Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life
'
Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life' 의 참고문헌
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The study of physics and thermal characteristics for in-hospital neutron irradiator (IHNI)
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The feasibility study of 177Lu production in Miniature Neutron Source Reactors using a multi-stage approach in Isfahan
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The Iranian MNSR Safety Analysis Report (SAR)
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Reactivity cost for different top reflector materials in miniature neutron source reactors
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Parametric tests and measurements after shimming of a Beryllium reflector in a miniature neutron source reactor (MNSR)
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Neutronics-design modification of the Syrian miniature neutron source reactor
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Monte Carlo simulation of core physics parameters of the Syrian MNSR reactor
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Monte Carlo N-particle Transport Code System Manual
[2000]
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Miniature neutron source reactor burn up calculations using IRBURN code system
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Miniature Neutron Source Reactors in medical research: achievements and challenges
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Measurement of the fast neutron flux in the MNSR inner irradiation site
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MNSR Accident (Event) Analysis
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IAEA Safety of Research Reactors
[2016]
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General Description of Miniature Neutron Source Reactor
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Design and optimization of the new LEU MNSR for neutron radiography using thermal column to upgrade thermal flux
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Conceptual design study of the low power and LEU medical reactor for BNCT using in-tank fission converter to increase epithermal flux
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Code of Conduct on the Safety and Security of Radioactive Sources
[2004]
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Calculations of the thermal and fast neutron fluxes in the Syrian miniature neutron source reactor using the MCNP-4C code
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Calculation and experiment of adding top beryllium shims for Iran MNSR
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Analysis of core life-time and neutronic parameters for HEU and potential LEU/MEU fuels in a typical MNSR
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A comparative neutronic study of the standard HEU core and various potential LEU alternatives for a typical MNSR system
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Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life'
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