Search Results 1-20 of 869

  • Development and release of fuel performance code FEMAXI-8  [in Japanese]

    宇田川 豊

    Ατομοσ : journal of the Atomic Energy Society of Japan = アトモス : 日本原子力学会誌 62(10), 555-559, 2020-10

  • Development and release of fuel performance code FEMAXI-8  [in Japanese]

    Udagawa Yutaka

    <p> 核燃料や燃料被覆管のふるまいに係る研究で得られた知見やデータは,燃料挙動解析コードにモデルとして集約され,燃料設計や安全評価に活用されている。著者らは,国産/公開コードであるFEMAXIの最新バージョンFEMAXI-8を開発し,燃料分野における産官学の研究開発をより強力にサポートする技術基盤とすべく,モデル/機能拡充に加え,体系的検証による性能評価を経た標準モデルセットを提供し …

    Journal of the Atomic Energy Society of Japan 62(10), 555-559, 2020

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  • Status of Investigation to Ensure Applicability of ECCS Acceptance Criteria to High-Burnup Fuel  [in Japanese]

    OZAWA Masaaki , AMAYA Masaki

    <p>Light-water reactors (LWRs) are equipped with an emergency core cooling system (ECCS) that is designed to maintain the coolable geometry of the reactor core and finally minimize the release o …

    Transactions of the Atomic Energy Society of Japan 19(4), 185-200, 2020

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  • Analysis of Chemical Contents Spatial Distribution in EUV Resist Using Resonant Soft X-ray Scattering Method

    Tanaka Jun , Ishiguro Takuma , Harada Tetsuo , Watanabe Takeo

    … The EUV resist has to be achieved high resolution, high sensitivity, and low line-width roughness (LWR), simultaneously. … Especially, the resist is required low LWR performance for a fine patterning. … To reduce LWR, it is significant to control and reduce the stochastic behavior of the resist chemical contents such as the functional groups, photo reactive compound (photoacid generators:PAG), additives such as amines and so on. …

    Journal of Photopolymer Science and Technology 33(5), 491-498, 2020

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  • Development of fission product chemistry database ECUME for the LWR severe accident

    MIWA Shuhei , MOHAMAD Afiqa , TAKASE Gaku , KARASAWA Hidetoshi , OSAKA Masahiko , NAKAJIMA Kunihisa , MIYAHARA Naoya , NISHIOKA Shunichiro , SUZUKI Eriko , HORIGUCHI Naoki , LIU Jiazhan , MIRADJI Faoulat , IMOTO Junpei

    … These results have shown the validity and importance of the ECUME application for the more accurate evaluation of FP chemistry during transportation in a reactor under a LWR severe accident.</p> …

    Mechanical Engineering Journal 7(3), 19-00537-19-00537, 2020

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  • Roughness Power Spectral Density as a Function of Aerial Image and Basic Process / Resist Parameters

    Cutler Charlotte , Lee Choong-Bong , Thackeray James W. , Trefonas Peter , Nelson John , DeSisto Jason , Li Mingqi , Rena Rochelle , Mack Chris

    … <p>Linewidth Roughness (LWR) remains a difficult challenge for improvement in all resist materials. … In previous work we focused on the impact of key components of LWR by analyzing the Power Spectral Density (PSD) curves which can be obtained using Fractilia's MetroLER computational software. … We showed there was an important relationship between ArF resist frequency components and LWR through lithographic process (before and after a resist trim step) as a function of resist formulation. …

    Journal of Photopolymer Science and Technology 32(6), 779-790, 2020

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  • On the Complexity of the LWR-Solving BKW Algorithm

    OKADA Hiroki , TAKAYASU Atsushi , FUKUSHIMA Kazuhide , KIYOMOTO Shinsaku , TAKAGI Tsuyoshi

    … applied BKW also to the learning with rounding problem (LWR). … However, it is not shown that his idea is also applicable to LWR. … We also show that Lyubashevsky's idea can be applied to LWR-solving BKW, under a heuristic assumption that is regularly used in the analysis of LPN-solving BKW. … of LWR. … satisfy the equation, the asymptotic time complexity of BKW to solve LWE and LWR are the same.</p> …

    IEICE Transactions on Fundamentals of Electronics, Communications and Computer Sciences E103.A(1), 173-182, 2020

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  • Statistical arguments towards the development of an advanced embrittlement correlation method for reactor pressure vessel materials

    Nakasuji Toshiki , Morishita Kazunori

    An embrittlement correlation method is one of the most important techniques used to ensure the integrity of pressure vessel steels in nuclear power plants. In Japan, the embrittlement correlation meth …

    Journal of Nuclear Science and Technology 57(3), 312-322, 2020

    IR 

  • Roughness Power Spectral Density as a Function of Aerial Image and Basic Process/Resist Parameters

    Cutler Charlotte , Lee Choong-Bong , Thackeray James W. , Trefonas Peter , Nelson John , DeSisto Jason , Li Mingqi , Rena Rochelle , Mack Chris

    Journal of photopolymer science and technology 32(6), 779-790, 2019

  • Proposal of guidelines for structural integrity assessment on thermal aging embrittlement of cast austenitic stainless steel in BWR environment  [in Japanese]

    MIURA Yasufumi , ARAI Taku

    … <p>For the components made by cast austenitic stainless steels in LWR plants, aging management and structural integrity assessment are required in terms of thermal aging embrittlement by 30th year of operation and the evaluation is also required every 10 years after 30 years operation. …

