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Atomic energy has played an important role in international relations as a means of state power. From 1945 to 1959, Japan was significantly influenced by developments in atomic energy as a result of the Anglo-American "special relationship." During World War II, Britain and the United States cooperated to develop atomic weapons to use against Japan. In the ensuing Cold War era, the two countries advanced peaceful uses of atomic energy for Japan to counter the influence of the Soviet Union through psychological warfare. The U.S. Atomic Energy Peace Mission visited Japan in May 1955. However, the Japanese government altered its nuclear policy to solicit support from Britain because the United States was falling behind in atomic energy development. A British nuclear reactor was used as the first commercial nuclear power station, in 1959, whereby Britain earned parity with the United States in the context of nuclear power. [ABSTRACT FROM AUTHOR]

The nuclear‐contaminated water in the seawater near the site of the Fukushima nuclear power plant (NPP) accident is being investigated for treating the radioactive material. One of the most important considerations in the treatment is the management of the vast aquatic area of the oceanic scale. There are two methods in the application of osmosis and filtration for the modeling. There is the molecule quantity by the water volume where the list of transition of quantities is shown, where it decreases to 10% from the reversed osmosis method and to 0.01% from the filtration method in 9 days. In the filtrations, the discharge variations in the sea are described as the maximum and minimum values within 100 square velocities. A design for the general radioactive contaminated seawater treatment facility is introduced. [ABSTRACT FROM AUTHOR]

The concept and methodology of traditional Defense in Depth (DID) was challenged in the Fukushima nuclear accident. In order to fix the weakness of the traditional emergency strategies of nuclear power plants (NPPs) and to enhance the DID for nuclear safety, the U.S. Nuclear Energy Institute (NEI) put forward the concept of Diverse and Flexible Coping Strategies (FLEX) for the special purpose of beyond-design-basis external event (BDBEE) hazard mitigation and the corresponding FLEX support guidelines (FSG). The theory has been wildly spread and accepted by many countries that generate nuclear power. The research on the FLEX strategy is a new trend in nuclear engineering in the recent decade. It provides not only fixed on-site equipment/devices but also on- and off-site portable resources to strengthen the reliability of the nuclear safety system, especially for the disaster/hazards (similar to the Fukushima nuclear accident) triggered by BDBEEs. After a brief introduction of the FLEX strategy, four opportunities and ten challenges are summarized. Subsequently, in view of these challenges and technical difficulties, five suggestions for future work are recommended. [ABSTRACT FROM AUTHOR]

• Assessment of the acute and chronic exposure situations in a hypothetical accident of long term station black out at the proposed Buyende nuclear site in Uganda. • Total effective dose equivalents and thyroid dose at the exclusion are boundary and emergency protection zone were within the regulatory limits. Uganda's energy policy of 2023 and Vision 2040 plans to address the country's electricity shortage by introducing nuclear power of 24,000 MW capacity by 2040. The pioneer nuclear power plants with a generation capacity of 8,400 MW will be built in Buyende District. This study focused on assessing the radiological consequences of potential nuclear accident on any of the four technologies of APR1400, VVER1200, HPR1000, and APR1000. Evaluation of acute and chronic radiation effects from a long-term station blackout accident using RASCAL and GENII codes identified the order of minimum health risks to the public as APR100, HPR1000, VVER1200, and APR1400 if single units are constructed. The total effective dose equivalents and thyroid doses at the exclusion area boundary and emergency protection zone were within the regulatory limits of 250 mSv and 3,000 mSv, respectively for all the reactor technologies. [ABSTRACT FROM AUTHOR]

This paper's theme "Creative Robot Contest for Decommissioning (hereinafter, this Creative Robot Contest)" may be called a contest that would never have been planned in the absence of the Great East Japan Earthquake on March 11, 2011 and the core meltdown accident at Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company. When it was decided to decommission the nuclear reactors, their decommissioning was immediately put in hand, which, however, met with a high barrier of high radiation doses unconquerable even by the modern science and technologies. In order to advance the stagnating decommissioning work and in hopes of some creative breakthrough ideas from KOSEN students, this Robot Contest, first held in 2016, has been held by KOSEN teams who have shown their willingness to participate in it as a venue useful to address any difficulties they will face in the real world or as teaching material for them to consider social problems. This Robot Contest, sponsored by the Japan Atomic Energy Agency and the Council of Technical Colleges for Human Resource Development for Decommissioning, is planned and managed by the Executive Committee of Creative Robot Contest for Decommissioning (hereinafter, the Executive Committee) with its secretariat at National Institute of Technology, Fukushima College (hereinafter, Fukushima KOSEN) in Fukushima Prefecture where Fukushima Daiichi Nuclear Power Plant is located. In this paper, teachers at Osaka Metropolitan University College of Technology (hereinafter, Osaka Metropolitan University KOSEN) and at Nara National College of Technology, Nara College (hereinafter, Nara KOSEN), whose respective teams have participated in this Robot Contest every year from the first one, and teachers at Fukushima KOSEN who organize and manage the executive committee describe their own views on this Robot Contest based on their viewpoints as KOSEN educators. In the first half, this paper reviews this Robot Contest and outlines the robots of Osaka Metropolitan University KOSEN which participated in it in FY2016 and FY2017 and of Nara KOSEN which did in FY2016. In the latter half, this paper describes the views of the KOSEN teachers who educate engineers in the framework of robot contests from the viewpoints of the teachers who have instructed the teams of Osaka Metropolitan University KOSEN and Nara KOSEN who have participated in this Robot Contest up to the sixth one and who have held this Robot Contest. [ABSTRACT FROM AUTHOR]

