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Academic Journal

The Study of Continuous Core Zoning to Extend the Graphite Component Irradiation Lifespan in Molten Salt Reactor.

Subjects: NEUTRON flux; FAST neutrons; NUCLEAR power plants

  • Source: International Journal of Energy Research; 9/12/2024, Vol. 2024, p1-17, 17p

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Academic Journal

Evaluation of the radiation damage parameters of ODS steel alloys in the first wall of deuterium-tritium fusion-fission (hybrid) reactors.

Subjects: *NUCLEAR reactor materials; *NEUTRON temperature; *STEEL alloys

  • Source: International Journal of Energy Research. Jan2018, Vol. 42 Issue 1, p198-206. 9p. 5 Charts, 1 Graph.

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Academic Journal

Fissile utilization of uranium, thorium, and plutonium fuels for a 60 MWt block‐type high‐temperature gas‐cooled reactor.

Subjects: THORIUM; FAST reactors; PLUTONIUM

  • Source: International Journal of Energy Research; 3/25/2022, Vol. 46 Issue 4, p5152-5164, 13p

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Academic Journal

Study on the Applicability of Neutron Radiation Damage Method Used for High-Temperature Superconducting Tape Based on Geant4 and SRIM.

Subjects: HIGH temperature superconductors; RADIATION damage; SUPERCONDUCTORS

  • Source: Science & Technology of Nuclear Installations; 11/24/2021, p1-9, 9p

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Academic Journal

Neutronic and burn‐up calculations of the (ThO2‐UO2) pin cell benchmark using DRAGON5 and MCNP6.2 codes with ENDF/B‐VIII.0 nuclear data library.

Subjects: DATA libraries; PRESSURIZED water reactors; FISSION products

  • Source: International Journal of Energy Research; 6/25/2021, Vol. 45 Issue 8, p11538-11551, 14p

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Academic Journal

Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code.

Subjects: FAST reactors; CORE materials; MODULAR design

  • Source: International Journal of Energy Research; 6/25/2021, Vol. 45 Issue 8, p12071-12085, 15p

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Academic Journal

Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum.

Subjects: FAST reactors; MATERIALS testing reactors; NEUTRON temperature

  • Source: Science & Technology of Nuclear Installations; 9/2/2018, p1-16, 16p

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Academic Journal

Preliminary design of a medium‐power modular lead‐cooled fast reactor with the application of optimization methods.

Subjects: FAST reactors; NUCLEAR reactor design & construction; MATHEMATICAL optimization

  • Source: International Journal of Energy Research; Sep2018, Vol. 42 Issue 11, p3643-3657, 15p, 3 Color Photographs, 3 Diagrams, 2 Charts, 16 Graphs

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Academic Journal

Determination of the Activity Inventory in the Structural Components of the Dalat Nuclear Research Reactor for Its Decommissioning Planning.

Subjects: NUCLEAR research; RESEARCH reactors; NUCLEAR reactors

  • Source: Science & Technology of Nuclear Installations; 5/18/2022, p1-10, 10p

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Academic Journal

Conceptual Engineering of CARA Fuel Element with Negative Void Coefficient for Atucha II.

Subjects: NUCLEAR fuel elements; NUCLEAR energy; NUCLEAR power plants

  • Source: Science & Technology of Nuclear Installations; 2011, Vol. 2011, p1-9, 9p

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  • 1-10 of  10 results for ""NEUTRON temperature""