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Following the severe accident at the Fukushima Daiichi nuclear power plant in 2011, recrystallized FeCrAl-ODS claddings have been developed in Japan as an accident-tolerant fuel (ATF) to mitigate the extent of oxidation reactions with hot steam. This paper presents an overview of the alloy design and the process used to manufacture the recrystallized cladding, together with a analysis of the applicability of these alloys as BWR fuel cladding and a summary of the results of simulated severe accident performance. A synergistic effect of co-addition of 12 mass% Cr and 6 mass% Al was found to suppress steam oxidation by a stable Al 2 O 3 scale formation and to inhibit a brittle αʹ precipitate after aging. The incorporation of 0.4 mass% Zr greatly improved not only the high temperature strength by replacing coarse Y-Al oxide particles with finer Y-Zr particles, but also the oxidation resistance at temperatures above 1673 K. These excellent performances are associated with the excess oxygen content. It was verified that core excess reactivities affected by the increased neutron absorption by Fe, Cr, Al can be compensated by reducing the thickness to half that of Zircaloy cladding, while maintaining mechanical integrity. A simulated design basis Loss of Coolant Accident (LOCA) event with assessment of post-LOCA ductility confirmed that FeCrAl-ODS cladding provided a greater safety margin along with exceptional high temperature strength and a significantly higher integral LOCA burst temperature compared with wrought FeCrAl alloy (C26M) and Zircaloy. An analysis using the MAAP 5.05b SA code indicated that melting of the Zircaloy core could be slightly accelerated due to release of the huge amount of exothermic reaction heat in the case of small amount of coolant injection. In contrast, the water injection always acts toward cooling the FeCrAl-ODS core. [ABSTRACT FROM AUTHOR]

This paper presents a multiscale data integration method to estimate the spatial distribution of air dose rates in the regional scale around the Fukushima Daiichi Nuclear Power Plant. We integrate various types of datasets, such as ground-based walk and car surveys, and airborne surveys, all of which have different scales, resolutions, spatial coverage, and accuracy. This method is based on geostatistics to represent spatial heterogeneous structures, and also on Bayesian hierarchical models to integrate multiscale, multi-type datasets in a consistent manner. The Bayesian method allows us to quantify the uncertainty in the estimates, and to provide the confidence intervals that are critical for robust decision-making. Although this approach is primarily data-driven, it has great flexibility to include mechanistic models for representing radiation transport or other complex correlations. We demonstrate our approach using three types of datasets collected at the same time over Fukushima City in Japan: (1) coarse-resolution airborne surveys covering the entire area, (2) car surveys along major roads, and (3) walk surveys in multiple neighborhoods. Results show that the method can successfully integrate three types of datasets and create an integrated map (including the confidence intervals) of air dose rates over the domain in high resolution. Moreover, this study provides us with various insights into the characteristics of each dataset, as well as radiocaesium distribution. In particular, the urban areas show high heterogeneity in the contaminant distribution due to human activities as well as large discrepancy among different surveys due to such heterogeneity. [ABSTRACT FROM AUTHOR]

7-Methyl-2H-1,5-benzodioxepin-3(4H)-one (Calone®) is used in fragrances to impart a marine note. It is produced industrially at volumes requiring repeated dose and developmental/reproductive toxicology data (OECD TG 422) under European chemicals legislation (i.e., REACH). Additionally, Japanese chemicals legislation requires evaluation of Calone® biodegradability and identification of metabolites in an environmental biodegradation test. 7-Methyl-2H-1,5-benzodioxepin-3-ol (Calol) was the sole metabolite identified following biodegradation and a 28-day repeated dose toxicity study (OECD TG 407) would normally be required to support registration in Japan. The current paper presents results showing no adverse effects in the parental, reproductive, or developmental phases of an OECD TG 422 study following dietary administration of Calone® to rats at targeted doses of up to 1000 mg/kg/day. The No Observed Adverse Effect Level (NOAEL) was the highest administered dose of 791 and 922 mg/kg/day for males and females, respectively. An i n vitro metabolism study conducted with rat and human liver microsomes demonstrated that greater than 90% of Calone® was metabolically reduced into Calol, the same metabolite observed in the environmental biodegradation test. Accordingly, the results from the OECD TG 422 study with Calone® are directly applicable to Calol and it would be expected to have the same NOAEL. [ABSTRACT FROM AUTHOR]