After the Fukushima nuclear meltdown, the Angela Merkel government in Germany officially announced its decision to permanently shut down all of its seventeen nuclear reactors. In closer proximity to Fukushima, the Lee Myung-bak government in South Korea expanded its nuclear energy program with specific plans to construct more nuclear reactors in various locations and pursued more export opportunities. It was only in 2017 that the South Korean government, under President Moon Jae-in, announced a gradual phase-out of nuclear power plants in South Korea. What explains the contrasting paths of the German and South Korean nuclear energy programs in the immediate aftermath of the Fukushima nuclear disaster? Why did the same external shock prompt sudden policy reversal in Germany while it took six more years for South Korea to turn its course? While existing studies are helpful in accounting for the rise of particular energy policies, they are insufficient for explaining the causes and specific timing of major policy reversals in the face of external crises. Building upon the literature on political opportunity structures, this article argues that the emergence of new political opportunities and the shift in political framing with respect to nuclear energy caused nuclear phase-out in both countries. A closer look at the two national cases offers an opportunity to delineate the domestic political process of nuclear energy policymaking and evaluate the role of exogenous shocks, such as a major nuclear disaster, in shifting political opportunity structure and reshaping the perceptions of energy security and political risks. [ABSTRACT FROM AUTHOR]

This article argues that the history of nuclear energy can and should be analyzed as a history of water. Taking inspiration from David Edgerton's The Shock of the Old and recent efforts to merge the history of technology with environmental history, here the focus shifts from nuclear reactors to the "conventional" parts of nuclear power plants. This brings to the fore that a range of hydraulic technologies with long prehistories—pumps, pipes, valves, dams, dikes, and so on—have been crucially important for nuclear safety. The "atomic age" is fundamentally a hydraulic age and should be seen in relation to experiences gathered by past hydraulic civilizations. [ABSTRACT FROM AUTHOR]

After the Fukushima disaster, the authors analyzed all past core-melt accidents and estimated a failure rate of 1 per 3704 reactor years. This rate indicates that more than one such accident could occur somewhere in the world within the next decade. The authors also analyzed the role that learning from past accidents can play over time. This analysis showed few or no learning effects occurring, depending on the database used. Because the International Atomic Energy Agency (IAEA) has no publicly available list of nuclear accidents, the authors used data compiled by the Guardian newspaper and the energy researcher Benjamin Sovacool. The results suggest that there are likely to be more severe nuclear accidents than have been expected and support Charles Perrow's "normal accidents" theory that nuclear power reactors cannot be operated without major accidents. However, a more detailed analysis of nuclear accident probabilities needs more transparency from the IAEA. Public support for nuclear power cannot currently be based on full knowledge simply because important information is not available. [ABSTRACT FROM AUTHOR]

Summary: The Extensive Damage Mitigation Guideline (EDMG), which was developed by the U.S. Nuclear Energy Institute (NEI) owing to the motivation of 911 terrorist attacks and not allowed to spread before the Fukushima nuclear accident, was publicly available after Fukushima nuclear accident and paid attention to worldwide. Many countries have adopted the U.S. EDMG methodology and developed their strategies (some are not called EDMG but have similar functions), planning to introduce it into the emergency plans of their domestic nuclear power plants (NPPs). Based on the defense‐in‐depth (DID) concept of nuclear safety, the experience of the Fukushima nuclear accident, and the state‐of‐the‐art of EDMGs research, this paper will give a comprehensive review of EDMG. To illustrate the reason for the introduction of EDMG into the traditional NPP procedures/guidelines, the review work started from the perspective of DID in nuclear safety and the reason for the Fukushima nuclear accident from the viewpoint of DID, which showed the weaknesses of DID implementation strategy ‐ underestimation of the damage during a beyond‐design‐basis external event (BDBEE). EDMG is crucial complementary for the old framework of procedures/guidelines to enhance the concept of DID. The research progress of EDMG in different countries has been reviewed and a rough comparison has been made among them according to the present state‐of‐the‐art from literature. The methodology of EDMG is summarized as follows: (a) Loss of Large Area (LOLA) ‐ the originally designed scenario for EDMG; (b) elements of EDMG ‐ the summarized contents for EDMG implementation; (c) classification of EDMG ‐ initial response EDMGs and Technical Support Center (TSC) response EDMGs; (d) implementation of EDMG‐introduction of three phases of EDMG implementation step by step. Furthermore, three typical methods to integrate EDMG into the traditional procedures/guidelines are reviewed. Finally, this paper gives some concluding remarks for EDMG‐related critical issues and recommended future work, which may be challenges for the development and application of EDMG and useful for the related researchers. Novelty Statement: The studies of the extensive damage mitigation guideline (EDMG), its methodology, and the progress in different countries have been reviewed.Three typical methods to integrate EDMG into the traditional procedures/guidelines are summarized and reviewed.Concluding remarks for EDMG‐related critical issues and recommended future work are summarized. [ABSTRACT FROM AUTHOR]

Switzerland has long met a good portion of its energy needs by using nuclear power. But in the wake of the accident at Fukushima, the country will have to turn elsewhere—while still remaining true to its history of self-sufficiency and energy independence. This effort is made more complicated by fears that one of its traditional energy sources, hydropower, may no longer be as reliable as in the past. But with a combination of energy conservation, greater efficiencies, alternative energy sources, the “smart grid,” and the introduction of new technologies currently on the drawing board, the country may readily be able to replace the energy lost by the closing of its existing nuclear power plants. And the loss of the snowpack and glaciers (due to climate change) may not be as dire for Switzerland’s hydropower as first anticipated. [ABSTRACT FROM AUTHOR]

