Výsledky vyhledávání - "Blair P. Bromley"

Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors

Autor: Daniel T. Wojtaszek, Blair P. Bromley

Publikováno v: Journal of Nuclear Engineering and Radiation Science. 9

Lattice physics calculations have been carried out to evaluate the performance and safety characteristics of a modified high temperature gas-cooled reactor (HTGR) prismatic fuel block concept, based on the MHTGR-350 benchmark problem. Key changes wer

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ee9128f4cce7044a66c9b84548bdf256
https://doi.org/10.1115/1.4055009

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Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels

Autor: Chenguang Li, Krishna Podila, Blair P. Bromley, Yanfei Rao

Publikováno v: Journal of Nuclear Engineering and Radiation Science. 9

Pressure loss coefficients are generally required by subchannel and system thermalhydraulics codes. These coefficients are not readily available for small modular reactors (SMRs) featuring nonconventional designs and novel coolants. In this study, th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::1e2fb0009b0dfcf3799f7bba14e7ee00
https://doi.org/10.1115/1.4054943

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Initial Exploratory Reactor Physics Assessment of Nonconventional Fuel Concepts for Very Compact Small Modular Reactors Using Hydroxides as Coolants and/or Moderators

Autor: Blair P. Bromley

Publikováno v: Nuclear Technology. 208:160-191

In this study, lattice physics calculations were carried out to evaluate the reactor physics characteristics of different advanced fuel lattices cooled with 7LiOH/NaOH or FLiBe and moderated extern...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::fb229f9c42057d804111e0a3e4f92db5
https://doi.org/10.1080/00295450.2021.1874778

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Reactor Physics Assessment of Potential Feasibility of Using Advanced, Nonconventional Fuels in a Pressure Tube Heavy Water Reactor to Destroy Americium and Curium

Autor: Ashlea V. Colton, Blair P. Bromley

Publikováno v: Nuclear Technology. 207:1193-1215

Lattice physics and core physics studies have been carried out to investigate the reactor physics feasibility of destroying americium (Am) and curium (Cm) using special target fuel bundles in blank...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::421ba0310424f4ec1f60455b3dd54910
https://doi.org/10.1080/00295450.2020.1853466

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Sensitivity Studies to Assess the Impact of Geometry and Operating/Boundary Condition Perturbations on Thermal-Hydraulic Behavior of Advanced Fuel Channels in Pressure Tube Heavy Water Reactors with Uranium and Thorium-Based Fuels

Autor: Ashlea V. Colton, A. Nava Dominguez, Z. Cheng, Blair P. Bromley

Publikováno v: Nuclear Technology. 207:1511-1537

This paper reports the results of subchannel thermal-hydraulic studies (using the ASSERT-PV code) of the effects of variations and uncertainties in operating/boundary conditions and geometry on the...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4d55b969444e633b738951d516a4a84d
https://doi.org/10.1080/00295450.2020.1827658

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Reactor Physics Analysis Assessment of Feasibility of Using Advanced, Nonconventional Fuels in a Pressure Tube Heavy Water Reactor to Destroy Long-Lived Fission Products

Autor: Ashlea V. Colton, Blair P. Bromley

Publikováno v: Nuclear Technology. 207:1182-1192

Lattice physics and core physics studies have been carried out to investigate the feasibility of destroying long-lived fission products (LLFPs) using special target fuel bundles in blanket fuel cha...

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https://doi.org/10.1080/00295450.2020.1812318

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Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels

Autor: Ayman M. Bayomy, Blair P. Bromley, Armando Nava Dominguez, Samuel Kelly

Publikováno v: Journal of Nuclear Engineering and Radiation Science. 8

Thermalhydraulic analyses using subchannel codes (e.g., ASSERT-PV) are performed as a support tool to evaluate safety margins and the key parameters. Advanced fuels have recently attracted the international community's interest to improve safety marg

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::dbaec0a7be4486d19a02dbf751b069c2
https://doi.org/10.1115/1.4053829

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Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor

Autor: T. Sinh Nguyen, Xiaolin Wang, Blair P. Bromley

Publikováno v: Journal of Nuclear Engineering and Radiation Science. 8

The development of advanced fuels and fuel cycles for conventional Generation III+ reactors, advanced reactors (such as Generation IV), and small modular reactors will help ensure the long-term sustainability and safety of the use of nuclear energy.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f0c271f16b18715fea6978919fb6b574
https://doi.org/10.1115/1.4053691

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Steady-State Subchannel Thermal-Hydraulic Assessment of Advanced Uranium-Based and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors

Autor: S. Liu, A. Nava-Dominguez, Ashlea V. Colton, Blair P. Bromley, T. Beuthe

Publikováno v: Nuclear Technology. 207:1216-1236

The use of advanced uranium-based and thorium-based fuel bundles in a 700-MW(electric)–class pressure tube heavy water reactor (PT-HWR) has the potential for improved performance characteristics wi...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4aa384e3c9cd39479c97250ba4619cd4
https://doi.org/10.1080/00295450.2020.1813463

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DIFFERENCES IN EXIT BURNUP, DEPLETION, AND FUEL REACTIVITY CALCULATIONS ARISING FROM THE CHOICE OF MODELLING CODE FOR BUNDLES WITH THORIUM AND URANIUM

Autor: Geoffrey W.R. Edwards, Ashlea V. Colton, Blair P. Bromley

Publikováno v: CNL Nuclear Review. 9:57-71

A computational benchmark, using the deterministic codes WIMS-AECL and WOBI, and the stochastic code SERPENT, is made for burnup calculations of advanced thorium fuels in heavy water moderated reactors. Exit burnups and the concentration of the longe

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::e7b93d3d82310d5e27d63ec71b9aa80a
https://doi.org/10.12943/cnr.2018.00011

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