Found: 10
Select item for more details and to access through your institution.
Comparison of uranium plutonium nitride (U-Pu-N) and thorium nitride (Th-N) fuel for 500 MWth gas-cooled fast reactor (GFR) long life without refueling.
- Published in:
- International Journal of Energy Research, 2018, v. 42, n. 1, p. 214, doi. 10.1002/er.3923
- By:
- Publication type:
- Article
Optimization of Core Regions and Fuel Fractions for Better Power Peaking Factor of 150, 450 and 1,000 MWth Molten Salt Reactor.
- Published in:
- Trends in Sciences, 2023, v. 20, n. 12, p. 1, doi. 10.48048/tis.2023.6937
- By:
- Publication type:
- Article
Core design selection for a long‐life modular gas‐cooled fast reactor using OpenMC code.
- Published in:
- International Journal of Energy Research, 2022, v. 46, n. 7, p. 9389, doi. 10.1002/er.7812
- By:
- Publication type:
- Article
Fissile utilization of uranium, thorium, and plutonium fuels for a 60 MWt block‐type high‐temperature gas‐cooled reactor.
- Published in:
- International Journal of Energy Research, 2022, v. 46, n. 4, p. 5152, doi. 10.1002/er.7506
- By:
- Publication type:
- Article
Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power.
- Published in:
- International Journal of Energy Research, 2022, v. 46, n. 4, p. 4852, doi. 10.1002/er.7479
- By:
- Publication type:
- Article
Initial core design analysis of lead (208) ‐bismuth eutectic‐cooled reactor with radial fuel shuffling.
- Published in:
- International Journal of Energy Research, 2021, v. 45, n. 8, p. 12317, doi. 10.1002/er.6476
- By:
- Publication type:
- Article
Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code.
- Published in:
- International Journal of Energy Research, 2021, v. 45, n. 8, p. 12071, doi. 10.1002/er.6042
- By:
- Publication type:
- Article
Properties of Oil Palm Empty Fruit Bunch-Filled Recycled Acrylonitrile Butadiene Styrene Composites: Effect of Shapes and Filler Loadings with Random Orientation.
- Published in:
- BioResources, 2017, v. 12, n. 1, p. 1090, doi. 10.15376/biores.12.1.1090-1101
- By:
- Publication type:
- Article
NEUTRONICS ANALYSIS OF UN-PUN FUEL FOR 300 MW PRESSURIZED WATER REACTOR USING SRAC-COREBN CODE.
- Published in:
- EUREKA: Physics & Engineering, 2022, n. 6, p. 12, doi. 10.21303/2461-4262.2022.002247
- By:
- Publication type:
- Article
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material.
- Published in:
- Science & Technology of Nuclear Installations, 2022, p. 1, doi. 10.1155/2022/5300160
- By:
- Publication type:
- Article