In response to a station blackout accident similar to the Fukushima nuclear accident, China's Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based on the two-phase natural circulation principle, the system is designed to bring out long-term core residual heat after an accident to ensure that the reactor is in a safe state. The steady-state characteristic test and transient start and run test of the PRS were carried out on the integrated experiment bench named ESPRIT. The experiment results show that the PRS can establish natural circulation and discharge residual heat of the first loop. China's Fuqing no. 5 nuclear power plant completed the installation of the PRS in September 2019 and carried out commissioning work in October. This debugging is the first real-world debugging of the new design. This paper introduces the design process of the PRS debugging scheme. [ABSTRACT FROM AUTHOR]

• A Phenomena Identification and Ranking Table (PIRT) dedicated to spent-fuel-pool-related accidents; • Eighteen unique phenomena identified as having priority research needs; • About half of these phenomena are related to thermal-hydraulics and heat transfer; • The other half comprises fuel-related phenomena such as fuel volatilization, cladding oxidation in mixed steam–air environment and nitrogen-assisted oxide breakaway at moderate temperature. Motivated by the 2011 accident at the Fukushima Daiichi Nuclear Power Station, the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) of the Organisation for Economic Cooperation and Development (OECD) launched several activities with the aim to support the post-Fukushima accident decision making process. One of these activities, discussed in the present paper, consisted in the production of a Phenomena Identification and Ranking Table (PIRT) in order to systematically highlight Spent-Fuel-Pool (SFP) accident-related phenomena that are of both high importance and high uncertainty, and thus of primary interest for further experimental or modeling activities. For that purpose, an international panel of experts identified and ranked more than a hundred physical phenomena with regard to their safety importance and current level of knowledge. Altogether eighteen unique phenomena were identified as having priority research needs. About half of these phenomena are related to thermal-hydraulics and heat transfer in the SFP, and they are judged to be important to the coolability of the spent fuel in loss-of-cooling and/or loss-of-coolant accidents. The other half comprises fuel-related phenomena such as fuel volatilization, cladding oxidation in mixed steam–air environment and nitrogen-assisted oxide breakaway at moderate temperature, judged as important and poorly modeled in the scope of SFP accidents. The final part of the paper discusses the research programmes performed on Spent Fuel Pool loss-of-cooling and loss-of-coolant accidents since the publication of the PIRT report in 2018 and the remaining R&D needs. [ABSTRACT FROM AUTHOR]

The study has been carried out to measure the activity concentration of natural and anthropogenic radionuclides in fifteen(15) soil samples of Natore, Kushtia and Pabna district, which are around the 30 km peripheral area of Rooppur Nuclear Power Plant, by gamma ray spectrometry system using a High Purity Germanium (HPGe) detector. It is found that the activity concentration of 226Ra, in the collected sample was from 3.52 Bq/kg to 28.5 Bq/kg with the average value of 12.42 Bq/kg. For 232Th, the range was from 4.18 Bq/kg to 34.5 Bq/kg with the average value of 12.6 Bq/kg. Finally, the activity concentration of 40K, in the collected sample was in the range of 84 Bq/kg to 345 Bq/kg, and the average value was 198.9 Bq/kg. The absorbed dose rate (D) was found to be in the range of 4.59 nGy/h to 40.93 nGy/h with the mean value 21.3 nGy/h. The annual effective dose (E) was in the range of 0.006 mSv/yr to 0.152 mSv/yr with an average of 0.033 mSv/yr. The radium equivalent activity was in the range from 10.02 Bq/kg to 89 Bq/kg with an average of 44.99 Bq/kg. The external hazard index (Hex) was found to be in the range of 0.027 to 0.242 with the mean value of 0.121 and the internal hazard index (Hin) was found to be in the range of 0.044 to 0.302 with the mean value of 0.156. All the values are much below the recommended limit by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 35 Bq/kg for 226Ra, 30 Bq/kg for 232Th and 400 Bq/kg for 40K. According to international and national regulation, the annual dose to members of the public, 1 mSvy-1 and Hex & Hin must be lower than unity. Moreover, no artificial radioactivity was found in the soil samples of this study area. This research concludes that the found values are within the permissible limits as required by the Nuclear Safety and Radiation Control(NSRC) Rules-1997 of Bangladesh and International Atomic Energy Agency(IAEA) Safety Standards- General Safety Requirements (GSR): Part-3. [ABSTRACT FROM AUTHOR]

South Korea's energy policy has been historically established through an energy production structure that relies on thermal and nuclear power generation in relation to a centralized 'Hard Energy System'. However, climate change issues are forcing the transition to renewable energy, and it is crucial for local governments to enable this. This study analyses Seoul city's local energy governance, which is known as One Less Nuclear Power Plant Initiative, by applying the collaborative governance framework inspired by Ansell and Gash (2008) and the Reflexivity framework of Confucianism. It is considered that the local energy governance model of Seoul city can be used as a model by other local governments, and it will eventually lead to a decentralized energy system in this era of energy transition. [ABSTRACT FROM AUTHOR]

