共查询到17条相似文献，搜索用时 53 毫秒
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介绍了福岛核事故后世界上主要核电国家相继开展的核电厂安全检查、再评价行动,并得出相应的检查和测试结论。法国、美国和中国等国家分别提出了福岛核事故后改进核电厂安全的建议、要求和行动,并制定了具体工程措施：在极端外部事件的设防,严重事故预防和缓解,水、电、通风实体改进,限制严重事故下的放射性释放和应急准备等主要方面开展的安全改进行动,将会提高核电厂的安全水平并提升缓解严重事故的能力。反思福岛核事故,总结福岛核事故对核电安全技术改进的促进作用,对未来核电安全技术的发展进行了展望。 相似文献
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根据日本政府核事故应急指挥部公布的数据,对参与日本福岛第一核电厂乏燃料水池注水作业工作人员分别受圆柱形、链形、锥形、扇形、漫烟形、屋脊形6种典型烟羽模型照射的吸收剂量率进行了计算.结果表明:身着含铅防护服工作人员受圆柱形和漫烟形烟羽照射的吸收剂量率分别为最小值0.14×102 μGy/h和最大值5.35×102 μGy/h;在同种放射性烟羽模型照射下,工作人员身着含铅防护服时吸收剂量率值小于未着气衣时值.计算结果将为核事故应急受照工作人员的剂量评估和医学治疗提供参考. 相似文献
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从秦山核电厂一期工程至今,我国核电厂的自主设计、建造已经走过了30多年的历程,目前仍然运行良好。但期间日本发生的福岛事件,为我们敲响了警钟,我们必须从中吸取经验教训,使我国的核电厂免于事故,做到防患于未然。本文从福岛事件后的改进项及核电厂多年运营经验的角度分析,对核电厂总平面设计进行研究,希望可以对以后的核电厂总平面设计提供参考。 相似文献
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正【日本东京电力公司网站2013年12月20日报道】日本东京电力公司(TEPCO)于2013年12月13日公布了一份题为《福岛第一核电厂堆芯与安全壳情况评价以及事故进程中未明确问题的研究》的报告,这是东电就福岛第一核电厂事故发布的首份事故原因调查进展报告。这份长达300页的报告介绍了有关此次事故原因及其事件序列的许多技术发现、 相似文献
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R. Ando;Y. Koyama;T. Kobayashi;D. Sasaki;N. Akimoto;T. Schneider;J. Lochard;Y. Kanai 《Radioprotection》2023,58(3):161-167
The 24th Fukushima Dialogue, a stakeholder meeting to discuss the future of the recovery phase in Fukushima Prefecture among the younger generation, was held in the town of Naraha in the Futaba district of the Fukushima Prefecture, in November 2022. Following a series of presentations, participants to the meeting aged 18 to 35 discussed the current challenges of the reconstruction activities in the Fukushima Prefecture and what is needed to improve the situation. The Dialogue revealed that the younger generation has difficulty in grasping what is meant by reconstruction and readily distinguishes between the “large” reconstruction of authorities and the “small” one of individuals. It also revealed that the Fukushima accident had a strong impact on the sense of belonging of its inhabitants to the region and that they now aspire to build a new identity by regaining control of their lives, even if it is sometimes a painful process. Finally, the Dialogue brought to light that the younger generation is willing and ready to engage in the decision-making process related to the recovery phase in the Fukushima Prefecture.https://doi.org/10.1051/radiopro/2023021 相似文献
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Osamu Kurihara Katsuta Kanai Takahiro Nakagawa Chie Takada Norio Tsujimura Takumaro Momose 《Journal of Nuclear Science and Technology》2013,50(2):122-129
The Great East Japan Earthquake Disaster on 11 March 2011 caused an unprecedented accident at the Fukushima Daiichi nuclear power station operated by Tokyo Electric Power Company (TEPCO). Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency performed internal dose measurements of 560 employees involved in the accident during the period from 20 April to 5 August in 2011 at the request of TEPCO. The present paper describes our measurements of 131I in the thyroid that is the predominant contributor to the internal dose. These measurements were carried out using an HPGe detector installed in a low-background shielded chamber made of 20-cm-thick steel and the detector was placed adjacent to the subject's neck. The typical minimum detectable activity of this technique was 10 Bq for a counting time of 10 min; however, this sensitivity made it difficult to identify a residual thyroid content of 131I corresponding to a committed effective dose of 20 mSv for late subjects. This paper discussed technical issues experienced through the measurements such as the influence of 131I in the rest of the body, the calibration phantom of use, and so on. 相似文献
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Shigekazu Hirao Hiromi Yamazawa Takuya Nagae 《Journal of Nuclear Science and Technology》2013,50(2):139-147