The Great Tohoku–Kanto earthquake and the resulting tsunami have brought considerable attention to the issue of building new nuclear power plants. In this paper we argue that nuclear power is not a sustainable solution to energy problems. First, we explore the stock of uranium-235 and the different methods, fast breeder and MOX fuel reactors, developed by the nuclear power industry to exploit this resource. Second, we show that these fuel reactors are not feasible. Third, we show that the claim that nuclear energy can be used to reduce CO2 emissions is false: the emissions from the increased water evaporation from nuclear power generation must be accounted for. In the case of Japan, water from nuclear power plants is drained into the surrounding sea, raising the water temperature which has an adverse effect on the immediate ecosystem, as well as increasing CO2 emissions from increased water evaporation from the sea. Next, a short exercise is used to show that nuclear power is not needed to meet electricity demand in Japan. Such an exercise should be performed for any country considering the construction of additional nuclear power plants. Lastly, the paper is concluded with a discussion of the implications of our paper. [Copyright &y& Elsevier]

Occurrence of severe accidents, such as the Fukushima incident in 2011, is unlikely with a probability of 10 −5 per reactor per year. However, such kinds of accidents have serious consequences on both, short term as well as on long term public health, environment and energy policy and security. They also adversely affect the progress of nuclear power industry. Thus, despite such a low probability of occurrence, a need arises to review the safety standards of nuclear power plants, especially in the light of the Fukushima accident. Apart from other systems, a review of thermal-hydraulics and safety system for the reactor containment is vital, as it is the last barrier to radioactive leakage. Main threats to the containment integrity include over-pressurization, not only due to steam alone, but its coupling with the possibility of local hydrogen combustion, depending on the local mixture composition of steam-air-hydrogens. It must be emphasized that steam condensation rate affects the local mixture composition and presence of hydrogen significantly deteriorates the condensation rate. This intrinsic coupling needs to be understood. In this paper, steam condensation and related issues, including basics of condensation, modeling approaches, parameters affecting condensation and experiments performed (in both separate effect and integral test facilities) are critically reviewed, in the light of coupled issues of hydrogen transport and combustion. Such studies are necessary for correlation development and/or to find out the local distribution of steam-hydrogen-air mixture within the containment to locate the possible hydrogen combustion location(s) and hence, deployment of active/passive safety systems. In addition, it is important that future studies, both experimental and numerical modeling, focus on the coupled nature of the problem in a comprehensive manner for ensuring long term safety. [ABSTRACT FROM AUTHOR]

The present paper studies how a random event (earthquake) and the subsequent disaster in Japan affect transport and deposition of fallout and the resulting health consequences. Therefore, except for the original accident in March 2011, three additional scenarios are assessed assuming that the same releases took place in winter 2010, summer 2011 and autumn 2011 in order to cover a full range of annual seasonality. This is also the first study where a large number of fission products released from the accident are used to assess health risks with the maximum possible efficiency. Xenon-133 and 137 Cs are directly estimated within the model, whereas 15 other radionuclides are calculated indirectly using reported isotopic ratios. As much as 85% of the released 137 Cs would be deposited in continental regions worldwide if the accident occurred in winter 2010, 22% in spring 2011 (when it actually happened), 55% in summer 2011 and 48% if it occurred during autumn 2011. Solid cancer incidents and mortalities from Fukushima are estimated to be between 160 and 880 and from 110 to 640 close to previous estimations. By adding thyroid cancers, the total number rises from 230 to 850 for incidents and from 120 to 650 for mortalities. Fatalities due to worker exposure and mandatory evacuation have been reported to be around 610 increasing total estimated mortalities to 730–1260. These estimates are 2.8 times higher than previously reported ones for radiocaesium and 131 I and 16% higher than those reported based on radiocaesium only. Total expected fatalities from Fukushima are 32% lower than in the winter scenario, 5% that in the summer scenario and 30% lower than in the autumn scenario. Nevertheless, cancer fatalities are expected to be less than 5% of those from the tsunami (~ 20,000). [ABSTRACT FROM AUTHOR]

