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Current situation of preparation for fuel removal from the Spent Fuel Pool of Fukushima Daiichi Nuclear Power Station Unit 3 福岛第一核电站3号机组乏燃料池燃料清除准备现状
Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.3327/jaesjb.59.1_28
K. Yamaguchi
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引用次数: 0
Development of Security and Safety Fuel for Pu-burner HTGR 钚燃烧器HTGR安全与安全燃料的研制
Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.1299/MEJ.18-00084
K. Okamoto
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引用次数: 4
Development of Security and Safety Fuel for Pu-burner HTGR 钚燃烧器HTGR安全与安全燃料的研制
Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.1115/ICONE25-66907
M. Nakano
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引用次数: 0
2)On Numerical Models for Mechanical behavior of Rock Mass 2)岩体力学行为数值模型研究
Atomic Energy Society of Japan Pub Date : 2016-02-22 DOI: 10.3327/jaesjb.58.8_489
T. Kyoya
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引用次数: 0
Development of Hydrogen Treatment System in Severe Accident 重大事故氢处理系统的研制
Atomic Energy Society of Japan Pub Date : 2016-02-22 DOI: 10.1115/ICONE25-66707
C. Iwaki
{"title":"Development of Hydrogen Treatment System in Severe Accident","authors":"C. Iwaki","doi":"10.1115/ICONE25-66707","DOIUrl":"https://doi.org/10.1115/ICONE25-66707","url":null,"abstract":"1. 緒言 シビアアクシデント時の水素処理装置開発において、これまで球形に成型した金属酸化物を充填した反 応器の水素処理特性を試験してきたが、実機適用においては反応を阻害する要因の影響評価が必要であ る。そこで、反応阻害要因のうち最も重要と考えられる水蒸気の影響を評価するための試験を実施した。 また、水蒸気の影響を考慮した反応器評価モデルを作成し、積算水素処理量の予測精度を評価した。 2. 反応器特性試験および評価 2-1. 試験装置 試験装置は主に、水素、水蒸気及び窒素を所定の流量比で 混合する混合器、混合ガスの予熱器、反応器試験体より構成 される。反応器試験体として、内径 65.9mm、高さ 600mm の ステンレス管の内部にφ2.0mmの CuO を充填したものを使用 した。反応器内に熱電対を、反応器入口・出口に水素濃度計 を設置して水素処理量を算出した。 2-2. 試験結果 圧力 0.17MPa、ガス流量 62L/min、水蒸気濃度 33vol%で試 験した時の水素濃度の時系列変化を図1に示す。ガスが供給 されると金属酸化物と水素との反応が開始し、反応器試験体 出口水素濃度が 0vol%となった。別途計測した反応器内温度 分布から、入口部より金属酸化物は反応熱によって約 600°Cま で温度上昇し、高温域(反応域)が徐々に出口側へ移行する ことを確認している。出口近傍の金属酸化物の温度低下とと もに、約 9400 秒から出口水素濃度が上昇し(図1)、やがて 反応が終了した。ガス温度、水素及び水蒸気濃度をパラメー タとした試験を実施したところ、出口水素濃度及び金属酸化 物の最高温度はこれらの条件に大きく依存した。そこで水素 処理性能を評価するため反応終了までの積算水素処理量を計 算したところ、図2に示すように、相対湿度が低いほど、ま たガス温度が高いほど積算水素処理量は増加することがわか った。 2-3. 反応器評価モデル 質量保存式とエネルギー保存式を基礎式とし、水素処理速度式を組込んだ一次元の反応器評価モデルを、 水蒸気の影響を考慮して修正した反応速度式を用いて改良し、解析結果を試験結果と比較した。その結 果、積算水素処理量を誤差約 30%以下で予測することを確認した。 3. 結論 反応器の水素処理特性試験により、水蒸気混在の条件でも水素処理が可能であること、積算水素処理量は相対 湿度に依存することがわかった。また水蒸気の影響を評価可能な反応器評価モデルを作成し、水蒸気混在条件 における水素処理量予測の目途を得た。 なお、本件は経済産業省平成 28 年度発電用原子炉等安全策高度化技術基盤整備事業(シビアアクシデント時の水素処理システムの開 発に向けた基盤整備)の成果の一部である。 参考文献 [1]岩城ら、「シビアアクシデント時の水素処理システムの開発(5)」、日本原子力学会 2016 年春の大会、1I14 [2]香月ら、「過酸化金属による水素処理特性評価」、日本機械学会、第 21 回動力・エネルギー技術シンポジウム、E212(2016) [3]山田ら、「シビアアクシデント時の水素処理システムの開発(8)」、日本原子力学会 2017 年秋の大会(投稿中) Chikako Iwaki, Tsukasa Sugita, Akira Yamada, Motoshige Yagyu, Yoshiko Haruguchi and Masashi Tanabe TOSHIBA Corporation 図1 水素濃度及び水素処理速度の試験結果","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"64 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2016-02-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82044752","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