    The Proceedings of the Materials and Mechanics Conference 2019(0), OS1316, 2019

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  • Past and Future of Commercial LWR fuel development  [in Japanese]

    Kusagaya Kazuyuki

    Journal of the Atomic Energy Society of Japan 61(4), 263-264, 2019

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  • Ageing Management for Metallic Components / Structures:Outline of aging evaluations  [in Japanese]

    Arai Taku

    <p> 軽水炉の金属製の機器や構造物は運転中に繰返し荷重負荷,中性子照射,300℃前後の冷却水や蒸気などの環境に曝される。このような環境に曝された場合,疲労,中性子照射脆化,応力腐食割れ,熱時効,腐食などの経年劣化を生じる可能性がある。これらの経年劣化事象が進行すると機器・構造物の健全性が損なわれる可能性があることから,軽水炉を安全に運転するためには,経年劣化事象を適切に管理することが …

    Journal of the Atomic Energy Society of Japan 61(2), 100-102, 2019

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  • EUROPEAN UTILY REQUIREMENTS FOR ADVANCED LWR ISSUE OF EUR REVISION E AND ONGOING ACTIVITIES

    TERNON-MORIN Françoise , JACQUART Guillaume , KYMÄLÄINEN Olli , FERRARO Giovanni

    … Since 1991, the European Utility Requirements (EUR), Organization has been actively developing and promoting harmonized technical specifications for advanced LWR designs in Europe gathered into a unique EUR Document. … The first one is to develop new Position Papers and harmonized requirements representing up-to-date European Utilities positions related to new LWR projects, especially innovative designs such as Small Modular LWR (SMLWR). …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 2198, 2019

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  • FUELING RPS WITH MEDIUM AND MEDIUM HEAVY METAL ISOTOPES FROM FRESH SPENT NUCLEAR FUEL OF LWR

    Zhou Yangping , Gu Zhengwei , Li Zhengcao , Shi Lei , Dong Yujie , Zhang Zuoyi

    All energy systems, including nuclear energy systems, are facing the challenge for economy and environment protection which are now closely related. In order to improve the economy of nuclear energy a …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1977, 2019

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  • DEVELOPMENT OF FISSION PRODUCT CHEMISTRY DATABASE ECUME FOR THE LWR SEVERE ACCIDENT

    Miwa Shuhei , Mohamad Afiqa , Takase Gaku , Karasawa Hidetoshi , Osaka Masahiko , Miyahara Naoya , Nakajima Kunihisa , Nishioka Shunichiro , Suzuki Eriko , Horiguchi Naoki , Liu Jiazhan , Miradji Faoulat , Imoto Junpei

    … These results have shown the validity and importance of the ECUME application for the more accurate evaluation of FP chemistry during transportation in a reactor under a LWR severe accident. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1993, 2019

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  • DEVELOPMENT OF EVALUATION METHOD FOR AEROSOL PARTICLE DEPOSITION IN A REACTOR BUILDING BASED ON CFD

    Horiguchi Naoki , Miyahara Naoya , Uesawa Shin-ichiro , Yoshida Hiroyuki , Osaka Masahiko

    … For source term evaluation from reactor buildings (RBs) in LWR severe accidents (SAs), we have launched to develop an evaluation method of FP aerosol particle deposition onto surfaces of internal structures in an RB based on computational fluid dynamics (CFD). …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 2158, 2019

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  • IMPACT OF VESSEL GEOMETRY AND BOUNDARY CONDITION ON THE HEAT TRANSFER OF LIQUID CORIUM IN LWR LOWER HEAD

    Gaus-Liu Xiaoyang

    … During the course of a postulated severe accident in a LWR reactor a melt pool is accumulated in the lower head of the reactor vessel. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1891, 2019

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  • Ablation Analysis with MPS for Proposing Ex-Vessel Corium Spreading Management in Light Water Reactors

    Katta Masafumi , Yamaji Akifumi , Duan Guangtao , Furuya Masahiro

    … In a postulated sever accident of a light water reactor (LWR), molten core debris (corium) may breach the reactor pressure vessel and be released to the ex-vessel containment floor. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1728, 2019

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  • INTRODUCING PASSIVE NUCLEAR SAFETY IN WATER-COOLED REACTORS - NUMERICAL SIMULATION AND VALIDATION OF NATURAL CONVECTION HEAT TRANSFER AND TRANSPORT IN PACKED BEDS OF HEATED MICROSPHERES

    O. Noah Olugbenga , F. Slabber Johan , P. Meyer Josua

    … Current light water reactors (LWR) designs have been optimized over decades, and required improvements cannot be based on mere redesign but will require novel technologies. … This will ensure retention of radioactive fission products by the fuel making LWR attain a passive safety status and among other advantages, higher fuel enrichment in the proposed nuclear fuel will provide higher burn-up. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1383, 2019

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  • DEVELOPMENT OF A COUPLED NEUTRONICS AND THERMAL HYDRAULICS CODE WITH AN ADVANCED SPATIAL MAPPING MODEL

    Kang Huilun , Tian Zhaofei , Li Lei , Chen Guangliang , Jin Yuguan

    … Multi-physics coupling schemes between 3D transport and sub-channel thermal hydraulic are needed to improve the design methodologies and the prediction of local safety margins for both LWR and innovative reactors. …

    The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27(0), 1310, 2019

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