In this paper, we extensively review the status and projection of the Filtered Containment Venting Systems (FCVSs) in the Nuclear Power Plants (NPPs) in Asia. As an important strategy to mitigate the Severe Accidents (SAs) in NPPs, FCVS is designed to prevent the containment overpressure failure by providing containment venting through a filtration system. The 2011 Fukushima Daiichi nuclear accident brought a negative impact to the public faith on the nuclear safety, the accident has led regulatory authorities and policy makers to re-evaluate safety criteria and reinforce safety supervision. As a result, the mitigation of SAs regains attention of nuclear community. Many investigation and research works were initialized or resumed, particularly about the enhancement of FCVS on robustness and filtration efficiency. Presently, Asia is a region where nuclear energy grow fast. To ensure nuclear safety, the FCVS is being taken into account in the SA mitigation strategy by regulatory authorities. Chinese nuclear safety administration requires NPPs to have adequate and reliable containment venting system. Thus FCVS is either equipped or about to be equipped on most reactors operating or under construction in China. Nuclear companies and research institutions are conducting research and engineering works about FCVS design and function. In South Korea, a government funded project was carried out during 2013–2017, aimed to design a domestic FCVS technology. Confirmatory tests have been performed to evaluate the function of designed FCVS. In Japan, Tokyo Electric Power Company started installing FCVS on the NPPs since 2013. Related research work is performing in Japanese universities and institutions. Taiwan’s Atomic Energy Council also requests utility companies to reexamine the present emergency operation procedures and study the strategies such as the addition of required facilities for SA prevention and mitigation in each NPP. It is noticed that India is also investigating the options to mitigate the SAs, including FCVS. [ABSTRACT FROM AUTHOR]

• DEC safety evaluations. • Challenging issues for DEC assessements. Safety Criteria for DEC Analyses. Experiments for Computational tools validation. After the Fukushima-Daiichi accident, the need to consider safety analyses under design extension conditions of the nuclear power installations has largely increased. The objective is to reassess and investigate the possibilities of the current nuclear installations to withstand accidental conditions that were not originally covered by the design basis accident. In Belgium, new regulation introduces the Design Extension Conditions (DEC) in the requirements for the design and operation of nuclear power plants. The purpose is to assess the safety of the current operating nuclear power installations and to identify design improvements, procedural measures and additional practicable provisions or mitigation means that could be used to prevent severe accidents. This paper provides a brief overview of the issues and challenges related to DEC safety evaluations in Belgium for the Licensee and also for the Safety Authority. [ABSTRACT FROM AUTHOR]

The article presents the statistical analysis of the impact of the 2011 Fukushima nuclear disaster on the German program of Energy Transition. It argues that the spectacular growth of renewable energy production in recent years was triggered not only by the increasing subsidies but also by the decision to phase out the nuclear power plants. However, the results seem to be far from what was desired by the architects of the Energy Transition. Except for 2014, the share of high-emission combustible fossils in the energy mix was growing. Meanwhile, the role of the two “transition fuels” (natural gas and nuclear energy) significantly decreased. The article also shows how the media, news, and communication in the modern world can seriously impact the economic policy of a state. It concludes that the decision made by the German government was largely irrational (except for electoral considerations) and it resulted in significant financial consequences. [ABSTRACT FROM AUTHOR]

Research Expert Committee on Evaluation of Severe Accident of AESJ (Atomic Energy Society of Japan) has developed thermal hydraulic PIRT (Phenomena Identification and Ranking Table) and source term (ST) PIRT based on findings during the Fukushima Daiichi NPPs accident. These PIRTs aim to explore the debris distribution and the current condition in the NPPs with high accuracy and to extract higher priority from the aspect of the sophistication of the analytical technology to predict the severe accident phenomena by the analytical codes. The ST PIRT is divided into 3 phases for time domain and 9 categories for spatial domain. The 68 phenomena have been extracted and the importance from the viewpoint of the source term has been ranked through brainstorming and discussions among experts. The present paper describes the developed ST PIRT list and summarizes the high ranked phenomena in each phase. [ABSTRACT FROM AUTHOR]

The Fukushima accident was clearly an accident made by humans and not caused by natural phenomena as was initially thought. Vulnerabilities were known by both regulators and operator but they postponed measures. The emergency plan was not effective in protecting the public, because the involved parties were not sufficiently prepared to make the right decisions. The shortcomings and faults mentioned above resulted from the lack of independence and transparency of the regulatory body. Even laws and regulations, and technical standards, have not been upgraded to international standards. Regulators have not defined requirements and left for the operator to decide what would be more appropriate. In this aspect, there was clearly a lack of independence between these bodies and operator’s lobby power. The above situation raised the question of urgent updating of institutions, in particular those responsible for nuclear safety. The above evidences show that several nuclear safety principles were not followed. This paper intends to highlight some existing safety criteria that were developed from the operational experience of the severe accidents that occurred at TMI and Chernobyl that should be incorporated in the design of new nuclear power plants and to provide appropriate design changes (backfittings) for reactors that belong to the previous generation prior to the occurrence of these accidents, through the study of design vulnerabilities. Furthermore, the main criteria that define an effective regulatory agency are also discussed. Although these criteria appear in IAEA guides and requirements, this paper proposes that some of these requirements should be more detailed in line with what has been learned as the most important lessons of Fukushima in order to prevent organizational failures. [ABSTRACT FROM AUTHOR]

In 2009, Japan pledged to reduce its GHG emissions by 25% from 1990 levels by 2020 (“Copenhagen Pledge”). The achievement of the target depended largely on a large expansion of nuclear power. However, this ambitious plan became unfeasible after the Fukushima nuclear disaster of March 2011. This paper conducted a comprehensive review of Japan’s recent energy and climate policy developments since 2009 and particularly after March 2011 to assess where Japan stands today with regard to the achievement of the long-term global 2 °C goal. Japan achieved its mitigation target for the first commitment period of the Kyoto Protocol, but it was unsuccessful in reducing domestic GHG emissions in the residential and commercial sectors, and consequently relied more heavily on purchased Kyoto units. With regard to the revised 2020 mitigation target (“Warsaw Target”), when expected emissions reductions through nuclear power is factored out, domestic mitigation under the Warsaw Target was found to be only marginally more ambitious than the target that preceded the Copenhagen Pledge (9% reduction from 1990 levels). Japan cannot make secondary acquisitions of Kyoto units up to 2020 and thus, a bilateral offset scheme (JCM) could become an important credit source. However, its development regarding the additionality of the emissions reductions needs to be tracked carefully. Moreover, the legal underpinning of national mitigation targets and actions was currently found to be very weak in Japan. The review of currently implemented policy measures revealed that among the three key measures considered for achieving the Copenhagen Pledge, only the renewable Feed-In-Tariff scheme was found to be relatively successful to date, but even this is currently under critical scrutiny. Recent new coal-fired power plant construction plans could jeopardize the achievement of both mid-term and long-term mitigation goals. The impact of nuclear power plant restarts on future CO 2 emissions was found to be limited around 2030. [ABSTRACT FROM AUTHOR]

