Kenneth R. Wagner
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View article: MELCOR Modeling Needs for Non LWR Accident Progression and Source Term Readiness
MELCOR Modeling Needs for Non LWR Accident Progression and Source Term Readiness Open
View article: Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration
Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration Open
To assess the modeling and simulation capabilities for radionuclide characterization, criticality, and shielding in the nuclear fuel cycle of non-light–water reactor (LWR) technologies, the US Nuclear Regulatory Commission (NRC) initiated …
View article: NORMALIZED DOSE ASSESSMENT AND RADIONUCLIDE SENSITIVITY ANALYSIS FOR A HIGH TEMPERATURE GAS REACTOR MECHANISTIC SOURCE TERM.
NORMALIZED DOSE ASSESSMENT AND RADIONUCLIDE SENSITIVITY ANALYSIS FOR A HIGH TEMPERATURE GAS REACTOR MECHANISTIC SOURCE TERM. Open
View article: MELCOR Accident Progression and Source Term Analysis for a Fluoride High-Temperature Reactor.
MELCOR Accident Progression and Source Term Analysis for a Fluoride High-Temperature Reactor. Open
View article: IAEA CRP I31033 : Status Report SNL .
IAEA CRP I31033 : Status Report SNL . Open
View article: Ion-pairing equilibria and kinetics of dimethyl phosphate: A model for counter-ion binding to the phosphate backbone of nucleic acids
Ion-pairing equilibria and kinetics of dimethyl phosphate: A model for counter-ion binding to the phosphate backbone of nucleic acids Open
Dimethyl phosphate (DMP–) is the simplest model ion to assess ion-pairing phenomena between metal ions and the phosphate backbone of nucleic acids. Yet, the equilibria and dynamics of ion binding to DMP– have not been fully uncovered. Here…
View article: Non-LWR MELCOR Capability Development for MSRs and SFRs.
Non-LWR MELCOR Capability Development for MSRs and SFRs. Open
View article: Non-LWR Fuel Cycle Analysis with SCALE/MELCOR.
Non-LWR Fuel Cycle Analysis with SCALE/MELCOR. Open
View article: MELCOR Integrated Severe Accident Code Demonstration and Sensitivity Study of HTGR Accident Progression.
MELCOR Integrated Severe Accident Code Demonstration and Sensitivity Study of HTGR Accident Progression. Open
View article: MELCOR Integrated Severe Accident Code Demonstration and Sensitivity Study of Heat Pipe Reactor Accident Progression .
MELCOR Integrated Severe Accident Code Demonstration and Sensitivity Study of Heat Pipe Reactor Accident Progression . Open
View article: MELCOR Integrated Severe Accident Code Demonstration and Sensitivity Study of FHR Accident Progression.
MELCOR Integrated Severe Accident Code Demonstration and Sensitivity Study of FHR Accident Progression. Open
View article: MELCOR Accident Progression and Source Term Demonstration Calculations for a FHR
MELCOR Accident Progression and Source Term Demonstration Calculations for a FHR Open
MELCOR is an integrated thermal hydraulics, accident progression, and source term code for reactor safety analysis that has been developed at Sandia National Laboratories for the United States Nuclear Regulatory Commission (NRC) since the …
View article: MELCOR Accident Progression and Source Term Demonstration Calculations for a Heat Pipe Reactor
MELCOR Accident Progression and Source Term Demonstration Calculations for a Heat Pipe Reactor Open
MELCOR is an integrated thermal hydraulics, accident progression, and source term code for reactor safety analysis that has been developed at Sandia National Laboratories for the United States Nuclear Regulatory Commission (NRC) since the …
View article: Bounding Radionuclide Release Estimates for a Hypothetical Power Reactor Accident
Bounding Radionuclide Release Estimates for a Hypothetical Power Reactor Accident Open
The object of this study is to provide an estimate of bounding radionuclide releases from a nuclear power plant accident. The time frame of interest is the release phase from the initiating event through 30 days. The maximum credible initi…
View article: MELCOR Accident Progression and Source Term Demonstration Calculations for a HTGR
MELCOR Accident Progression and Source Term Demonstration Calculations for a HTGR Open
MELCOR is an integrated thermal hydraulics, accident progression, and source term code for reactor safety analysis that has been developed at Sandia National Laboratories for the United States Nuclear Regulatory Commission (NRC) since the …
View article: MODELING HEAT PIPE REACTORS IN THE MELCOR SEVERE ACCIDENT CODE.
MODELING HEAT PIPE REACTORS IN THE MELCOR SEVERE ACCIDENT CODE. Open
View article: MELCOR Code Change History: Revision 11932 to 14959 Patch Release Addendum
MELCOR Code Change History: Revision 11932 to 14959 Patch Release Addendum Open
This document summarily provides brief descriptions of the MELCOR code enhancement made between code revision number 11932 and 14959. Revision 11932 represents the last official code release; therefore, the modeling features described with…
View article: MELCOR Modeling of Accident Scenarios at a Facility for Aqueous Reprocessing of Spent Nuclear Fuel
MELCOR Modeling of Accident Scenarios at a Facility for Aqueous Reprocessing of Spent Nuclear Fuel Open
The work presented in this report applies the MELCOR code to evaluate potential accidents in non-reactor nuclear facilities, focusing on Design Basis Accidents. Ten accident scenarios were modeled using NRC's best-estimate severe accident …