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2
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68949215117
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Experimental and calculation research of heat generation field and burnup of fuel IRT
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Bushuev A., Haddad Kh., Zubarev V., Portnov A., Shurovskaya M., Kojin A., and Alferov V. Experimental and calculation research of heat generation field and burnup of fuel IRT. Atomnaya-Energiya (Moscow) 88 (2000) 426-431
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Kojin, A.6
Alferov, V.7
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3
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68949212997
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CIAE safety analysis report (SAR) for the Syrian Miniature Neutron Source Reactor, China
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CIAE safety analysis report (SAR) for the Syrian Miniature Neutron Source Reactor, China, 1993.
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4
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68949205693
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Comparison of experimentally determined fission product activities Pf. Rossendrof research reactor spent fuel with ORIGEN-JR calculations
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Germany, 9-11 May
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Franke, E., Giera, H.-D., Hofman, G., 1995. Comparison of experimentally determined fission product activities Pf. Rossendrof research reactor spent fuel with ORIGEN-JR calculations. In: Proceedings of 17th Annual Symposium on Safeguards and Nuclear Material Management, ESARDA, Germany, 9-11 May.
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Franke, E.1
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5
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0019337147
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Gamma-spectrometric determination of burnup and cooling time of irradiated ECH-1 fuel assemblies
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IAEA, Vienna
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Graber, H., Hofmann, G., Nagel, S., Keddar, A., 1979. Gamma-spectrometric determination of burnup and cooling time of irradiated ECH-1 fuel assemblies. In: Proceedings of Symposium on Nuclear Material Safeguards, IAEA, Vienna, vol. 1, pp. 353-368.
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Graber, H.1
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6
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68949215116
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High resolution gamma ray spectroscopy measurements of spent fuel
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IAEA, Vienna, 14-18 March, Vienna, pp
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Hankansson, A., Basklin, A., 1994. High resolution gamma ray spectroscopy measurements of spent fuel. In: Proceedings of a Symposium on Internet Safeguards Organised in Cooperation with the American Nuclear Society Technology. IAEA, Vienna, 14-18 March, vol. 2, Vienna, pp. 439-449.
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Hankansson, A.1
Basklin, A.2
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7
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0040995402
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Safeguards verification of spent materials testing reactor (MTR) fuel using gamma-ray spectrometry
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IAEA, Vienna
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Hanna, L., 1979. Safeguards verification of spent materials testing reactor (MTR) fuel using gamma-ray spectrometry. In: Proceedings of Symposium on Nuclear Material Safeguards. IAEA, Vienna, vol. 1, pp. 369-386.
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Hanna, L.1
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68949220909
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IAEA-TECDOC-633. Determination of Research Reactor Fuel Burnup. IAEA, Vienna, 1992.
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IAEA-TECDOC-633. Determination of Research Reactor Fuel Burnup. IAEA, Vienna, 1992.
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10
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68949221778
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JEF-PC Version 2. A PC program for displaying data from the joint evaluated file (JEF) library, 1997
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JEF-PC Version 2. A PC program for displaying data from the joint evaluated file (JEF) library, 1997.
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11
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1642487720
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Calculation of the top beryllium shim plate worths for the Syrian miniature neutron source reactor
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Khattab K., and Khamis I. Calculation of the top beryllium shim plate worths for the Syrian miniature neutron source reactor. Progress in Nuclear Energy, UK 44 1 (2004) 33-42
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Khattab, K.1
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0025326141
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Investigation of gamma and neutron fields around spent reactor fuel by sup 1 sup 1 sup 5 In activation
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Lakosi L., Nemeth Z.S., Pavlicsek I., and Veres A. Investigation of gamma and neutron fields around spent reactor fuel by sup 1 sup 1 sup 5 In activation. Applied Radiation and Isotopes 41 2 (1990) 131-137
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44949290520
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Nondestructive assay of fission products in spent-fuel assemblies using gamma and photoneutron activation
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Lakosi L., and Veres A. Nondestructive assay of fission products in spent-fuel assemblies using gamma and photoneutron activation. Nuclear Instruments and Methods in Physics Research Section A 299 1-3 (1990) 463-467
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Nemeth Z., Veres A., Pavlicsk I., and Lakosi L. Gamma-ray activation and passive neutron methods for nondestructive assay of spent-fuel assemblies. Nuclear Science and Engineering 105 3 (1990) 233-243
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0004048298
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Neutron Fluence Measurements
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Neutron Fluence Measurements, 1970. IAEA, Technical Reports Series No. 107, Vienna.
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Reilly, D., Ensslin, N., Smith, H., Kreiner, Jr. (Eds.), 1991. Passive nondestructive assay of nuclear material, Los Alamos National Lab., United States.
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