Neutronic performance characteristics of different LEU fuels in a proposed NIST research reactor

Turkoglu, Danyal J.; Wu, Zeyun; Williams, Robert E.; Newton, Thomas H.

doi:10.1016/j.anucene.2019.01.006

Cited by 6 publications

(2 citation statements)

References 9 publications

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“…Monolithic U-Mo fuels have been demonstrated to be attractive candidates because of their low neutron capture cross section, high uranium density, stable irradiation swelling performance (Burkes et al, 2009;Robinson et al, 2013;Mei et al, 2015;Newell et al, 2017). Rectangular fuel assemblies (Brown et al, 2013;Wu et al, 2017) can be made by connecting a number of U-Mo/Al monolithic fuel plates (Cheng et al, 2004;Perez et al, 2011;Robinson et al, 2013;Turkoglu et al, 2019) with an Al alloy frame, using the processing method of rolling-swage. In the reactor cores, dozens of fuel assemblies will be placed into specified positions, and control rod channels are retained among the fuel assemblies (Wu et al, 2017).…”

Section: Introductionmentioning

confidence: 99%

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

et al. 2021

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To obtain the optimized fuel performance, the effects of U-Mo irradiation creep rate coefficient on the thermo-mechanical behavior of a fuel assembly are investigated. In this study, three cases of creep rate coefficient are considered. The distribution and evolution results of temperature, displacement, stress/strain and fuel foil micro-structure are analyzed. The simulation results indicate that with the increase of creep rate coefficient 1) the temperature field in the fuel assembly changes slightly; 2) the maximum out-of-plane displacements in the side plates decrease slightly; the maximum out-of-plane displacements in the fuel plates adjacent to the outside Al plates rise distinctly, induced by the enhanced bending deformation contributions; 3) the peak values of the first principal stresses and skeleton normal stresses in the fuel foils are reduced, while the through-thickness creep strains are enlarged; 4) with an increase of fuel creep rate coefficient from 500 × 10−22 mm3/(fission MPa) to 2,000 × 10−22 mm3/(fission·MPa), the maximum Von Mises stress in the fuel cladding decreases by ∼24% on the 308th day. This work is helpful for advanced fabrication and optimization design of U-Mo/Al fuel assemblies.

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Section: Introductionmentioning

confidence: 99%

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

et al. 2021

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“…Future plans for the NBSR are to convert to low-enriched uranium (LEU) fuel [ 5 ]. The conversion to LEU will result in an anticipated loss of 10 % in neutron flux.…”

Section: Introductionmentioning

confidence: 99%

Progress towards Operation of a Deuterium Cold Neutron Source at the NCNR

Jurns

Middleton

Williams

2020

IOP Conf. Ser.: Mater. Sci. Eng.

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The NIST Center for Neutron Research (NCNR) operates a 20 MW research reactor that produces neutrons for a suite of 30 neutron scattering instruments. 70% of these instruments use cold neutrons (E<5 meV), which are moderated by two separate cold neutron sources. The cold moderator for both sources is liquid hydrogen (LH 2 ), which is in turn cooled by a recently commissioned 7 kW, 14K helium refrigerator. NCNR plans to replace the larger cold source with a new one operating with liquid deuterium (LD 2 ). This report focuses on progress towards the upgrade to liquid deuterium, and options to address the particular challenges of designing and operating a cooling system that simultaneously supports operation with both LH 2 and LD 2 .

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An innovative multi-layer shell model for in-pile thermo-mechanical behavior analysis of plate-type fuel assemblies

Mao

Zhang

Pan

et al. 2022

Composite Structures

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Neutronic performance characteristics of different LEU fuels in a proposed NIST research reactor

Cited by 6 publications

References 9 publications

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

Progress towards Operation of a Deuterium Cold Neutron Source at the NCNR

An innovative multi-layer shell model for in-pile thermo-mechanical behavior analysis of plate-type fuel assemblies

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