After the two major nuclear accidents in history considered to be beyond-design-basis accidents (BDBA) – the Chernobyl Reactor Four explosion in Ukraine (1986) and the Fukushima Daiichi accident in Japan (2011), the United States Nuclear Regulatory Commission and other countries have included in the Final Safety Analysis Report (FSAR), a new chapter (19) dedicated to the Probabilistic Safety Assessment (PSA) and Severe Accident Analysis (SAA), with significant damage to the reactor core. The Safety Analysis Report (SAR) is the most important document used by a regulatory body to assess the adequacy of plant safety at all stages of the life time of a Nuclear Power Plant (NPP), and presents the licensing basis of a plant. This study aims at comparing the progression of severe accidents during a Total Loss of Feed Water Accident (TLOFW) and a TLOFW combined with An Anticipated Transient Without SCRAM (ATWS) reactivity accident for a Pressurized Water Reactor (PWR) type NPP. This paper takes into account the results of the PSA Level 1 for the reference NPP. The calculations were performed with the deterministic computer code MELCOR version 2.2 used to analyze severe accident progression in NPP with a Light Water Reactor (LWR). The paper presents a hydrogen risk assessment – the assessment is deterministic, s a prerequisite before performing PSA Level 2. The hydrogen source is determined, too. Saphiro's diagram is applied to investigate the containment atmosphere condition (inert or combustible) for two scenarios. The main results of the study reveal that the containment integrity of the reference PWR NPP when both accidents occurred is maintained. However, the core is severely damaged. A future work will investigate mitigation strategies to limit the hydrogen risk during accident. • The representation of the reference Small Nuclear Power Plant was made to simulate different types of transients and severe accidents and subsequently to verify the performance of safety and mitigation components. • This paper results provide a better understanding of progression of in-vessel core degradation processes for both postulated accidents (TLOFW and TLOFW + ATWS) in a Small Modular Reactor (SMR). • The analysis of severe accident scenarios for a generic Small Modular Reactor (SMR) on 48MWt Pressurized Water Reactor (PWR) using the MELCOR v.2.2 code resulting in a better understanding of the phenomena involved. [ABSTRACT FROM AUTHOR]

Highlights: [•] Chernobyl accident had limited influence on basic research in nuclear energy. [•] Budget allocation to R&D and number of published papers have recently decreased. [•] Citation network analysis revealed reactor safety and fusion as current research trend. [•] Nuclear energy research policy will change after Fukushima disaster. [Copyright &y& Elsevier]

Abstract: In the recent nuclear catastrophe which occurred in Japan on March 11, 2011, several units of Fukushima conventional BWR experienced a total loss of power and water supply triggered by a heavy earthquake and a following Tsunami beyond design basis. In Fukushima accident it was observed that sea water was injected into reactors only after hydrogen explosion took place and it was considered a little too late to prevent core from damage. With regard to this fact, the Taiwan power company develops an ultimate measure to prevent reactor from encountering core damage, if either designed AC power or reactor water supply cannot be restored in time. This ultimate measure was named as DIVing plan, abbreviated from system depressurization, water injection and containment venting. Once any designed AC power or reactor water supply is made available, this DIVing plan will be activated to (1) depressurize reactor first, (2) inject any available water into reactor by any available power supply if this critical status cannot be restored in time, and (3) vent the containment if necessary to maintain containment integrity. In this paper the DIVing plan was simulated by RELAP5-3D to verify the concept of it and also to quantify the required raw water injection rate to prevent core from damage for both PWR and BWR plants in Taiwan, after the loss of passive cooling mechanism. Provided the passive cooling mechanism is lost within the first hour, for Chinshan BWR/4 and Kuosheng BWR/6 plants 1400l/m (370GPM) and 2441l/m (645GPM) raw water injection rate are, respectively, required and for Maanshan 3-loop PWR plant 2271l/m (600GPM) water injection rate is required, to prevent the PCT higher than 1088.6K (1500°F). [Copyright &y& Elsevier]

Abstract: This paper presents measurements of the effect of the atmospheric radioactive release from the Fukushima Dai-ichi nuclear power station at three sites belonging to the Spanish environmental monitoring system. Measured values varied depending on the locations of the sites in Spain and their respective climatic characteristics. 134Cs, 136Cs, 137Cs, 131I, and 132Te activity concentrations in filter samples were studied and associated levels of 131I fallout were estimated from wet and dry deposition. Particulate aerosol activity concentrations ranges, in μBq/m3, were 1.63–3080 (131I), 2.8–690 (137Cs), 1.3–620 (134Cs) and 3.6–330 (132Te), while the associated 131I fallout was roughly estimated to be less than 20 Bq/m2, Gaseous 131I was also detected and the 131I-gaseous/131I-total ratio increased at the three stations from approximately 0.75 at the end of March to 0.85–0.9 during the first few days of April. Finally, the presence of 131I in some crucial parts of the food chain was also studied. 131I was detected in samples from goat''s and cow''s milk (maximum levels of 1.11 Bq/L) and in broadleaf plants (maximum level 1.42 Bq/kg). [Copyright &y& Elsevier]

