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シビアアクシデント発生時におけるBWRプラント挙動の基礎的研究(1) -(主蒸気系/再循環系LOCA+ECCS 失敗)事故-
https://doi.org/10.57375/00001623
https://doi.org/10.57375/00001623a80787c7-3ad0-4e35-ba39-129d9ff41e6e
| 名前 / ファイル | ライセンス | アクション |
|---|---|---|
304-315.pdf (13.6 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BWRプラント挙動の基礎的研究(1) -(主蒸気系/再循環系LOCA+ECCS 失敗)事故- | |||||
| タイトル | ||||||
| タイトル | Basic Study on BWR 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 | BWR 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 | 10.57375/00001623 | |||||
| ID登録タイプ | JaLC | |||||
| 著者 |
尾崎, 禎彦
× 尾崎, 禎彦× 上光, 伸吾× 堂後, 光史× Ozaki, Yoshihiko× Jyohko, Shingo× Dohgo, Hirofumi |
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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 BWR 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. The simulation experiments were carried out for the cases that LOCA has occurred in the main steam piping or in the recirculation piping, respectively. As for the results about the relationship between the LOCA area and the time from LOCA occurs until the fuel temperature rise start, the effect that RCIC operated was extremely big for LOCA area of up to 100cm2 for both type LOCA. In the case of main steam system LOCA, the core water level suddenly decreased for large LOCA of 2000cm2 area, however, if the irrigation into the reactor core was carried out 30min after LOCA occurrence, the core had little damage. In addition, the H2 concentration in the containment vessel did not exceed both limits of H2 explosion nor detonation. The pressure of the containment vessel was around 3kg/cm2 of design value, so the soundness of the containment vessel was confirmed. On the other hand, for the recirculation system LOCA of 2000cm2 area, a drop of the core water level was extremely in comparison with main steam system LOCA, and the fuel assemblies were completely exposed during up to 30min. to the irrigation from approximately 100sec. after LOCA occurrence. Therefore, the fuel temperature during the irrigation had reached approximately 1900℃. Thus, the fuel cladding were damaged approximately less than 10%, and H2 concentration in the containment vessel was approximately 9% which did not exceed H2 detonation limit of 13% but exceeded H2 explosion limit of 4%. However, the containment vessel internal pressure was settled around design pressure value of containment vessel. As the results, some core damage could not be avoided, but soundness of the containment vessel, which should take the role of "confine", was found to be secured. | |||||
| 書誌情報 |
福井工業大学研究紀要 号 45, p. 304-315, 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 | TF00010504 | |||||
| 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 | |||||
