign verification. This raises important questionsabout whether and how the IAEA might conduct DIVactivities for reactors being supplied by a nuclearweapon state to a non-nuclear weapon state. Second,certain IAEA verification authorities pertain tolocations that handle nuclear materials. For SMRfabrication sites where no nuclear materials will bepresent, inspectors may have to invoke a differentbasis for access than IAEA has used in the past, orpossibly contend with more limited access rights anda less robust toolkit to verify reactor designs.This paper reviews different safeguardsagreements (including INFCIRC/153 and the ModelAdditional Protocol) and discusses IAEA legalauthorities that may be relevant to DIV for smallmodular reactors. By considering different modes ofSMR construction, it identifies potential legal gaps orlimitations that may affect the IAEA’s ability toconduct rigorous design verification. It concludes bycommenting on the general steps to address any suchgaps, including legal and policy measures anddirections for future technical work.
机译:许多小模块化反应堆的一个关键优势(SMR)设计是构建专业的能力工厂设置中的反应器组件随后的现场装配。但是,这种方法可能对国际原子构成挑战能源机构(原子能机构)设计信息验证(DIV)活动。原子能机构的行为在反应堆施工现场,以验证这一点组件与声明的设施设计匹配在完全集成并成为之前检查员无法进入。它是通过div原子能机构可以设计保障措施的方法有效解决潜在的转移和滥用情景并确认其持续的充足性时间。根据综合保障协议,国际原子能机构的权威遵守“设施”,由核的存在定义以某种数量或某些功能的材料方面,无论核的存在如何材料。传统上是电力反应堆在同一地点构造和操作,在哪里div可以在整个过程中进行。对于一些SMR.然而,开发设计,某些反应堆组件可以在工厂完全安装比终极建筑/运营现场,提升一些SMR的前景可以制造,燃料,和/或在不同地点运行,甚至不同的国家(具有不同的保障措施协议和义务)。结果,位置除了SMR的最终运营现场之外对于div可能是潜在的重要意义,而它是asyet不清楚国际原子能机构的权力是如何行为Div延伸到这些地点,特别是在国际供应方案中。这些发展可能需要原子能机构适应它解释其法定权限的方式并进行技术验证措施。二问题尤为重要。一,核不扩散条约(NPT)仅义无核武器国家在其框架下接受IAEA保障措施,包括访问原子能机构设计验证。这提出了重要的问题关于是否以及原子能机构如何行动由核提供的反应堆的活动武器状态到非核武器状态。第二,某些原子能机构核查机构有关处理核材料的位置。对于SMR.没有核材料的制造网站目前,检查员可能需要调用不同的比IAEA过去使用的访问基础,或者可能争夺更多有限的访问权限和一个较稳健的工具包,可验证电抗器设计。本文评论了不同的保障措施协议(包括INFCIRC / 153和模型)附加方案)并讨论IAEA法律可能与小号有关的当局模块化反应器。通过考虑不同模式SMR建设,它识别潜在的合法差距或可能影响原子能机构的能力的限制进行严谨的设计验证。它结束了评论普遍措施来解决任何此类差距,包括法律和政策措施和未来技术工作的指示。

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