KAERI (Korea Atomic Energy Research Institute) will launch an OECD/NEA project by utilizing a thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) from April, 2014. In the OECD-ATLAS project, design extension conditions (DECs) such as a station blackout (SBO) and a total loss of feed water (TLOFW) will be experimentally investigated to identify the major thermal-hydraulic phenomena of high risk multiple failure accidents considering magnified safety concerns after the Fukushima accident. A SBO is one of the most important DECs in that without any proper operator actions, a total loss of heat sink leads to core uncover, to core damage, and ultimately a core melt-down scenario under high pressure. Due to this safety importance, a SBO is considered to be a base test item of the OECD-ATLAS project. In this study, a phenomena identification ranking table (PIRT) has been developed for identifying the major parameters affecting the thermal-hydraulic phenomena in SBO transients. Development of a PIRT for the SBO transients is expected to contribute to making strategy for performing a thermal-hydraulic integral effect test with ATLAS which includes determination of proper test conditions and improvement of measurements. The primary safety criterion (PSC) was determined to be the core mixture level from the expert panel discussion. As for the major components of the nuclear power plant, the rank of the importance and the knowledge level were summarized for each of the three temporal phases. Taking into account the important phenomena from the PIRT result, it can be confirmed that ATLAS has a capability of simulating the major thermal-hydraulic phenomena during a SBO transient as realistically as possible. The present PIRT will be directly used to make strategy for performing a thermal-hydraulic integral effect test with ATLAS in the framework of the OECD-ATLAS project. [ABSTRACT FROM AUTHOR]

After the nuclear disaster in Fukushima in Japan in 2011, a nation-wide survey using a standardized self-administered questionnaire was conducted in Taiwan, with a sample size of 2,742 individuals including the residents who live within and beyond 30 km from a nuclear power plant (NPP), to evaluate the participants’ perceived nuclear risk in comparison with their perceived risks from selected environmental hazards and human behaviors. The three leading concerns of nuclear energy were “nuclear accidents (82.2%),” “radioactive nuclear waste disposal (76.9%)” and “potential health effects (73.3%).” Respondents (77.6%) perceived a higher relative risk of cancer incidence for those who live within 30 km from an NPP than those who live outside 30 km from an NPP. All the participants had a higher risk perception of death related to “nuclear power operation and nuclear waste” than cigarette smoking, motorcycling, food poisoning, plasticizer poisoning and traveling by air. Moreover, the residents in Gongliao where the planned fourth NPP is located had a significantly higher perceived risk ratio (PRR) of cancer incidence (adjusted odd ratio (aOR) = 1.84, p value = 0.017) and perceived risk of death (aOR = 4.03, p value < 0.001) related to nuclear energy. The other factors such as female gender (aOR/ p value, 1.25/0.026 and 1.34/0.001 respectively), lower education levels (aOR/ p value: 1.31/0.032; 2.03/< 0.001) and the participants’ concerns about nuclear accidents (aOR/ p value: 1.33/0.022; 1.51/< 0.001) and potential health effects (aOR/ p value: 2.95/ < 0.001; 2.56/< 0.001) were found to be commonly associated with the PRRs of “cancer incidence” and “perceived risk of death” related to nuclear energy, respectively. In addition, the respondents’ concerns about nuclear waste disposal and possible eco-environmental damage made significant contributions (aOR/ p value: 1.39/ 0.001; 1.40/< 0.001) to predict their perceived risk of death related to nuclear power. These factors are considered as important indicators and they can be used for suggesting future policy amendments and public referendum on the decision of the operation of the planned NPP. [ABSTRACT FROM AUTHOR]

This paper draws upon perspectives on legal personhood, expert knowledge-practices, and social relations influential in STS and anthropology to revisit the legal-procedural framing of the United States' now-defunct high-level nuclear waste repository project at Yucca Mountain. Specifically, it examines how this project reinvented both (a) conventional figures of legal personhood as what is called a 'reasonably maximally exposed individual' and (b) legal adjudication's familiar 'rule-facts-judge' template as a frame for establishing the repository licensing regime's delegation of roles, responsibilities, and duties in response to its unique regulatory horizons that extended millennia into the future. Unpacking the implications of these familiar legal figures being brought to bear on historically unprecedented 'deep' timescales, this paper concludes by offering alternative lines of inquiry for interdisciplinary analysis of nuclear energy and its associated waste products. [ABSTRACT FROM AUTHOR]

