Zobrazeno 1 - 10
of 16
pro vyhledávání: '"Joshua L. Peterson"'
Publikováno v:
Nuclear Engineering and Technology. 54:790-802
Large-scale reactor simulation often requires the use of Monte Carlo calculation techniques to estimate important reactor parameters. One drawback of these Monte Carlo calculation techniques is they inevitably result in some uncertainty in calculated
Autor:
Joshua L. Peterson-Droogh, Richard H. Howard, Jorge Navarro, Jagoda M. Urban-Klaehn, M. A. Reichenberger, Jason V. Brookman
Publikováno v:
Nuclear Technology. 208:303-309
Production of high specific activity (HSA) 60Co has recently resumed at the Advanced Test Reactor (ATR) at the Idaho National Laboratory. The technical steps of performing in-canal assay of HSA 60C...
Publikováno v:
Annals of Nuclear Energy. 128:288-291
Many nuclear fuel cycle simulators can analyze transitions from once-through to advanced nuclear fuel cycles. Verification studies compare various fuel cycle analysis tools to test agreement and identify sources of difference. A recent verification s
Autor:
M. A. Reichenberger, Jagoda M. Urban-Klaehn, C. Tyler, Jason V. Brookman, M. Lillo, Joshua L. Peterson-Droogh, Richard H. Howard, Brian J. Gross, A. Zillmer, Jorge Navarro
Publikováno v:
Applied Radiation and Isotopes. 169:109494
Domestic production of high specific activity 60Co was halted after a target rupture in 2012 at the Advanced Test Reactor (ATR). The Isotope Program (IP) within the US Department of Energy (DOE) Office of Science tasked a multilaboratory team of rese
Autor:
Eva E. Davidson, Benjamin R. Betzler, Bo Feng, T. Fei, Joshua L. Peterson-Droogh, Taeil Kim, Andrew Worrall, Temitope A. Taiwo, Francesco Ganda, R. Hays, E. Hoffman, H. Hiruta, Brent Dixon, John H. L. Hansen
Publikováno v:
Annals of Nuclear Energy. 147:107652
This paper presents the major takeaways from studies conducted over several years that were focused on transitioning the U.S. nuclear infrastructure from the current once-through fuel cycle to one in which fuel is continuously recycled in fast reacto
Autor:
John M Scaglione, Kaushik Banerjee, Georgeta Radulescu, Justin B. Clarity, John C. Wagner, Joshua L. Peterson, Robert A Lefebvre, Kevin R Robb
Publikováno v:
Nuclear Technology. 195:124-142
We completed a novel assessment to determine the unquantified and uncredited safety margins (i.e., the difference between the licensing basis and as-loaded calculations) available in as-loaded spent nuclear fuel (SNF) casks. This assessment was perfo
Publikováno v:
ResearcherID
Shutdown dose rate (SDDR) analysis requires (a) a neutron transport calculation to estimate neutron flux fields, (b) an activation calculation to compute radionuclide inventories and associated pho...
Publikováno v:
Fusion Science and Technology. 68:700-704
The Multi-Step Consistent Adjoint Driven Importance Sampling (MS-CADIS) hybrid Monte Carlo (MC)/deterministic radiation transport method was proposed to speed up the shutdown dose rate (SDDR) neutron MC calculation using an importance function that r
Publikováno v:
Fusion Engineering and Design. 89:1933-1938
The rigorous 2-step (R2S) computational system uses three-dimensional Monte Carlo transport simulations to calculate the shutdown dose rate (SDDR) in fusion reactors. Accurate full-scale R2S calculations are impractical in fusion reactors because the
Autor:
Erich A. Schneider, Joshua L. Peterson
Publikováno v:
Nuclear Science and Engineering. 173:28-42
A modified form of first-order perturbation theory, called phase-space interpolated perturbation theory (PSIPT), was developed to more accurately model families of perturbations where changes are intermediate to defined reference and bounding configu