Search Results - "Woolstenhulme, Nicolas"
-
1
Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices
Published in Progress in nuclear energy (New series) (01-11-2023)“…Triply periodic minimal surface (TPMS) lattices are receiving substantial attention in numerous engineering fields due to their impressive topology-driven…”
Get full text
Journal Article -
2
BISON automation to predict transient power history based off prescribed cladding temperature
Published in Nuclear engineering and design (01-04-2022)“…•TREAT transient power history predictions on prescribed temperatures.•BISON fuel performance simulations for U-10Zr and UO2 fuel.•Different transient profiles…”
Get full text
Journal Article -
3
Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT
Published in Progress in nuclear energy (New series) (01-05-2020)“…Preventing the occurrence of a departure from nucleate boiling (DNB) event is an important aspect of nuclear safety in pressurized water reactors (PWRs). This…”
Get full text
Journal Article -
4
Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility
Published in Nuclear engineering and design (01-10-2022)“…•Design of a novel, non-fueled nuclear heated rod for in-pile tests in the Transient Reactor Test Facility.•Separate-effect tests to study critical heat flux…”
Get full text
Journal Article -
5
Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT
Published in Annals of nuclear energy (01-02-2019)“…•MARCH irradiation vehicle system to be used for inaugural TREAT experiments.•Transient testing needs and TREAT capabilities discussed.•Baseline…”
Get full text
Journal Article -
6
Mechanical Behavior Assessment of Ti-6Al-4V ELI Alloy Produced by Laser Powder Bed Fusion
Published in Metals (Basel ) (01-11-2021)“…The present work correlates the quasi-static, tensile mechanical properties of additively manufactured Ti-6Al-4V extra low interstitial (ELI, Grade 23) alloy…”
Get full text
Journal Article -
7
Microstructural Development in Inconel 718 Nickel-Based Superalloy Additively Manufactured by Laser Powder Bed Fusion
Published in Metallography, microstructure, and analysis (01-02-2022)“…Excellent weldability and high temperature stability make Inconel 718 (IN718) one of the most popular alloys to be produced by additive manufacturing. In this…”
Get full text
Journal Article -
8
The use of U3Si2/Al dispersion fuel for high power research reactors
Published in Journal of nuclear materials (01-01-2020)“…In order to investigate the irradiation performance of U3Si2/Al dispersion fuel at relatively aggressive reactor conditions, compared to how this fuel is…”
Get full text
Journal Article -
9
Narrowing transient testing pulse widths to enhance LWR RIA experiment design in the TREAT facility
Published in Annals of nuclear energy (01-02-2019)“…•LDRD established to enable TREAT support of LWR HZP-RIA testing.•Kinetics studies indicated transient clipping techniques necessary to narrow pulse…”
Get full text
Journal Article -
10
Correction to: A source biasing and variance reduction technique for Monte Carlo radiation transport modeling of emission tomography problems
Published in Journal of radioanalytical and nuclear chemistry (01-04-2020)“…In the original article, Equation 4 was incorrectly published. The correct equation is provided in this correction…”
Get full text
Journal Article -
11
Additive manufacturing and mechanical properties of the dense and crack free Zr-modified aluminum alloy 6061 fabricated by the laser-powder bed fusion
Published in Additive manufacturing (01-05-2021)“…For additive manufacturing such as laser powder bed fusion (LPBF), commercial aluminum alloy (AA) 6061 is typically considered unsuitable due to formation of…”
Get full text
Journal Article -
12
Feasibility studies for simultaneous irradiation of NBSR & MITR fuel elements in the BR2 reactor
Published in Annals of nuclear energy (01-05-2019)“…•BR2 can perform simultaneous irradiation of DDE-NBSR & MITR as in original reactors.•MCNP BR2 burn-up model with DDE irradiation rigs is developed by BR2…”
Get full text
Journal Article -
13
Potential annealing treatments for tailoring the starting microstructure of low-enriched U–Mo dispersion fuels to optimize performance during irradiation
Published in Journal of nuclear materials (01-12-2011)“…► We applied different heat treatments to low-enriched U–Mo alloy dispersion fuels. ► Specific treatments produce uniform fuel/matrix interaction layers around…”
Get full text
Journal Article -
14
Microstructure characterization of as-fabricated and 475 Degrees C annealed U–7 wt.% Mo dispersion fuel in Al–Si alloy matrix
Published in Journal of alloys and compounds (29-09-2011)“…High-density uranium (U) alloys with an increased concentration of U are being examined for the development of research and test reactors with low enriched…”
Get full text
Journal Article -
15
A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions
Published in Journal of nuclear materials (01-04-2021)“…High burnup fuel in excess of ~6268 GWd/MTU has been observed to severely fragment when subjected to temperature transient conditions as in a loss-of-coolant…”
Get full text
Journal Article -
16
Nuclear fuels for transient test reactors
Published in Annals of nuclear energy (01-09-2024)“…Transient test reactors with the ability to test fissile specimens under extreme conditions have been crucial tools in the development of nuclear technologies…”
Get full text
Journal Article -
17
Nuclear fuels for transient test reactors
Published in Annals of nuclear energy (19-04-2024)“…Transient test reactors with the ability to test fissile specimens under extreme conditions have been crucial tools in the development of nuclear technologies…”
Get full text
Journal Article -
18
Thermal and hydraulic performance of volumetrically heated triply periodic minimal surface heaters
Published in Applied thermal engineering (01-07-2024)“…•The 50 mm gyroid TPMS showed friction factors 1.5x that of the 50 mm diamond TPMS.•The 50 mm gyroid TPMS showed friction factors up to 90x that of the rod…”
Get full text
Journal Article -
19
Post-irradiation examination of UN-Mo-W fuels for space nuclear propulsion
Published in Journal of nuclear materials (01-01-2025)“…The National Aeronautics and Space Administration's return to space nuclear propulsion stems from the need for a more efficient method of space travel. Nuclear…”
Get full text
Journal Article -
20
Accelerated radiation transport modeling techniques for pencil beam computed tomography using gamma rays
Published in Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment (11-09-2022)“…Monte Carlo radiation transport modeling studies were performed for a compact, and high-resolution gamma-ray computed tomography system designed for imaging…”
Get full text
Journal Article