Reactor

Results: 8433



#Item
861

Failure Knowledge DatabaseSelected Cases Leakage of Sodium Coolant from Secondary Cooling Loop in Prototype Fast Breeder Reactor MONJU Dec. 8th, 1995, Tsuruga, Fukui pref. KOBAYASHI, Hideo (Tokyo Institute of Tec

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Source URL: www.sozogaku.com

Language: English - Date: 2011-03-25 06:15:03
    862

    SGTR ANALYSES FOR KRŠKO FULL SCOPE SIMULATOR VERIFICATION Iztok Parzer, Boštjan Končar, Andrej Prošek “Jožef Stefan” Institute Reactor Engineering Division Jamova 39, 1000 Ljubljana, Slovenia

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    Source URL: www.djs.si

    Language: English - Date: 2001-09-28 08:29:41
      863

      THE PHYSICS SCALE MODEL PROJECT OF TWO-CASCADE POWER BLANKET FOR ELECTRONUCLEAR REACTOR N.V. Zavyalov, V.F. Kolesov, A.V. Telnov, Yu.A. Khokhlov Russian Federal Nuclear Center – All-Russia Scientific Research Institute

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      Source URL: www.kipt.kharkov.ua

      Language: English - Date: 2009-07-14 07:19:52
        864

        Application of burnable absorbers in an accelerator driven system Jan Wallenius, Kamil Tuˇcek, Johan Carlsson, Waclaw Gudowski Department of Nuclear & Reactor Physics Royal Institute of TechnologyStockholm, Swed

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        Source URL: neutron.kth.se

        Language: English
          865

          Reactor Accident Costs; Fukushima & Three Mile Island

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          Source URL: www-pub.iaea.org

          Language: English - Date: 2013-02-01 07:12:16
            866

            Operation and Exploitation of the Reactor, Dosimetry (RPI) and Reactor Calculations A.J.G. Ramalho, I.C. Gonçalves, N.P. Barradas The central objective of the operation and exploitation of the reactor is to be able to s

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            Source URL: www.itn.pt

            Language: English - Date: 2011-08-03 10:30:26
              867

              Kyoto University Research Reactor Institute International Symposium on Radiological Issues for

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              Source URL: www.rri.kyoto-u.ac.jp

              Language: English - Date: 2014-09-02 20:01:00
                868

                Optimization of an Integrated Neutronic/Thermal-Hydraulic Reactor Core Analysis Model A.G. Mylonakis1,2 1 National Centre for Scientific Research “Demokritos”, Institute for Nuclear and Radiological Sciences, Energy,

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                Source URL: www.djs.si

                Language: English - Date: 2015-02-07 16:50:43
                  869

                  Proceedings of the 7th Conference on Nuclear and Particle Physics, 11-15 Nov. 2009, Sharm El-Sheikh, Egypt BURNUP AND CRITICALITY ANALYSIS OF CARBON COATED PARTICLE FUEL IN HTR-10 REACTOR Moustafa Aziz and Riham Refeat

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                  Source URL: www.physicsegypt.org

                  Language: English - Date: 2010-12-19 14:19:11
                    870

                    106 The Detection of Hydrogen flakes in the Belgian Doel 3/Tihange 2 Reactor Pressure Vessels – Overview of Technical Developments to support Restart Justification

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                    Source URL: www.nss.si

                    Language: English - Date: 2014-07-21 14:38:27
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