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Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor
https://shonan-it.repo.nii.ac.jp/records/2000330
https://shonan-it.repo.nii.ac.jp/records/2000330b036df92-feb0-46cb-b751-69a5cd3a3236
| 名前 / ファイル | ライセンス | アクション |
|---|---|---|
Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor (1 MB)
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| Item type | 紀要論文 / Departmental Bulletin Paper(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2024-11-11 | |||||
| タイトル | ||||||
| タイトル | Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor | |||||
| 言語 | en | |||||
| 言語 | ||||||
| 言語 | eng | |||||
| キーワード | ||||||
| 言語 | en | |||||
| 主題Scheme | Other | |||||
| 主題 | Thermal Hydraulics | |||||
| キーワード | ||||||
| 言語 | en | |||||
| 主題Scheme | Other | |||||
| 主題 | Ultra High Temperature Nuclear Reactor (UHTR) | |||||
| キーワード | ||||||
| 言語 | en | |||||
| 主題Scheme | Other | |||||
| 主題 | Porosity and Pebble Type Fuel | |||||
| 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 | |||||
| 著者 |
FUMIZAWA, Motoo
× FUMIZAWA, Motoo× 文沢, 元雄 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | This study presents an experimental method of porosity evaluation and a predictive thermal-hydraulic analysis with packed spheres in a nuclear reactor core. The porosity experiments were carried out in both a fully shaken state with the closest possible packing and in a state of non-vibration. The predictive analysis considering the fixed porosity value was applied as a design condition for an Ultra High Temperature Reactor Experiment (UHTREX). The thermal-hydraulic computer code was developed and identified as PEBTEMP. The highest outlet coolant temperature of 1316°C was achieved in the case of an UHTREX at Los Alamos Scientific Laboratory, which was a small scale UHTR. In the present study, the fuel was changed to a pebble type, a porous media. In order to compare the present pebble bed reactor and UHTREX, a calculation based on HTGR-GT300 was carried out in similar conditions with UHTREX; in other words, with an inlet coolant temperature of 871°C, system pressure of 3.45MPa and power density of 1.3W/cm3. As a result, the fuel temperature in the present pebble bed reactor showed an extremely lower value compared to that of UHTREX. | |||||
| 言語 | en | |||||
| bibliographic_information |
ja : 湘南工科大学紀要 en : MEMOIRS OF SHONAN INSTITIUTE OF TECHNOLOGY 巻 41, 号 1, p. 1-8, 発行日 2007-03-18 |
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| 出版者 | ||||||
| 出版者 | 湘南工科大学 | |||||
| 言語 | ja | |||||
| item_10002_source_id_9 | ||||||
| 収録物識別子タイプ | PISSN | |||||
| 収録物識別子 | 09192549 | |||||
| item_10002_source_id_11 | ||||||
| 収録物識別子タイプ | NCID | |||||
| 収録物識別子 | AN10400308 | |||||
| 出版タイプ | ||||||
| 出版タイプ | VoR | |||||
| 出版タイプResource | http://purl.org/coar/version/c_970fb48d4fbd8a85 | |||||