Because of the high-magnitude earthquake and consequent tsunami that struck the east coast of Japan on March 11, 2011, at 14:46, Tokyo Electric Power Company's Fukushima Daiichi nuclear power plant experienced station blackout (SBO) resulting in a nuclear accident unprecedented in time and extent. Simulation of such an accident by means of computer codes is largely dependent on the applied boundary conditions and physical models. However, still-unknown boundary conditions and unclear phenomena result in uncertain computed quantities. In this study, first, the boundary conditions of emergency systems are theoretically derived, starting from a discussion of the reactor available measured quantities and related uncertainties. Then, newly implemented physical models (e.g., wetwell condensation mechanism), which were not accounted for in historical studies of long-term SBOs, are explained. As an early method for accident clarification and explanation regarding effective boundary conditions, results from the SAMPSON severe accident code were compared with theoretical values. The results of SAMPSON compared with the measured quantities available have shown that despite successful safety operations performed by the plant operators in Fukushima Daiichi Unit 3, the eventual lack of batteries (for systems operation and measurement reading) led to plant conditions of low core water level at high pressure, nullifying the attempt of the subsequent alternative water injection to prevent core degradation. [ABSTRACT FROM AUTHOR]

Two aerosol sampling stations in Lithuania were simultaneously used for assessing consequences of the accident at the Fukushima Dai-ichi nuclear power plant. The maximum activity concentrations of 129mTe, 131I, 134Cs and 137Cs were 0.59±0.06, 3.5±0.3, 0.90±0.08, 0.90±0.07mBqm−3 at station #1 in Vilnius, and 0.29±0.03, 1.0±0.1, 0.41±0.04, 0.41±0.04mBqm−3 at station #2 in northeastern part of Lithuania, respectively. [ABSTRACT FROM AUTHOR]

The article focuses on the nuclear safety in China as of July 2013 following the aftermath of the nuclear accident at Fukushima, Japan in 2011. Due to this nuclear accident, several countries including Germany, Switzerland and Italy abandoned their plans to extend their nuclear capacity but China is among the countries that will continue to build nuclear plants. The author states that China should exploit all usable possibilities to meet their growing electricity demand. As of the said date, there are eight East Asian countries, including Malaysia, South and North Korea and Thailand, who are having plans for civil nuclear energy.

This essay was written under the impact of the 2011 Fukushima nuclear catastrophe to locate the nuclear power issue in a context broader than energy and environment. “Peaceful use of nuclear energy” was brought in by the US in the mid-1950s as part of its “psy” warfare to cleanse atomic power of the horrifying image of the Hiroshima-Nagasaki massacre. “Peaceful use” as such was accepted as a symbol of progress even by left-wing intellectuals. However, the Japanese ruling groups situated such use in their long-term military context. In the ensuing decades, the government carried out huge national nuclear programs and said they were genuinely for energy supply. But in 1965–72, the government undertook serious studies on Japan's nuclear arms, concluding that although Japan would stay non-nuclear “for the time being,” it would keep its techno-economic capacity ready to produce nuclear bombs any time they were needed. This essay examines Japan's nuclear power in reference to the major defining factors of the postwar Japanese statehood—the US–Japan security alliance(Anpo), Okinawa as the pivot ofAnpo, the rightists' ambition to revive the glory of the prewar Empire, and Japan's position in the US–China relationship. TheFukushimadisaster and Okinawa's resistance to military colony status rocked this whole structure, bankrupting the postwar statehood. People are now urged to define what comes next. [ABSTRACT FROM AUTHOR]

Even in the face of the March 2011 accident at the Fukushima nuclear power plant in Japan, nuclear power is being promoted in the U.S. as a necessary response to global climate change. Conducted prior to the Fukushima accident, the present study used a nation-wide telephone survey of 2751 U.S. residents to assess the factors that influence whether a person has become more open to nuclear power because of global climate change rather than supportive or opposed to nuclear power. Results showed that belief that climate change is a risk and is human-caused, belief that nuclear energy contributes to climate change, environmental support, cultural worldviews, and selected socio-demographics consistently predicted openness to nuclear power because of climate change. Implications of the current results and avenues for additional research on this topic are discussed. [ABSTRACT FROM AUTHOR]

Abstract: The reports from the International Atomic Energy Agency (IAEA) and the Japanese Nuclear and Industrial Safety Agency (NISA) have confirmed that the Fukushima Daiichi nuclear power plant (NPP) survived the initial earthquake impacts, but fell victim to the following tsunami. The 14-m tsunami well exceeded the maximum safety design of 5.7m. It damaged the pumps, cut off the external power supplies to cool the reactors and spent fuel pool, and directly contributed to the three core meltdowns at the Fukushima Daiichi NPP. These official reports, academic papers, and breaking news also show that five warnings of tsunamis at the Fukushima Daiichi NPP had been ignored by the nuclear operator and regulators since 2000. This article argues that not the natural disaster, but the regulatory failures contributed to the worst nuclear accident since Chernobyl. It explains how the cozy relationship between the government, regulators and nuclear operators, the combined role of NISA as an industry promoter and regulator, and the revolving door between bureaucrats and industries had long undermined the capacity of NISA as a watchdog for nuclear safety. It concludes that upgrading and strengthening a nuclear regulatory system is not optional but imperative to prevent the next core meltdown. Three key recommendations are offered for upgrading nuclear safety regulation. [Copyright &y& Elsevier]

The article explores the impact of the 2011 Fukushima Daiichi nuclear plant accident in Japan on anti-nuclear movements in India. Nuclear energy's role in India's overall development paradigm is described. The Indian anti-nuclear movements' basis, chronology and activities are explained. The Indian government's decision to halt construction of a nuclear plant as a result of mass protests and to begin consultations with citizens regarding better nuclear regulation and safety is cited. Strategies that India's anti-nuclear movements should consider in order to become more effective include educating people about nuclear catastrophe and suggesting socio-economically feasible courses of action requiring less energy.

