- 著者
- 玉井 秀定 秋本 肇 高瀬 和之
- 出版者
- Atomic Energy Society of Japan
- 雑誌
- 日本原子力学会和文論文誌 (ISSN:13472879)
- 巻号頁・発行日
- vol.11, no.1, pp.8-12, 2012 (Released:2012-02-15)
- 参考文献数
- 5
- 被引用文献数
- 1 1
The Fukushima Daiichi Nuclear Plant Unit 1 accident was investigated with the TRAC-BF1 code in order to confirm the effect of an isolation condenser (IC) on core cooling analytically. The analysis shows that the formation of two-phase natural-circulation flow is a key phenomenon for core cooling. Therefore, it is too late to cool fuel rods, once the core is heated up because of the lack of coolant. It also shows that the early start-up of the IC is essential for avoiding the core meltdown under station blackout conditions.
- 著者
- 玉井 秀定 秋本 肇 高瀬 和之
- 出版者
- Atomic Energy Society of Japan
- 雑誌
- 日本原子力学会和文論文誌 (ISSN:13472879)
- 巻号頁・発行日
- pp.1201280043, (Released:2012-01-31)
- 参考文献数
- 5
- 被引用文献数
- 1 1
The Fukushima Daiichi Nuclear Plant Unit 1 accident was investigated with the TRAC-BF1 code in order to confirm the effect of an isolation condenser (IC) on core cooling analytically. The analysis shows that the formation of two-phase natural-circulation flow is a key phenomenon for core cooling. Therefore, it is too late to cool fuel rods, once the core is heated up because of the lack of coolant. It also shows that the early start-up of the IC is essential for avoiding the core meltdown under station blackout conditions.
- 著者
- 永武 拓 玉井 秀定 秋本 肇 吉田 啓之 高瀬 和之
- 出版者
- 一般社団法人日本機械学会
- 雑誌
- 計算力学講演会講演論文集 (ISSN:1348026X)
- 巻号頁・発行日
- vol.2012, no.25, pp.718-719, 2012-10-06
The Fukushima Daiichi Nuclear Plant, Unit No.1, 2 and 3 which were under operation were automatically shut down when the earthquake occurred. After the earthquake, the tsunami reached the planst and all AC power was lost. This loss of AC power made it impossible to supply cooling water into the pressure vessel. After that, the water level in the pressure vessel became less and the meltdown occurred. But the loss of coolant and core uncovery process is unclear, because the plant parameters (water level, pressure, etc) could not be checked in the situation of loss of electric power. Now we are performing the numerical evaluation regarding to the core uncovery process in the Fukushima Daiichi Nuclear Plant Unit No.1 accident with the TRAC-BF1 code. In this study, the core uncovery process and the effect of isolation condenser for the reactor core cooling were investigated. This paper describes the results of the numerical evaluation on the core uncovery process.
- 著者
- 高瀬 和之 小瀬 裕男 久米 悦雄 秋本 肇
- 出版者
- The Visualization Society of Japan
- 雑誌
- 可視化情報学会誌 (ISSN:09164731)
- 巻号頁・発行日
- vol.20, no.1, pp.113-114, 2000
Numerical analyses on thermal-hydraulic characteristics in fusion reactors at accident events such as ICE (Ingress-of-Coolant Event) and LOVA (Loss-of-Vacuum Event) were carried out due to make sure adequacy of the safety design in ITER (International Thermonuclear Experimental Reactor) and the results were visualized numerically to enhance the understanding of physical phenomena during ICE and LOVA events. Relation between pressure rise and void fraction in ITER at the ICE event was obtained with a TRAC code. Air-ingress behavior into water was also clarified quantitatively with a CIP code. Furthermore, exchange flow and dust mobilization behavior through breaches on the fusion reactor during the LOVA event were analyzed based on equations of compressible fluid and dust momentum. It was found from the results of present numerical visualization that a suppression tank system which will be used in ITER is very effective and the ITER pressure suppression system during ICE and LOVA events is adequate.
- 著者
- 永武 拓 秋本 肇 吉田 啓之 高瀬 和之
- 出版者
- 一般社団法人 日本原子力学会
- 雑誌
- 日本原子力学会 年会・大会予稿集
- 巻号頁・発行日
- vol.2012, 2012
福島第一原発1号機の炉心冷却状況を把握するため、過渡解析コードTRAC-BF1を用いて原子炉及び非常用復水器を模擬した体系で圧力容器内の冷却材分布を解析し、地震発生及び津波到達後から炉心露出に至るまでの過程及び非常用復水器の炉心冷却への影響を検討している。本発表では、前報で課題とされた炉心部多次元性の影響について、Vessel Componentを用いた解析を実施することにより検討を行った。