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シビアアクシデント発生時におけるPWRプラント挙動の基礎的研究(1) -(1次系LOCA+ECCS 失敗)事故-
https://doi.org/10.57375/00001552
https://doi.org/10.57375/0000155290a587fa-9376-4f5d-8933-896ae935fe9e
| 名前 / ファイル | ライセンス | アクション |
|---|---|---|
293-303.pdf (12.6 MB)
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| Item type | 紀要論文 / Departmental Bulletin Paper(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2015-08-06 | |||||
| タイトル | ||||||
| タイトル | シビアアクシデント発生時におけるPWRプラント挙動の基礎的研究(1) -(1次系LOCA+ECCS 失敗)事故- | |||||
| タイトル | ||||||
| タイトル | Basic Study on PWR Plant Behavior under the Condition of Severe Accident(1) | |||||
| 言語 | en | |||||
| 言語 | ||||||
| 言語 | jpn | |||||
| キーワード | ||||||
| 主題Scheme | Other | |||||
| 主題 | Nuclear Power Plant | |||||
| キーワード | ||||||
| 主題Scheme | Other | |||||
| 主題 | Safety Assesment | |||||
| キーワード | ||||||
| 主題Scheme | Other | |||||
| 主題 | Severe Accident | |||||
| キーワード | ||||||
| 主題Scheme | Other | |||||
| 主題 | Severe Accident Managemnt | |||||
| キーワード | ||||||
| 主題Scheme | Other | |||||
| 主題 | Plant Behavior in Severe Accident | |||||
| キーワード | ||||||
| 主題Scheme | Other | |||||
| 主題 | PWR Plant Simulator | |||||
| 資源タイプ | ||||||
| 資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
| 資源タイプ | departmental bulletin paper | |||||
| ID登録 | ||||||
| ID登録 | 10.57375/00001552 | |||||
| ID登録タイプ | JaLC | |||||
| 著者 |
尾崎, 禎彦
× 尾崎, 禎彦× 井田, 将馬× 中村, 真也× Ozaki, Yoshihiko× Ida, Shohma× Nakamura, Shinya |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | In this paper, we report on the results using the PWR plant simulator about the plant behavior under the condition of the severe accident that LOCA occurs but ECCS fails the water irrigation into the reactor core. As for the results about the relationship between the LOCA area and the time from LOCA occurs until fuel temperature rise start, the time became shorter as the area was the larger. But, in LOCA area of 1000cm2 or more large, the time was almost constant regardless of the area. For small LOCA of 25cm2 area, from the results of the comparative experiments for RCS natural circulation cooling effect in the case of SG open or not, in SG open condition compared with SG not open, the effect was observed more, but the reactor water level was greatly reduced and the time until the fuel temperature rise start was shortened, so the fuel temperature at the time of water irrigation into the reactor core has become higher. On the other hand, for the large LOCA of 1000cm2, the effect was not observed regardless of SG open or not. In addition, the reactor core damage was not spared in the irrigation into the reactor core after 30 minutes from LOCA, however, the hydrogen concentration in the containment building is less than the lower limit of hydrogen detonation, and also the pressure in the containment building is less than the designed value. That is, although suffered the core damage, the integrity of the containment building has been shown to be secured. | |||||
| 書誌情報 |
福井工業大学研究紀要 号 45, p. 293-303, 発行日 2015-08-06 |
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| 出版者 | ||||||
| 出版者 | 福井工業大学 | |||||
| 書誌レコードID | ||||||
| 識別子タイプ | NCID | |||||
| 関連識別子 | TF00010433 | |||||
| 著者版フラグ | ||||||
| 出版タイプ | VoR | |||||
| 出版タイプResource | http://purl.org/coar/version/c_970fb48d4fbd8a85 | |||||
