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Margin between safety and disaster concerned with nuclear power generation entities

机译：与核发电实体有关的安全与灾害之间的裕度

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摘要

The concern for nuclear power safety was initiated by the International Atomic Energy Agency (IAEA) about 12 years after World War Ⅱ. Within the commercial arena alone, the safety issues connected with nuclear power generation of electricity are already enormous. They can involve the interactive changes of the combined effects of technical, ecological, economical, social, and political. The heart of the nuclear power plant is the nuclear reactor that can be PWR, BWR, GMR (RBMK) and MSR. Safety operational regulations are presently concerned mostly with the PWR and BWR to which the US NRC coordinates with 14 other countries. As commendable as the tasks performed by the Nuclear Regulatory Commission (NRC) for the past 30 years and more, Codes & Standards (C&S) do age and amendments are necessary. This is especially true for those that require the support of hard core science and advanced technology. Advanced physical laws and computational schemes can enhanced the C&S. The revision, validation, and revalidation of the NRC-ASME &Ⅲ/XI codes, about 10 years ago under the VOCALIST program, however, have not lived up to their intention. The Elastic-Plastic Fracture Mechanics (EPFM) code as part of PVC (Pressure Vessel Code) lost credibility as the elastoplasticity-based J-Integral had no connection with the dislocation theories that were assumed to provide the theoretical mechanics foundation for elastoplasiticy. This hope vanished after the NRC C&S codes were prematurely installed. The possible use of multiple scaling were bypassed, since the 1990s. Certainly, nuclear power safety will not wait for NRC to recognize Multiscale Fracture Mechanics (MFM). Particularly vulnerable are the use of commercial black box programs based on mono-scale parameters such as the J-, C- and C~*-Integral for characterizing inherently dual- or multiscale-damage processes that are referred to as Elastic & Plastic (E&P), Creep & Fatigue (C&F), and Stress Corrosion Cracking (SCC). Future code development connected with the Liquid Salt Very High Temperature Reactor (LS-VHTR) cannot afford to disregard the life expectancy of the critical components for each scale range from nano to macro. The J- and C~*-Integral are mono-scale by definition. Their replacement by the Generalized Crack Extension Energy (GCEE) G can be accomplished simply by altering the specimen thickness, and loading rate for a given material using Multiscale Fracture Mechanics (MFM). The suggested approach is heuristic since adjustments are needed to remove the ambiguities in applying the J- and C~*-Integral. The global (load) energy transferred to the "crack tip " had to be measured correctly. This required a knowledge that the singularity point (absorbing-dissipating energy in tandem) can be assumed to characterize the phantom crack tip as inhaling and exhaling in breathing at the different spatial-temporal scales. Keep in mind that not all of the input energy is absorbed. Some can be dissipated. This mass pulsation behavior is described in the theory of "Crack Tip Mechanics" (CTM). The pulsation energy model was necessary for determination of the multiscale crack tip location. A consistent interpretation of the fracture mechanics test data was thus made possible. The mission of NRC envisioned by the Energy Reorganization Act (ERA) of 1974 was to oversee reactor safety and security, reactor licensing and renewal. While the choice of nuclear power plant (NNP) type is influenced by democracy, technocracy, and sciocracy, the rules governing nuclear safety, however, should follow hard core science and not decided by the expediency of the establishment. The Fukushima disaster has indeed pointed out the need to delineate these differences and to scrutinize the present system of administering and defining nuclear safety. Predicting the unpredictable stood out as a key issue. The need for a research operational group is apparent. It can be dubbed as "Think Tank for Nuclear Power Safety (TTNPS)" with the mission to translate theoretical concepts from formal economics and hard science into seemingly unquantifiable predictions. It is not unthinkable that the un-expectable can be converted to the expectable. Careful thought should be given to placing safety before cost or reducing cost at the expense of safety.
机译：第二次世界大战大约12年后，国际原子能机构（IAEA）发起了对核电安全的关注。仅在商业领域内，与核能发电相关的安全问题就已经十分巨大。它们可以涉及技术，生态，经济，社会和政治综合影响的互动变化。核电站的核心是核反应堆，可以是PWR，BWR，GMR（RBMK）和MSR。目前，安全操作法规主要涉及PWR和BWR，美国NRC与其他14个国家进行协调。值得赞扬的是，核监管委员会（NRC）在过去30多年中执行的任务中，《规范与标准》（C＆S）确实存在年龄并需要进行修订。对于那些需要硬核科学和先进技术支持的人来说尤其如此。先进的物理定律和计算方案可以增强C＆S。但是，大约在10年前的VOCALIST计划下，对NRC-ASME＆Ⅲ/ XI规范的修订，验证和重新验证还没有达到他们的意图。由于基于弹塑性的J积分与位错理论没有联系，因此作为PVC（压力容器规范）一部分的弹塑性断裂力学（EPFM）代码失去了可信度，后者被认为是为弹塑性提供了理论力学基础的位错理论。在过早安装了NRC C＆S代码后，这种希望就消失了。自1990年代以来，就不再使用可能的多重缩放。当然，核电安全不会等到NRC承认多尺度断裂力学（MFM）。尤其容易受到攻击的是使用基于单尺度参数（例如J-，C-和C〜* -Integral）的商业黑匣子程序来表征固有的双尺度或多尺度破坏过程，这些过程称为弹性与塑性（E＆P ），蠕变和疲劳（C＆F）和应力腐蚀开裂（SCC）。与液态盐超高温反应堆（LS-VHTR）相关的未来代码开发不能忽视从纳米级到宏观级各个尺度的关键组件的预期寿命。根据定义，J和C〜*积分是单尺度的。只需使用多尺度断裂力学（MFM）更改试样的厚度和给定材料的加载速率，即可用广义裂纹扩展能（GCEE）G代替它们。建议的方法是启发式的，因为需要进行调整以消除应用J-和C〜*积分时的歧义。必须正确测量传递到“裂纹尖端”的总（负载）能量。这就要求知道，可以假定奇点（串联吸收能量耗散能量）将幻像裂纹尖端表征为在不同的时空尺度下呼吸中的吸气和呼气。请记住，并非所有输入能量都会被吸收。有些可以消散。这种质量脉动行为在“裂纹尖端力学”（CTM）的理论中进行了描述。脉动能量模型对于确定多尺度裂纹尖端位置是必要的。因此，可以对断裂力学测试数据进行一致的解释。 1974年《能源重组法》（ERA）设想的NRC的任务是监督反应堆的安全和保障，反应堆的许可和更新。尽管核电厂类型的选择受民主，技术专制和社会民主制的影响，但是控制核安全的规则应遵循硬核科学，而不应由企业的权宜之计决定。福岛核灾确实指出需要描述这些分歧，并审查现行的管理和定义核安全制度。预测不可预测性是一个关键问题。显然需要一个研究业务小组。它可以被称为“核电安全智囊团（TTNPS）”，其使命是将形式经济学和硬科学的理论概念转化为看似无法量化的预测。不可思议的事物可以转化为期望的事物，这不是不可想象的。应谨慎考虑将安全放在成本之前，或以牺牲安全为代价降低成本。

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