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Results 1 - 10 of about 66155. Search took: 1.77 seconds.
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Phenix Power Plant Decommissioning Project. Treatment of the Primary Cold Trap
by Deluge, M. (CEA /Marcoule DDCO/SDSP BP 17171 302078 Bagnols Sur Ceze (France))
fromProceedings of the 2007 ANS Topical Meeting on Decommissioning, Decontamination, and Reutilization - DD and R 2007
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Standard procedure for the high temperature structure integrity assessment procedure(draft)/ part I - high temperature structure design guideline
by Jung, Hoan Sung; Park, Y. C.; Ryu, J. S.; Cho, Y. G.; Ahn, S. H.; Wu, S. I.; Lee, Y. S.; Kim, B. S.; Kim, Y. K.; Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
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Increasing of power up-rating of Unit 1 and Unit 2 of the Mochovce NPP
246 KB - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/43/124/43124123.pdf
by Simko, J. (Slovenske elektrarne, JE Mochovce, Mochovce (Slovakia))
fromNUSIM 2008: 16. Annual Nuclear Seminar and Information Meeting
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A novel concept for CRIEC-driven subcritical research reactors
228 KB - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/33/031/33031188.pdf - Text Version
by Nieto, M.; Miley, G.H. (Illinois Univ., Fusion Studies Lab., Dept. of Nuclear, Plasma, and Radiological Engineering, Urbana, IL (United States)); Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)
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Experience with pressuriser for PHT pressure control in TAPP 4 reactor
by Hegde, Rajeev; Gupta, Babita; Kandar, T.K.; Nair, Suma; Chakravarti, A.K. (Nuclear Power Corporation of India Ltd., Nabhikiya Urja Bhavan, Mumbai (India))
fromProceedings of national conference on operating experience of nuclear reactors and power plants: book of preprints
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Level 1 and 2 probabilistic safety assessment technology study and its application in the design of CHASHMA nuclear power plant unit2
by Yan Jinquan; Zhang Qinfang; Qiu Yongping; Zhou Quanfu; Qiu Zhongmin; Chen Song (Shanghai Nuclear Engineering Research and Design Inst., Shanghai (China))
fromProgress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.2--nuclear power sub-volume (Pt.1)
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Science and Service at a University Research Reactor
http://www-pub.iaea.org/MTCD/Publications/PDF/SupplementaryMaterials/TECDOC_1713_CD/template-cd/datasets/papers/Bode%20Science%20and%20Service%20at%20University%20RR%20Feb2011.pdf
by Bode, Peter (Delft University of Technology, Interfaculty Reactor Institute, Delft (Netherlands)), E-mail: P.Bode@tudelft.nl
fromCommercial products and services of research reactors. Proceedings of a technical meeting
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Human factor risk management in nuclear industry
by Abramova, V.N.; Roshchupkina, A.S.; Fedorenko, D.I. (ONITs Prognoz, Obninsk (Russian Federation))
from11-th International conference Nuclear power safety and nuclear education - 2009. Abstracts. Part 1. Session: Safety of nuclear technology; Innovative nuclear systems and fuel cycle; Nuclear knowledge management
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Thermal-hydraulically corrected neutron cross-sections for PWR reactors
404 KB - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/42/109/42109420.pdf - Text Version
by Santiago, Daniela M.N.; Alvim, Antonio C.M.; Silva, Fernando C. (Universidade Federal do Rio de Janeiro (PEN/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Engenharia Nuclear), E-mail: dsantiago@con.ufrj.br, E-mail: alvim@con.ufrj.br, E-mail: fernando@con.ufrj.br; Associacao Brasileira de Energia Nuclear, Rio de Janeiro, RJ (Brazil)
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