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Articles 1 - 7 of 7
Full-Text Articles in Physics
Unlv Magazine, Holly Ivy De Vore, Tony Allen, Barbara Cloud, Erin O'Donnell, Matthew K. Jacobsen, Gian Galassi, Michelle Mouton, Afsha Bawany, Shane Bevell
Unlv Magazine, Holly Ivy De Vore, Tony Allen, Barbara Cloud, Erin O'Donnell, Matthew K. Jacobsen, Gian Galassi, Michelle Mouton, Afsha Bawany, Shane Bevell
UNLV Magazine
No abstract provided.
Nuclear Energy, Steve Kraft
Nuclear Energy, Steve Kraft
Native American Forum on Nuclear Issues
Abstract:
-Why Nuclear Energy?
-The lesson of the last 20 years in U.S. electricity policy:
– Diversified fuel and technology portfolio is essential
– All fuels and technologies (nuclear, coal, natural gas, renewables, efficiency) have a legitimate role
-The challenge for the future:
– Preserving/restoring diversified portfolio
– Ensuring resource adequacy, particularly in competitive markets
-Expanded use of nuclear energy is part of the answer
– Integrated used fuel management supports nuclear competitiveness
Implementation Of Uncertainty Propagation In Triton/Keno, Charlotta Sanders, Denis Beller
Implementation Of Uncertainty Propagation In Triton/Keno, Charlotta Sanders, Denis Beller
Reactor Campaign (TRP)
Monte Carlo methods are beginning to be used for three dimensional fuel depletion analyses to compute various quantities of interest, including isotopic compositions of used nuclear fuel. The TRITON control module, available in the SCALE 5.1 code system, can perform three-dimensional (3-D) depletion calculations using either the KENO V.a or KENO-VI Monte Carlo transport codes, as well as the two-dimensional (2-D) NEWT discrete ordinates code. To overcome problems such as spatially nonuniform neutron flux and non-uniform statistical uncertainties in computed reaction rates and to improve the fidelity of calculations using Monte Carlo methods, uncertainty propagation is needed for depletion calculations.
Monaco/Mavric Evaluation For Facility Shielding And Dose Rate Analysis, Charlotta Sanders, Denis Beller
Monaco/Mavric Evaluation For Facility Shielding And Dose Rate Analysis, Charlotta Sanders, Denis Beller
Reactor Campaign (TRP)
The dimensions and the large amount of shielding required for Global Nuclear Energy Partnership (GNEP) facilities, advanced radiation shielding, and dose computation techniques are beyond today’s capabilities and will certainly be required. With the Generation IV Nuclear Energy System Initiative, it will become increasingly important to be able to accurately model advanced Boiling Water Reactor and Pressurized Water Reactor facilities, and to calculate dose rates at all locations within a containment (e.g., resulting from radiations from the reactor as well as the from the primary coolant loop) and adjoining structures (e.g., from the spent fuel pool).
The MAVRIC sequence is …
Dissolution, Reactor, And Environmental Behavior Of Zro2-Mgo Inert Fuel Matrix, Kenneth Czerwinski
Dissolution, Reactor, And Environmental Behavior Of Zro2-Mgo Inert Fuel Matrix, Kenneth Czerwinski
Fuels Campaign (TRP)
This project will examine inert fuels containing ZrO2 and MgO as the inert matrix. Ceramics with this inert matrix, Ce, U and eventually Pu will be synthesized and examined. While the Advanced Fuel Cycle Initiative focus is on inert fuels with Pu as the fissile component, this task will perform initial laboratory experiments with Ce and U. The initial work with Ce will be performed early in the project with results used as a basis for U studies. Reactor physics calculations will be used to examine suitable quantities of burnable poisons from the candidate elements Gd, Er, or Hf. …
Impact Of The Synthesis Process On Structure Properties For Afci Fuel Candidates, Kenneth Czerwinski
Impact Of The Synthesis Process On Structure Properties For Afci Fuel Candidates, Kenneth Czerwinski
Fuels Campaign (TRP)
The research objectives are:
• To explore a low-temperature fluoride route to synthesize actinide nitrides. • To characterize actinide nitrides structurally and thermally.
• To use high resolution TEM techniques to explore the microstructure of the radioactive samples.
Solution-Based Synthesis Of Nitride Fuels, Kenneth Czerwinski, Tyler A. Sullens
Solution-Based Synthesis Of Nitride Fuels, Kenneth Czerwinski, Tyler A. Sullens
Fuels Campaign (TRP)
One of the original synthetic routes devised for the synthesis of U (III)N involved the entire reaction taking place in liquid ammonia. Several experimental reactions were conducted in an attempt to synthesize the UI3(NH3)x and U(NH2)3(NH3)x precursors of U(III) N. Each attempt involved cleaning of the uranium metal to remove the oxide coating of the metal reagent with 3 washes of concentrated nitric acid, each followed by a rinse with liquid ammonia. Success of this cleaning procedure was varied, with a majority of cleaned metal oxidizing rapidly once …