Search Results 1-20 of 257

  • Erratum for "Verbal Expressions of Risk Communication: A Case Study After the 3.11 Crisis" (Vol.9, pp. 644-652, 2014)

    Okamoto Shinichiro , Kikkawa Toshiko

    … response to the inquiry to our article, the authors would like to specify the information sources for the following four citations in our article (Citations 12, 15, 18, and 23):</p><br><p>Citation #12:</p><p>(As for the conflict of domestic laws with international treaties,) We conducted the discharge of contaminated water because, after we had consulted the Nuclear and Industrial Safety Agency and the Nuclear Safety Committee, it was judged to cause no problem in the light of domestic …

    Journal of Disaster Research 16(2), 298-298, 2021

    J-STAGE 

  • Subcriticality-from basics to applications (5):Criticality approach monitoring for the fuel debris in Fukushima Dai-ichi Nuclear Power Plants  [in Japanese]

    Hayashi Yamato , Kano Shinya , Wada Satoshi

    <p> 福島第一原子力発電所において計画されている燃料デブリの取り出し作業においては,燃料デブリの臨界近接を監視する計画としている。本稿では,燃料デブリ取り出し作業における臨界近接監視の考え方と技術開発の状況を説明する。</p>

    Journal of the Atomic Energy Society of Japan 62(2), 89-93, 2020

    J-STAGE 

  • Subcriticality-from basics to apprications (4):Criticality Safety and Subcriticality  [in Japanese]

    Yamane Yuichi

    <p> 核燃料物質を取り扱う施設特有のリスクに対して「安全」を保つための考え方や技術が「臨界安全」である。臨界安全において第一に重要なことは未臨界を保つことであり,その要点は未臨界である条件を明白にしてそれを守ることにある。そのために中性子の漏れや吸収の効果を利用して臨界安全管理を行う。今後の課題の一つとして,事故時の未臨界条件を明らかにするために,不均一な体系の物質分布の計算モデルの …

    Journal of the Atomic Energy Society of Japan 62(1), 42-46, 2020

    J-STAGE 

  • Study of the screening survey using an ambient dose equivalent rate survey meter in criticality accidents (The 9th International Symposium on Radiation Safety and Detection Technology (ISORD-9))

    Hoshi Katsuya , Tsujimura Norio , Yoshida Tadayoshi , Kurihara Osamu , Kim Eunjoo , Yajima Kazuaki

    Progress in nuclear science and technology 6, 152-155, 2019-01

  • Subcriticality - from basics to applications (1):Revisiting subcriticality  [in Japanese]

    Endo Tomohiro , Tsujimoto Kazufumi , Yamamoto Akio

    <p> 臨界管理や原子炉の運転等において,体系の中性子実効増倍率は最も基本的な概念の一つである。実効増倍率が1のときを臨界,1未満のときを未臨界と呼ぶことは良く知られているが,実は両者は大きく異なる状態である。本連載講座では,核燃料サイクル施設の臨界安全,原子炉施設の臨界管理や福島第一原子力発電所のデブリ取り出し等で重要となる未臨界状態について,臨界状態の原子炉との違い,炉物理的な特徴 …

    Journal of the Atomic Energy Society of Japan 61(10), 734-738, 2019

    J-STAGE 

  • Widening Narrow Alleys to Enhance Response Efficiency for Fire Emergency from the Perspective of Urban Roadway Network Analysis

    CHEN Po-An , WU Hsuan-Ting , HSU Yu-Ting

    … <p>Narrow alleys serve as the key factor of fire safety in urban areas. … In light of the frequent and repeated fire accidents due to such situation, this research seeks to address the issue of urban fire safety by considering measures to widen narrow alleys or designate emergency passages. … Subsequently, the reduction of firefighting response time and the enhancement of overall area fire safety are analyzed. …

    Journal of the Eastern Asia Society for Transportation Studies 13(0), 2598-2613, 2019

