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Thermal-hydraulic Aspects of the Use of Low Enrichment Uranium Fuel in the MIT Research Reactor
Language: en
Pages: 304
Authors: Joseph B. Gehret
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Type: BOOK - Published: 1984 - Publisher:

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Thermal Hydraulics Analysis of the MIT Research Reactor in Support of a Low Enrichment Uranium (LEU) Core Conversion
Language: en
Pages: 290
Authors: Yu-Chih Ko (Ph. D.)
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Type: BOOK - Published: 2008 - Publisher:

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The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density m
Thermal Hydraulic Limits Analysis for the Massachusetts Institute of Technology Research Reactor Low Enrichment Uranium Core Conversion Using Statistical Propagation of Parametric Uncertainties
Language: en
Pages: 171
Authors: Keng-Yen Chiang
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Type: BOOK - Published: 2012 - Publisher:

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The MIT Research Reactor (MITR) is evaluating the conversion from highly enriched uranium (HEU) to low enrichment uranium (LEU) fuel. In addition to the fuel el
Impact Assessment for the MIT Research Reactor Low Enrichment Uranium Fuel Fabrication Tolerances
Language: en
Pages: 109
Authors: Dakota J. Allen
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Type: BOOK - Published: 2020 - Publisher:

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In the framework of non-proliferation policy, the Massachusetts Institute of Technology Reactor (MITR) is planning to convert from highly enriched uranium (HEU)
Evaluation of the Thermal-hydraulic Operating Limits of the HEU-LEU Transition Cores for the MIT Research Reactor
Language: en
Pages: 115
Authors: Yunzhi Diana Wang
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Type: BOOK - Published: 2009 - Publisher:

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The MIT Research Reactor (MITR) is in the process of conducting a design study to convert from High Enrichment Uranium (HEU) fuel to Low Enrichment Uranium (LEU