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U.S. planning test reactor to run on weapons-grade uranium

Science (American Association for the Advancement of Science), 2023-05, Vol.380 (6647), p.783-783

Cho, Adrian

2023

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Accurate Measurement of the Electron Antineutrino Yield of U235 Fissions from the STEREO Experiment with 119 Days of Reactor-On Data

Physical review letters, 2020-11, Vol.125 (20)

Almazán, H

2020

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The weapons potential of high-assay low-enriched uranium

Science (American Association for the Advancement of Science), 2024-06, Vol.384 (6700), p.1071-1073

2024

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A critical review of the microstructure of U–Mo fuels

Journal of nuclear materials, 2020-11, Vol.540, p.152386, Article 152386

2020

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Conceptual core design and neutronics analysis for a space heat pipe reactor using a low enriched uranium fuel

Nuclear engineering and design, 2022-02, Vol.387, p.111603, Article 111603

2022

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Preliminary study of 300 MWth pressurized water reactor with carbide fuel with addition neptunium 237 using SRAC-COREBN code

AIP Conference Proceedings, 2022, Vol.2663 (1)

2022

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Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium

Progress in nuclear energy (New series), 2018-04, Vol.104, p.75-84

2018

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Post-irradiation examination of U-7Mo/Mg and U-10Mo/Mg dispersion fuels irradiated in the NRU reactor

Journal of nuclear materials, 2022-01, Vol.558, p.153343, Article 153343

2022

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Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part I: Assembly-level analysis

Nuclear engineering and design, 2019-05, Vol.346, p.157-175

2019

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Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd2O3 – UO2 and Al2O3 – B4C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.012061

2024

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Conceptual design of a new space nuclear reactor with low‐enriched uranium fuel based on the optimization of fuel composition and reflector geometry via optimized adaptive neuro‐fuzzy inference system as well as investigation of fresh core cycle length

International journal of energy research, 2022-06, Vol.46 (7), p.9456-9485

2022

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Implications of HALEU fuel on the design of SMRs and micro-reactors

Nuclear engineering and design, 2022-04, Vol.389, p.111648, Article 111648

2022

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Burn‐up calculation of the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle in a Westinghouse small modular reactor

International journal of energy research, 2021-06, Vol.45 (8), p.12013-12028

2021

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Neutronic and thermal-hydraulic fuel design for a dual-salt breed-and-burn molten salt reactor

Nuclear engineering and design, 2021-02, Vol.372, p.110953, Article 110953

2021

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Microscale Isotopic Variation in Uranium Fuel Pellets with Implications for Nuclear Forensics

Analytical chemistry (Washington), 2019-09, Vol.91 (18), p.11598-11605

2019

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Neutronic performance of 208Pb-Bi eutectic-cooled fast reactor with uranium nitride fuel (enriched 15N)

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.012060

2024

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Fuel geometry options for a moderated low-enriched uranium kilowatt-class space nuclear reactor

Nuclear engineering and design, 2018-12, Vol.340, p.122-132

2018

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Low enriched uranium and thorium fuel utilization under once‐through and offline reprocessing scenarios in small modular molten salt reactor

International journal of energy research, 2019-09, Vol.43 (11), p.5775-5787

2019

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Comparative evaluation of the performance of improved genetic algorithms and differential evolution for in-core fuel management of a research reactor

Nuclear engineering and design, 2022-11, Vol.398, p.111953, Article 111953

2022

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Neutronic analysis of the NuScale core using accident tolerant fuels with different coating materials

Nuclear engineering and design, 2021-06, Vol.377, p.111169, Article 111169

2021

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Design of a new Small Modular Nuclear Reactor using TVS-2M Fuel Assemblies and Fuel Depletion analysis during the fresh-core cycle length

Nuclear engineering and design, 2021-12, Vol.385, p.111540, Article 111540

2021

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Micro-tensile testing of the bond line in hot isostatic pressed aluminum

Journal of nuclear materials, 2022-04, Vol.561, p.153532, Article 153532

2022

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Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Journal of nuclear materials, 2017-08, Vol.492 (C), p.195-203

2017

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Investigation of a two-year cycle pressurized water reactor core design with increased enrichment and extended burnup limits

Nuclear engineering and design, 2021-05, Vol.376 (C), p.111132, Article 111132

2021

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Impact of core power density on economics of a small integral PWR

Nuclear engineering and design, 2021-12, Vol.385, p.111488, Article 111488

2021

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U.S. planning test reactor to run on weapons-grade uranium

Accurate Measurement of the Electron Antineutrino Yield of U235 Fissions from the STEREO Experiment with 119 Days of Reactor-On Data

The weapons potential of high-assay low-enriched uranium

A critical review of the microstructure of U–Mo fuels

Conceptual core design and neutronics analysis for a space heat pipe reactor using a low enriched uranium fuel

Preliminary study of 300 MWth pressurized water reactor with carbide fuel with addition neptunium 237 using SRAC-COREBN code

Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium

Post-irradiation examination of U-7Mo/Mg and U-10Mo/Mg dispersion fuels irradiated in the NRU reactor

Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part I: Assembly-level analysis

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd2O3 – UO2 and Al2O3 – B4C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Conceptual design of a new space nuclear reactor with low‐enriched uranium fuel based on the optimization of fuel composition and reflector geometry via optimized adaptive neuro‐fuzzy inference system as well as investigation of fresh core cycle length

Implications of HALEU fuel on the design of SMRs and micro-reactors

Burn‐up calculation of the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle in a Westinghouse small modular reactor

Neutronic and thermal-hydraulic fuel design for a dual-salt breed-and-burn molten salt reactor

Microscale Isotopic Variation in Uranium Fuel Pellets with Implications for Nuclear Forensics

Neutronic performance of 208Pb-Bi eutectic-cooled fast reactor with uranium nitride fuel (enriched 15N)

Fuel geometry options for a moderated low-enriched uranium kilowatt-class space nuclear reactor

Low enriched uranium and thorium fuel utilization under once‐through and offline reprocessing scenarios in small modular molten salt reactor

Comparative evaluation of the performance of improved genetic algorithms and differential evolution for in-core fuel management of a research reactor

Neutronic analysis of the NuScale core using accident tolerant fuels with different coating materials

Design of a new Small Modular Nuclear Reactor using TVS-2M Fuel Assemblies and Fuel Depletion analysis during the fresh-core cycle length

Micro-tensile testing of the bond line in hot isostatic pressed aluminum

Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Investigation of a two-year cycle pressurized water reactor core design with increased enrichment and extended burnup limits

Impact of core power density on economics of a small integral PWR

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