The atmospheric release rates of I-131 and Cs-137 from the Fukushima Daiichi nuclear power plant in March 2011 were estimated by comparing environmental monitoring data of air concentration and deposition rate on a regional scale with calculated values from an atmospheric dispersion model. Although the release rates were not estimated for all days after 11 March, because of lack of monitoring data, temporal changes in the release rates were reasonably estimated with estimated uncertainties in a factor of 3.3 and 2.9 for I-131 and Cs-137, respectively. A large release was estimated from the night of 14 March to at least the afternoon of 15 March, with maximum values of 7.2 × 1015 Bq h?1 for I-131 and 1.5 × 1014 Bq h?1 for Cs-137. The release rates during other periods were estimated at one- to two-orders of magnitude smaller than the largest release rate on 15 March. Uncertainty in the estimated release rate for 15 and 20 March was larger than for other periods. The significant release during 14 and 15 March and the trend of the release rate by the end of March were consistent with previous reports. This agreement, despite using different datasets, shows robustness of the temporal changes estimated in the studies. 相似文献
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Takuya Kobayashi Haruyasu Nagai Masamichi Chino Hideyuki Kawamura 《Journal of Nuclear Science and Technology》2013,50(3):255-264
The source term of the atmospheric release of 131I and 137Cs due to the Fukushima Dai-ichi Nuclear Power Plant accident estimated by previous studies was validated and refined by coupling atmospheric and oceanic dispersion simulations with observed 134Cs in seawater collected from the Pacific Ocean. By assuming the same release rate for 134Cs and 137Cs, the sea surface concentration of 134Cs was calculated using the previously estimated source term and was compared with measurement data. The release rate of 137Cs was refined to reduce underestimation of measurements, which resulted in a larger value than that previously estimated. In addition, the release rate of 131I was refined to follow the radioactivity ratio of 137Cs. As a result, the total amounts of 131I and 137Cs discharged into the atmosphere from 5 JST on March 12 to 0 JST on March 20 were estimated to be approximately 2.0 × 1017 and 1.3 × 1016 Bq, respectively. 相似文献
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Toru Kitagaki Hirotomo Ikeuchi Kimihiko Yano Laurent Brissonneau Brigitte Tormos Renaud Domenger 《Journal of Nuclear Science and Technology》2019,56(9-10):902-914
ABSTRACTCharacterization of fuel debris is required to develop fuel debris removal tools for decommissioning Fukushima Daiichi nuclear power plant (1F). Especially, knowledge about the characteristics of molten core-concrete interaction (MCCI) product is needed because of the limited information available at present. Samples from a large-scale MCCI test performed under quenching conditions, VULCANO VW-U1 were analyzed to evaluate the characteristics of the surface of MCCI product. Four samples were selected from test sections at different locations. As a result, the characteristics of the samples were found to be similar. Several corium phases, such as cubic-(U,Zr)O2 and tetragonal ZrO2, were detected by X-ray diffraction (XRD), but concrete-based phases, such as the crystalline SiO2 phase, were not detected by XRD because the quantity of the SiO2 phase was too small to be measured. The Vickers hardness of each phase in these samples was higher than that of previously analyzed samples in another VULCANO test campaign, VBS-U4. Based on a comparison between MCCI product generated under quenching condition, such as VW-U1, and gently cooled MCCI product, such as VBS-U4, the MCCI product generated under quenching condition is more homogeneous, and its hardness is higher than that of the gently cooled MCCI product. 相似文献
