{"created":"2024-11-11T05:08:18.626999+00:00","id":2000330,"links":{},"metadata":{"_buckets":{"deposit":"7d1716ee-6ad5-4ec8-a7e9-d5785691445b"},"_deposit":{"created_by":14,"id":"2000330","owner":"14","owners":[14],"pid":{"revision_id":0,"type":"depid","value":"2000330"},"status":"published"},"_oai":{"id":"oai:shonan-it.repo.nii.ac.jp:02000330","sets":["1724133071054:1724293369364"]},"author_link":["1788","1786"],"item_10002_biblio_info_7":{"attribute_name":"bibliographic_information","attribute_value_mlt":[{"bibliographicIssueDates":{"bibliographicIssueDate":"2007-03-18","bibliographicIssueDateType":"Issued"},"bibliographicIssueNumber":"1","bibliographicPageEnd":"8","bibliographicPageStart":"1","bibliographicVolumeNumber":"41","bibliographic_titles":[{"bibliographic_title":"湘南工科大学紀要","bibliographic_titleLang":"ja"},{"bibliographic_title":"MEMOIRS OF SHONAN INSTITIUTE OF TECHNOLOGY","bibliographic_titleLang":"en"}]}]},"item_10002_description_5":{"attribute_name":"抄録","attribute_value_mlt":[{"subitem_description":"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.","subitem_description_language":"en","subitem_description_type":"Abstract"}]},"item_10002_publisher_8":{"attribute_name":"出版者","attribute_value_mlt":[{"subitem_publisher":"湘南工科大学","subitem_publisher_language":"ja"}]},"item_10002_source_id_11":{"attribute_name":"item_10002_source_id_11","attribute_value_mlt":[{"subitem_source_identifier":"AN10400308","subitem_source_identifier_type":"NCID"}]},"item_10002_source_id_9":{"attribute_name":"item_10002_source_id_9","attribute_value_mlt":[{"subitem_source_identifier":"09192549","subitem_source_identifier_type":"PISSN"}]},"item_10002_version_type_20":{"attribute_name":"出版タイプ","attribute_value_mlt":[{"subitem_version_resource":"http://purl.org/coar/version/c_970fb48d4fbd8a85","subitem_version_type":"VoR"}]},"item_creator":{"attribute_name":"著者","attribute_type":"creator","attribute_value_mlt":[{"creatorNames":[{"creatorName":"FUMIZAWA, Motoo","creatorNameLang":"en"}],"familyNames":[{"familyName":"FUMIZAWA","familyNameLang":"en"}],"givenNames":[{"givenName":"Motoo","givenNameLang":"en"}],"nameIdentifiers":[{"nameIdentifier":"1788","nameIdentifierScheme":"WEKO"}]},{"creatorNames":[{"creatorName":"文沢, 元雄","creatorNameLang":"ja"},{"creatorName":"フミザワ, モトオ","creatorNameLang":"ja-Kana"}],"familyNames":[{"familyName":"文沢","familyNameLang":"ja"},{"familyName":"フミザワ","familyNameLang":"ja-Kana"}],"givenNames":[{"givenName":"元雄","givenNameLang":"ja"},{"givenName":"モトオ","givenNameLang":"ja-Kana"}],"nameIdentifiers":[{"nameIdentifier":"1786","nameIdentifierScheme":"WEKO"}]}]},"item_files":{"attribute_name":"ファイル情報","attribute_type":"file","attribute_value_mlt":[{"accessrole":"open_date","date":[{"dateType":"Available","dateValue":"2024-11-11"}],"displaytype":"detail","filename":"001-008_FumizawaMotoo_Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor.pdf","filesize":[{"value":"1 MB"}],"format":"application/pdf","licensetype":"license_11","url":{"label":"Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor","url":"https://shonan-it.repo.nii.ac.jp/record/2000330/files/001-008_FumizawaMotoo_Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor.pdf"},"version_id":"f3588752-4139-4fff-9603-4d9b5730f85c"}]},"item_keyword":{"attribute_name":"キーワード","attribute_value_mlt":[{"subitem_subject":"Thermal Hydraulics","subitem_subject_language":"en","subitem_subject_scheme":"Other"},{"subitem_subject":"Ultra High Temperature Nuclear Reactor (UHTR)","subitem_subject_language":"en","subitem_subject_scheme":"Other"},{"subitem_subject":"Porosity and Pebble Type Fuel","subitem_subject_language":"en","subitem_subject_scheme":"Other"}]},"item_language":{"attribute_name":"言語","attribute_value_mlt":[{"subitem_language":"eng"}]},"item_resource_type":{"attribute_name":"item_resource_type","attribute_value_mlt":[{"resourcetype":"departmental bulletin paper","resourceuri":"http://purl.org/coar/resource_type/c_6501"}]},"item_title":"Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor","item_titles":{"attribute_name":"タイトル","attribute_value_mlt":[{"subitem_title":"Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor","subitem_title_language":"en"}]},"item_type_id":"10002","owner":"14","path":["1724293369364"],"pubdate":{"attribute_name":"公開日","attribute_value":"2024-11-11"},"publish_date":"2024-11-11","publish_status":"0","recid":"2000330","relation_version_is_last":true,"title":["Porosity Effect in the Core Thermal Hydraulics for an Ultra High Temperature Gas-cooled Nuclear Reactor"],"weko_creator_id":"14","weko_shared_id":-1},"updated":"2024-11-13T06:36:17.137436+00:00"}