Development of a high efficiency multi-nuclide aerosol filters for radiation protection during a process of cutting core debris 高效多核素气溶胶过滤器的研制，用于岩心碎片切割过程中的辐射防护
Atomic Energy Society of Japan Pub Date : 2016-02-22 DOI: 10.1299/jsmepes.2016.21.B211
Daisuke Akiyama
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引用次数: 2
3)General discussion 3)一般讨论
Atomic Energy Society of Japan Pub Date : 2016-02-22 DOI: 10.1515/9783111352213-005
N. Sekimura
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引用次数: 0
2)Development of Muography Detector for Underground Cavity Survey 地下洞室测量专用成像探测器的研制
Atomic Energy Society of Japan Pub Date : 2016-02-22 DOI: 10.3327/jaesjb.58.9_568
T. Kin
{"title":"2)Development of Muography Detector for Underground Cavity Survey","authors":"T. Kin","doi":"10.3327/jaesjb.58.9_568","DOIUrl":"https://doi.org/10.3327/jaesjb.58.9_568","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"128 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2016-02-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86309548","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Estimation of Redox Condition of Simulated High-level Waste Glass Based on the Chemical Composition of Crystalline Phases of Platinum-group Elements 基于铂族元素晶相化学组成的模拟高放废玻璃氧化还原条件估算
Atomic Energy Society of Japan Pub Date : 2016-01-01 DOI: 10.3327/TAESJ.J15.007
T. Sugawara, T. Ohira, Satoshi Komamine, E. Ochi
{"title":"Estimation of Redox Condition of Simulated High-level Waste Glass Based on the Chemical Composition of Crystalline Phases of Platinum-group Elements","authors":"T. Sugawara, T. Ohira, Satoshi Komamine, E. Ochi","doi":"10.3327/TAESJ.J15.007","DOIUrl":"https://doi.org/10.3327/TAESJ.J15.007","url":null,"abstract":"Toru SUGAWARA, Toshiaki OHIRA, Satoshi KOMAMINE and Eiji OCHI Center for Engineering Science, Akita University, 1-1 Tegatagakuenmachi, Akita-shi, Akita 010-8502, Japan Research and Development Department, Reprocessing Business Division, Japan Nuclear Fuel Limited, 4-108 Okitsuke, Obuchi, Rokkasho-mura, kamikita-gun, Aomori 039-3212, Japan (Received June 26, 2015 and accepted in revised form September 18, 2015; published online February 2, 2016)","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"21 1","pages":"43-52"},"PeriodicalIF":0.0,"publicationDate":"2016-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89033047","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
290℃および320℃でのニッケル基合金の応力腐食割れ感受性に及ぼすPWR一次系模擬水中溶存水素濃度の影響 PWR一次系统模拟水中溶化水浓度对290℃和320℃镍基合金应力腐蚀裂纹感受性的影响
Atomic Energy Society of Japan Pub Date : 2016-01-01 DOI: 10.3327/TAESJ.J14.041
Takaaki Kobayashi, T. Yonezawa, K. Dozaki, K. Hisamune, Wataru Sugino, Kenji Sato
{"title":"290℃および320℃でのニッケル基合金の応力腐食割れ感受性に及ぼすPWR一次系模擬水中溶存水素濃度の影響","authors":"Takaaki Kobayashi, T. Yonezawa, K. Dozaki, K. Hisamune, Wataru Sugino, Kenji Sato","doi":"10.3327/TAESJ.J14.041","DOIUrl":"https://doi.org/10.3327/TAESJ.J14.041","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"69 1","pages":"21-31"},"PeriodicalIF":0.0,"publicationDate":"2016-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74221245","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
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