The work done by the Technical Crisis Center at the Institute of Problems in the Safe Development of Nuclear Energy of the Russian Academy of Sciences on providing scientific-technical support to the National Control Center for Crisis Situations of the Russian Ministry of Emergency Situations and Crisis Situation Center at Rosatom during the first few days and subsequent period after the accident at the Fukushima-1 NPP in Japan in March 2011 is described. The results of computer calculations of possible development of the situation in the power-generating units of the damaged NPP, predictions of the dynamics of the change of the radiation conditions near and at large distances from the NPP, right up to the Far East territory of our country as well estimates of the irradiation dose to the population are presented. [ABSTRACT FROM AUTHOR]

Abstract: The recent events at the Fukushima power plants (PP) have brought to light key issues which have to be discussed concerning the position of nuclear energy in the energy mix, in the context of global warming, of waning petroleum resources, of an increasing world population, and of its industrial development. These questions are addressed here from the viewpoint of physical facts; and, without proposing definite choices, this article aims to provide information on the equipment required to benefit from the fission chain reaction, while explaining the possible incidents and accidents, and the possible hidden military misuse of nuclear matter. Specific issues, such as risk assessment and risk management, will be considered, under the constraints of dealing with international non-proliferation safeguards and France energy resources independence. A special emphasis will be given on the fuel cycle, on the variety of time scales involved, and on the requirements of developing the next generation of nuclear power plants, and more specifically the fast breeder option. The lessons to be drawn from the Fukushima accident, resulting mainly from the residual power of used fuel and the loss of cooling source, are outlined, and the consequences to be drawn about the various relevant time scales are emphasized. [Copyright &y& Elsevier]

Summary Using cross-country data, this paper investigates how freedom of media influenced views regarding the security of nuclear energy after the Fukushima accident in Japan. Key findings are: (1) citizens are less likely to agree that nuclear power plants are properly secured against accidents with the presence of a free media and higher levels of freedom of expression; and (2) freedom of expression and free media are positively associated with the presence of nuclear plants. These findings indicate that sufficient information leads citizens to both understand the risk of nuclear energy and to accept the existence of nuclear plants. [ABSTRACT FROM AUTHOR]

The article discusses the economic impact of the 2011 Earthquake in Japan. Topics include a possible economic recession in Japan after a decline in the GDP (gross domestic product), the large debt burden of Japan, and the finances of the disaster relief. Discussion is included about a potential global economic crisis prompted by the Japanese economic decline such as the crisis in 2008. Problems related to the use of nuclear power in light of the Fukushima nuclear accident after the earthquake are also discussed. It is suggested that the earthquake could have lasting economic effects on Japan and the world.

This paper provides novel evidence of the unintended health effects stemming from the halt in nuclear power production after the Fukushima Daiichi nuclear accident. After the accident, nuclear power stations ceased operation and nuclear power was replaced by fossil fuels, causing an increase in electricity prices. We find that this increase led to a reduction in energy consumption, which caused an increase in mortality during very cold temperatures, given the protective role that climate control plays against the elements. Our results contribute to the debate surrounding the use of nuclear as a source of energy by documenting a yet unexplored health benefit from using nuclear power, and more broadly to regulatory policy approaches implemented during periods of scientific uncertainty about potential adverse effects. [ABSTRACT FROM AUTHOR]

Nuclear power remains one of the most accessible choices in addressing environmental and social concerns due to the continuously increasing energy needs around the world. While it remains an excellent source of energy due to its low price and low level of emissions, potential accidents remain a serious problem. An example of such is the most recent accident in the Fukushima Daiichi Nuclear Power Plant (2011), which reminded the world of the potential risks of nuclear energy and the consequences of which continue to have a lasting effect. There is no nuclear power plant in Serbia, but there are about 15 nuclear power stations scattered within its neighboring countries. Therefore, the Serbian Government decided to study how the Serbian public perceives the risks related to the potential construction of nuclear power stations in the country, nuclear energy in general, and its possible benefits and risks. The objective of this paper is to present the results of this assessment along with a literature overview on the (environmental) risk of nuclear power. A pilot study consisted of a series of 270 randomized face-to-face interviews that took place in the public square of Belgrade in March 2019. Logistic regression was used to examine the cumulative effects of the different risk factors. The results showed that the majority of the respondents are skeptical and do not support the construction of nuclear power stations in Serbia. Furthermore, this research identified several additional important correlations that have a significant impact on the public perception of risk. [ABSTRACT FROM AUTHOR]

Much is still not known about the end-state of core materials in each of the units at Fukushima Daiichi Nuclear Power Station (Daiichi) that were operating on March 11, 2011. The Nuclear Energy Agency of the Organization for Economic Development has launched the Preparatory Study on Analysis of Fuel Debris (PreADES) project as a first step to reduce some of these uncertainties. As part of the PreADES Task 1, relevant information was reviewed to confirm the accuracy of graphical depictions of the debris endstates at the damaged Daiichi units, which provides a basis for suggesting future debris examinations. Two activities have been completed within the PreADES Task 1. First, relevant knowledge from severe accidents at the Three Mile Island Unit 2 and the Chernobyl Nuclear Power Plant Unit 4 was reviewed, along with results from prototypic tests and hot cell examinations, to glean insights that may inform future decommissioning activities at Daiichi. Second, the current debris endstate diagrams for the damaged reactors at Daiichi were reviewed to confirm that they incorporate relevant knowledge from plant observations and from severe accident code analyses of the BSAF (Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station) 1 and 2 projects. This paper highlights Task 1 insights, which have the potential to not only inform future Decontamination and Decommissioning activities at Daiichi but also provide important perspectives for severe accident analyses and management, particularly regarding the long-term management of a damaged nuclear site following a severe accident. [ABSTRACT FROM AUTHOR]