    J-STAGE 

  • OPTIMIZATION OF A DRY, MIXED NUCLEAR FUEL STORAGE ARRAY FOR NUCLEAR CRITICALITY SAFETY

    Tokuhiro Akira , Baranko Benjamin

    … Nuclear criticality safety is maintained primarily by moderation control and through (spatial) control of neutron interaction and leakage provided by the established geometry. … This creates a concern since the entire remaining facility storage capacity cannot be utilized without exceeding the minimum subcritical (safe) state (ksafe) for ensuring nuclear criticality safety. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 2327, 2019

    J-STAGE 

  • ENHANCED NUCLEAR SAFETY OF SPENT FUEL

    Zavorka Jiri , Lovecky Martin , Jirickova Jana , Skoda Radek

    Criticality safety analysis of highly enriched nuclear fuels requires sophisticated calculation techniques like burnup credit in order to show that fuel reactivity is below legislative limits. … This study shows a concept for enhanced nuclear safety of spent fuel. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1906, 2019

    J-STAGE 

  • STUDY ON LOSS-OF-COOLING AND LOSS-OF-COOLANT ACCIDENTS IN SPENT FUEL POOL, (1) OVERVIEW

    Kaji Yoshiyuki , Watanabe Satoshi , Nemoto Yoshiyuki , Nagatake Taku , Yoshida Hiroyuki , Tojo Masayuki , Goto Daisuke , Nishimura Satoshi , Suzuki Hiroaki , Yamato Masaaki

    … Effectiveness of considerable safety measures against SFP accident has to be investigated. … In addition, threedimensional criticality analysis method was developed as well, and safer loading pattern of spent fuelsin SFP was investigated. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1343, 2019

    J-STAGE 

  • NUMERICAL INVESTIGATIONS AND ANALYSES ON DEBRIS BED COOLABILITY AND RE-CRICALITY FOR JAPAN SODIUM COOLED FAST REACTOR (JSFR)

    LI Chun-Yen , TAKATA Takashi , OKAMOTO Koji

    … The in-vessel retention (IVR) of core disruptive accident(CDA) is of prime importance in enhancing safety characteristics of Japan Sodium Cooled Fast Reactor (JSFR). … therefore, re-criticality calculations via MCNP4 were also considered based on the alternative types of debris bed. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1319, 2019

    J-STAGE 

  • DEVELOPMENT OF A HANDY CRITICALITY ANALYSIS TOOL FOR FUEL DEBRIS

    Tada Kenichi

    … The criticality safety of fuel debris is imperative to prevent radiation exposure of workers. … To prevent the criticality accident, the estimation of criticality of fuel debris is required for the fuel debris retrieval. … Though the expert knowledge of reactor physics is necessary to estimate the criticality of fuel debris, many people who make a plan of fuel debris retrieval may not know well about criticality analysis. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1151, 2019

    J-STAGE 

  • ORGAN DOSE CALCULATIONS USING ICRP ADULT VOXEL PHANTOMS AND TRIPOLI-4 MONTE CARLO CODE

    Lee Yi-Kang

    … The TRIPOLI-4 Monte Carlo radiation transport code has been widely used in radiation shielding, criticality safety and reactor physics fields for supporting French nuclear energy research and industrial applications. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1069, 2019

    J-STAGE 

  • International conference on computing, networking and communications 2015  [in Japanese]

    Nauchi Yasushi , Takezawa Hiroki , Tonoike Kotaro

    <p> 臨界安全国際会議ICNC2015が2015年9月に米国で開催された。冒頭の全体会合では,臨界安全を確実に実施しつつ進歩させるために,人材育成や知識継承が目下の課題であることが強調された。本報告では,解析コード・核データ,臨界安全管理実務,標準・評価手法整備,使用済燃料の臨界安全,不確かさ・感度解析,臨界実験,臨界事故評価,専門家育成,及び核分裂性物質の保管・輸送・処分の9つの口 …

