書誌事項
- タイトル別名
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- Evaluations of Fracture Mechanical Properties, Thermal Stress Resistances and Their Neutron Irradiation Effects of Fuel Compact for HTTR.
- HTTRヨウ ネンリョウ コンパクト ノ キカイテキ セイシツ タイネツ オウ
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To simulate the nuclear fuel for the High Temperature Engineering Testing Reactor (HTTR), fuel compact models using SiC-kernel coated particles instead of UO2-kernel coated particles were prepared under the same conditions as those for the real fuel compact. The mechanical and fracture mechanics properties were studied at room temperature. The thermal shock resistance and fracture toughness for thermal stresses of the fuel compact were experimentally assessed by means of arc discharge heating applied at a central area of the disk specimens. These model specimens were then neutron irradiated in the Japan Material Testing Reactor (JMTR) for fluences up to 1.7×1025n/mm2 (E>29fJ) at 900°C±50°C. The effects of irradiation on a series of fracture mechanical properties were evaluated and compared with the cases of graphite IG-110 used as the core materials in the HTTR.
収録刊行物
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- 日本原子力学会誌
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日本原子力学会誌 34 (3), 266-276, 1992
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390001206546694400
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- NII論文ID
- 130003747225
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- NII書誌ID
- AN00188477
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- ISSN
- 21865256
- 00047120
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- NDL書誌ID
- 3757508
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- 本文言語コード
- ja
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- データソース種別
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- JaLC
- NDL
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可