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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(2) -(給水系LOCA+ECCS 注入失敗)事故と(SBO+SRV 開固着)事故 -
https://doi.org/10.57375/00001585
https://doi.org/10.57375/000015854c53c571-70e5-4653-9844-f89ab94eb235
| 名前 / ファイル | ライセンス | アクション |
|---|---|---|
148-159.pdf (10.7 MB)
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| Item type | 紀要論文 / Departmental Bulletin Paper(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2016-07-21 | |||||
| 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(2) -(給水系LOCA+ECCS 注入失敗)事故と(SBO+SRV 開固着)事故 - | |||||
| タイトル | ||||||
| タイトル | Basic Study on BWR Plant Behavior under the Condition of Severe Accident (2) | |||||
| 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 Assesmen | |||||
| 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 | 10.57375/00001585 | |||||
| ID登録タイプ | JaLC | |||||
| 著者 |
尾崎, 禎彦
× 尾崎, 禎彦× 上田, 将正× 佐々木, 一× Ozaki, Yoshihiko× Ueda, Masataka× Sasaki, Hajime |
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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 two types of severe accidents that LOCA occurs but ECCS fails the water irrigation into the reactor core and SBO occurs and at the same time the reclosed failure of SRV occurs. The simulation experiments were carried out for the cases that LOCA has occurred in the main feed-water piping. 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 small and middle LOCA area. In the case of main feed-water 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 accident of SBO with reclosed failure of SRV, it has been shown that the accidents continue to progress rapidly as compared with the case of normally operating of SRV. Because SRV has the function that keep the inside pressure of reactor core by repeating opened and closed in response of the inside pressure and prevent the decrease of water level inside reactor core. However, if the irrigation into the reactor core was carried out 30min after SBO occurrence, the core had little damage and also the H2 concentration in the containment vessel did not exceed limits of H2 explosion. Further, as for the accident of reclosed failure of SRV, it has been shown that there are very good correspondence with the simulation results of main steam piping LOCA of area 180cm2 corresponding to the inlet cross-sectional area SRV installed on the piping. Therefore, the accident of reclosed failure has been also shown that can be regarded as small LOCA accidents of main steam piping. | |||||
| 書誌情報 |
福井工業大学研究紀要 号 46, p. 148-159, 発行日 2016-07-21 |
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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 | TF00010466 | |||||
| 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 | |||||