    Journal of the Atomic Energy Society of Japan 58(4), 247-252, 2016

    J-STAGE 

  • Criticality Assessment of Metals for Japan’s Resource Strategy

    Hatayama Hiroki , Tahara Kiyotaka

    Criticality assessment of metals has been developed to analyze a country’s supply risk and vulnerability to supply restriction. … This study presents Japan’s criticality of 22 metals during 2012. … In addition, a new analytic method included mineral interest sufficiency as a criticality component. …

    MATERIALS TRANSACTIONS 56(2), 229-235, 2015

    J-STAGE 

  • ICONE23-1948 A STUDY ON CHARACTERISTICS OF MOLTEN POOL SLOSHING IN CORE DISRUPTIVE ACCIDENTS OF FAST REACTORS

    TATEWAKI Isao , MORITA Koji , ENDO Hiroshi

    … To understand the mechanism of maximum energy released in core disruptive accidents (CDAs) of sodium-cooled fast reactors (SFRs), we investigated behavior of whole core molten fuel pool using a fast reactor safety analysis code. … Several high reactivity insertions and power peaks due to super prompt criticality appears by radial pool sloshing motion. … We noticed that the pool motion suppressed at the super prompt criticality in series of analysis. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23(0), _ICONE23-1-_ICONE23-1, 2015

    J-STAGE 

  • ICONE23-1814 AUTOMATIC OPTIMIZED WIELANDT'S ACCELERATION METHOD OF SOURCE CONVERGENCE FOR MONTE CARLO CRITICALITY CALCULATION

    Yan Yawen , Song Jing , Zheng Huaqing , Hao Lijuan , Hu Liqin

    … Slow source convergence of Monte Carlo criticality calculation is a significant problem. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23(0), _ICONE23-1-_ICONE23-1, 2015

    J-STAGE 

  • ICONE23-1651 IMPACT ON BURNUP PERFORMANCE OF COATED PARTICLE FUEL DESIGN IN PEBBLE BED REACTOR WITH ROX FUEL

    Ho Hai Quan , Obara Toru

    … The pebble bed reactor (PBR), a kind of high-temperature gas-cooled reactor (HTGR), is expected to be among the next generation of nuclear reactors as it has excellent passive safety features, as well as online refueling and high thermal efficiency. … Criticality and core burnup calculations were performed by MCPBR code using the JENDL-4.0 library. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23(0), _ICONE23-1-_ICONE23-1, 2015

    J-STAGE 

  • ICONE23-1626 Application of Integral Kinetic Model to Transient Analysis of Different Types of Weakly Coupled Systems

    Tuya Delgersaikhan , Kikuchi Haruka , Obara Toru

    … An integral kinetic model was used to perform a transient analysis for possible criticality accidents in different types of weakly coupled systems, showing the potential of this method for general coupled systems. … It was concluded from this study that the integral kinetic model can further be applied to other coupled systems and can provide important characteristics of the criticality accident of such systems. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23(0), _ICONE23-1-_ICONE23-1, 2015

    J-STAGE 

  • ICONE23-1497 FIRST ANALYSIS OF LOCAL FUEL-COOLANT INTERACTIONS IN A MOLTEN POOL BY SIMMER-III USING REACTOR MATERIALS

    CHENG Songbai , MATSUBA Ken-ichi , ISOZAKI Mikio , KAMIYAMA Kenji , SUZUKI Tohru , TOBITA Yoshiharu

    … Analyses of severe accidents for sodium-cooled fast reactors have shown that by assuming pessimistic conditions the accident might proceed into a transition phase where a large whole-core-scale pool containing sufficient fuel to exceed prompt criticality by fuel compaction might be formed. … the pressure buildup) was investigated using the SIMMER-III, an advanced fast reactor safety analysis code. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23(0), _ICONE23-1-_ICONE23-1, 2015

    J-STAGE 

Page Top