Abstract: The radioactivity levels in the air of the radionuclides released by the Fukushima accident were measured at the Laboratoire Souterrain de Modane, in the South-East of France, during the period 25 March–18 April 2011. Air-filters from the ventilation system exposed for one or two days were measured using low-background gamma-ray spectrometry. In this paper we present the activity concentrations obtained for the radionuclides 131I, 132Te, 134Cs, 137Cs, 95Nb, 95Zr, 106Ru, 140Ba/La and 103Ru. The activity concentration of 131I was of the order of 100 μBq/m3, more than 100 times higher than the activities of other fission products. The highest activities of 131I were measured as a first peak on 30 March and a second peak on 3–4 April. The activity concentrations of 134Cs and 137Cs varied from 5 to 30 μBq/m3. The highest activity concentration recorded for Cs corresponded to the same period as for 131I, with a peak on 2–3 April. The results of the radioactivity concentration levels in grass and mushrooms exposed to the air in the Modane region were also measured. Activity concentrations of 131I of about 100 mBq/m2 were found in grass. [Copyright &y& Elsevier]

Abstract: On 11 March 2011, the magnitude-9.0 earthquake and a substantial tsunami struck off the northeast coast of Japan. The Fukushima nuclear power plants were inundated and stricken, followed by radionuclide releases outside the crippled reactors. Provisional regulation values for radioactivity in food and drink were set on 17 March and were adopted from the preset index values, except that for radioiodines in water and milk ingested by infants. For radiocesiums, uranium, plutonium and transuranic α emitters, index values were defined in all food and drink not to exceed a committed effective dose of 5 mSv/year. Index values for radioiodines were defined not to exceed a committed equivalent dose to the thyroid of 50 mSv/year, and set in water, milk and some vegetables, but not in other foodstuffs. Index values were calculated as radioactive concentrations of indicator radionuclides (131I for radioiodines, 134Cs and 137Cs for radiocesiums) by postulating the relative radioactive concentration of coexisting radionuclides (e.g., 132I, 133I, 134I, 135I and 132Te for 131I). Surveys were thence conducted to monitor levels of 131I, 134Cs and 137Cs. Provisional regulation values were exceeded in tap water, raw milk and some vegetables, and restrictions on distribution and consumption began on 21 March. Fish contaminated with radioiodines at levels of concern were then detected, so that the provisional regulation value for radioiodines in seafood adopted from that in vegetables were additionally set on 5 April. Overall, restrictions started within 25 days after the first excess in each food or drink item, and maximum levels were detected in leafy vegetables (54,100 Bq/kg for 131I, and a total of 82,000 Bq/kg for 134Cs and 137Cs). This paper focuses on the logic behind such food safety regulations, and discusses its underlying issues. The outlines of the food monitoring results for 24,685 samples and the enforced restrictions will also be described. [Copyright &y& Elsevier]

Abstract: This paper uses cross-country data compiled immediately after the Fukushima nuclear accident to investigate how the experience of such disasters affects the perception of the risk of nuclear accidents. Estimation results show that the perceived risk of a nuclear accident is positively associated with experiencing technological disasters but not with that of natural disasters. [Copyright &y& Elsevier]

Abstract: After the Fukushima nuclear plant accident, Japan is facing an unprecedented situation with its energy supply. This paper provides an overview of Japan’s current energy landscape with descriptions of the kinds and production of energy. Since it is inevitable that the use of nuclear energy will decrease, we shall propose a best mix of electric sources of the large-scale and centralized network as well as the decentralized network as an alternative. The hub for this proposal is regional power centers (RPC) to control the electric supply as well as fuel transportation and storage on an area-by-area basis. As technologies that will realize this power center, we will discuss fuel cells, hydrogen production and storage and furthermore, the potential of CCS, which is requisite technology for carbon dioxide emissions reduction. [Copyright &y& Elsevier]