• A molten corium-concrete interaction (MCCI) analysis code MOQUICO is developed. • The code is validated using various experiments. • The MCCI analysis for light water reactor plants is performed using the developed code. After the Fukushima nuclear accident, great attention is being paid to the late-phase behavior of the severe accident in the reactor, especially the molten corium-concrete interaction (MCCI). The MCCI process is very complex, involving physical and chemical reactions, heat and mass transfer processes. Many factors will affect the final result, with a high degree of uncertainty and there are still many unknowns based on current knowledge. In this paper, aimed at the MCCI phenomena in the containment cavity during a hypothetical accident in the nuclear power plant, an MCCI analysis code MOQUICO was developed by coupling the models of molten corium-concrete heat transfer, the concrete pyrolysis, and the corium cooling characteristics. The code MOQUICO was validated using the CCI-2, CCI-3 and SURC-2 tests with limestone-common sand concrete (LCS), siliceous concrete (SIL), and basaltic concrete (BAS), respectively. The simulant axial and radial ablation depths, upward heat flux and melt temperature agreed well with the experimental measurements. Afterwards, the code was used to simulate the typical PWR and BWR nuclear power plants. The ablation depth and gas production were analyzed for both simulations. Furthermore, the corium cooling was studied with eight different water injection moments for PWR and sensitivity analysis for decay heat and concrete type was conducted for BWR. The analysis proved that the developed code is capable of simulating MCCI and related phenomena of Light Water Reactor (LWR). [ABSTRACT FROM AUTHOR]

Utilizing the data of a large nationwide household survey conducted in 2014, we investigate public preferences on nuclear power in Japan after the Fukushima nuclear accident and the role of four sets of factors: (1) household/individual socioeconomic characteristics, (2) psychological status, (3) geographical aspects, and (4) Fukushima accident-related experiences. The preferred energy mix, according to the averaged responses from the survey, includes 0.59 for renewables, 0.29 for fossil fuels, and 0.12 for nuclear—much more skewed towards the renewables than the actual national share of renewables of less than 0.2. Male, older, unmarried, less educated, high-income people, and government party supporters have a preference towards a higher share of nuclear power, except if they live near nuclear power plants. The experience of blackout and aversion to nuclear power during the Great East Japan Earthquake of 2011 lowers the share of nuclear power in the preferred mix. [ABSTRACT FROM AUTHOR]

• This paper introduces accident behavior of typical DBAs and BDBAs of the HTR-PM. • All accidents of the HTR-PM have be divided into several categories, each with similar phenomena or same mitigation measures. • The Extended Emergency Operational Procedures (EEOP) and Beyond design basis accident Additional Mitigation Guideline (BAMG) have been developed for the HTR-PM operators. • This work can provide preliminary reference for the further study on the safety regulation, standards or guidelines for design, operation and accident management of the HTGR. High Temperature Gas-cooled Reactor (HTGR), which plays an important role in the worldwide development of Generation-IV nuclear energy technology, is well-known for the high safety, high efficiency and process heat application. A commercial-scale 200 MWe High Temperature gas-cooled Reactor Pebble-bed Module (HTR-PM) has been designed and is now under construction in Shandong Province, China. Most of the construction and installation work have been finished and the connection to the electric grid will be expected in the end of 2020. In this paper, the reactor behaviors of the HTR-PM during the typical design basis accidents (DBAs) and beyond design basis accidents (BDBAs) have been introduced. In the DBAs, the maximum fuel temperature will never exceed its design limitation of 1620 °C, below which under the design burn-up the "Tristructural-isotropic" (TRISO) coated particles can effectively retain their fission-product inventory. Even in the typical BDBAs with extremely low probability, there is enough time, e.g. several days, to adopt appropriate measures to mitigate the consequence, so that the large release of the radioactive materials would not happen. Accident management is important for the nuclear power plant. Besides, After the Fukushima Dai-ichi nuclear accident, in the worldwide, people are more concerned about the severe accident management of the nuclear power plant, and some standards and guidelines are issued. Based on the accident analyses of the HTR-PM, its accident management is studied and discussed. The designers believe that the accident management procedures can be simplified and no offsite emergency measures are needed for the HTR-PM due to the inherent safety design. Compared to the other types of the nuclear power plant, e.g. the Pressurized-Water Reactor (PWR) power plant, the Severe Accident Management Guideline (SAMG) can be simplified or even unnecessary for the HTR-PM. Above work also can provide reference for the further study on the safety regulations, standards or guidelines for the design, operation and accident management of the HTGR. [ABSTRACT FROM AUTHOR]

Probabilistic safety assessment (PSA) of nuclear facilities on external multi-hazards has become a major issue after the Fukushima accident in 2011. However, the existing external hazard PSA methodology is for single hazard events and cannot cover the impact of multi-hazards. Therefore, this study proposes a methodology for quantifying multi-hazard risks for nuclear energy plants. Specifically, we developed an efficient multi-hazard PSA methodology based on the probability distribution-based Boolean algebraic approach and sampling-based method, which are currently single-hazard PSA methodologies. The limitations of the probability distribution-based Boolean algebraic approach not being able to handle partial dependencies between the components are solved through this sampling-based method. In addition, we devised an algorithm that was more efficient than the existing algorithm for improving the limits of the current sampling-based method, as it required a significant computational time. The proposed methodology was applied from simple examples to single- and multi-hazard PSA examples of actual nuclear power plants. The results showed that the proposed methodology was verified in terms of accuracy and efficiency perspectives. Regarding the sampling-based method, it was confirmed that the proposed algorithm yielded fragility and risk results that have similar degrees of accuracy, even though it extracted a smaller number of samples than the existing algorithm. [ABSTRACT FROM AUTHOR]