David Louie
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View article: Validation study of sodium pool fire modeling efforts in MELCOR and SPHINCS codes
Validation study of sodium pool fire modeling efforts in MELCOR and SPHINCS codes Open
View article: Injectable sacrificial material systems and methods to contain molten corium in nuclear accidents
Injectable sacrificial material systems and methods to contain molten corium in nuclear accidents Open
Systems and methods for injecting a carbonate-based sacrificial material into a nuclear reactor containment for containment of molten corium in severe nuclear reactor accidents are disclosed. Molten corium can be quickly cooled and solidif…
View article: Enhancement of Sodium Pool Fire Modeling in MELCOR.
Enhancement of Sodium Pool Fire Modeling in MELCOR. Open
View article: Sodium Fire Collaborative Study Progress (CNWG Fiscal Year 2022)
Sodium Fire Collaborative Study Progress (CNWG Fiscal Year 2022) Open
This report discusses the progress on the collaboration between Sandia National Laboratories (Sandia) and Japan Atomic Energy Agency (JAEA) on the sodium fire research in fiscal year (FY) 2022 and is a continuation of the FY 2021 progress …
View article: Validation Study of Sodium Pool Fire Modeling Efforts in MELCOR and SPHINCS Codes.
Validation Study of Sodium Pool Fire Modeling Efforts in MELCOR and SPHINCS Codes. Open
View article: MELCOR Validation Study of the Sodium Pool Fire Model with Comparison to SPHINCS.
MELCOR Validation Study of the Sodium Pool Fire Model with Comparison to SPHINCS. Open
View article: Study of alkaline carbonate cooling to mitigate Ex-Vessel molten corium accidents
Study of alkaline carbonate cooling to mitigate Ex-Vessel molten corium accidents Open
View article: MELCOR INTEGRATED SEVERE ACCIDENT CODE FOR NON-LWR APPLICATIONS.
MELCOR INTEGRATED SEVERE ACCIDENT CODE FOR NON-LWR APPLICATIONS. Open
View article: MELCOR CODE VALIDATION STUDIES ON FIRE ACCIDENTS IN NON-REACTOR FACILITIES.
MELCOR CODE VALIDATION STUDIES ON FIRE ACCIDENTS IN NON-REACTOR FACILITIES. Open
View article: MELCOR Overview Introduction .
MELCOR Overview Introduction . Open
View article: MELCOR Overview Summary.
MELCOR Overview Summary. Open
View article: MELCOR Validation Study on Sodium Pool Fire Model with Comparison to SPHINCS
MELCOR Validation Study on Sodium Pool Fire Model with Comparison to SPHINCS Open
View article: CNWG Collaborative Research -SNL and JAEA - FY20.
CNWG Collaborative Research -SNL and JAEA - FY20. Open
View article: Sodium Fire Collaborative Study Progress CNWG Fiscal Year 2021
Sodium Fire Collaborative Study Progress CNWG Fiscal Year 2021 Open
This report discusses the progress on the collaboration between Sandia National Laboratories (Sandia) and Japan Atomic Energy Agency (JAEA) on the sodium fire research in fiscal year (FY) 2021 and is a continuation of the FY2020 progress r…
View article: Using Alkaline Carbonate to Mitigate Molten Corium in Severe Nuclear Reactor Accidents.
Using Alkaline Carbonate to Mitigate Molten Corium in Severe Nuclear Reactor Accidents. Open
View article: Review of Spent Fuel Reprocessing and Associated Accident Phenomena.
Review of Spent Fuel Reprocessing and Associated Accident Phenomena. Open
View article: Review of Spent Fuel Reprocessing and Associated Accident Phenomena.
Review of Spent Fuel Reprocessing and Associated Accident Phenomena. Open
View article: Study of Recent Sodium Pool Fire Model Improvements for MELCOR Code
Study of Recent Sodium Pool Fire Model Improvements for MELCOR Code Open
The Sodium Chemistry (NAC) package in MELCOR has been developed to enhance application to sodium cooled fast reactor. The models in the NAC package have been assessed through benchmark analyses. The F7-1 sodium pool fire experimental analy…
View article: Study of Sodium Pool Fire Model Improvement in MELCOR for SFR.
Study of Sodium Pool Fire Model Improvement in MELCOR for SFR. Open
View article: Task 2-aDevelopment and V&V of multi-physics mechanistic numerical simulation methods.
Task 2-aDevelopment and V&V of multi-physics mechanistic numerical simulation methods. Open
View article: Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults
Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults Open
Throughout U.S. Department of Energy (DOE) complexes, safety engineers employ the five-factor formula to calculate the source term (ST) that includes parameters of airborne release fraction (ARF), respirable fraction (RF) and damage ratio …
View article: MELCOR Validation Study on Multi-Room Fire.
MELCOR Validation Study on Multi-Room Fire. Open
View article: MELCOR Code Validation for LPF Applications.
MELCOR Code Validation for LPF Applications. Open
View article: Sodium Fire Collaborative Study Progress -- CNWG Fiscal Year 2020
Sodium Fire Collaborative Study Progress -- CNWG Fiscal Year 2020 Open
This report discusses the progress on the collaboration between Sandia National Laboratories (Sandia) and Japan Atomic Energy Agency (JAEA) on the sodium fire research in fiscal year 2020. First, the current sodium pool fire model in MELCO…
View article: Development of the sodium fire module in integrated severe accident analysis code, SPECTRA
Development of the sodium fire module in integrated severe accident analysis code, SPECTRA Open
The SPECTRA code has been developed as an integrated simulation system for severe accident evaluation in a sodium cooled fast reactor. In this study, the sodium pool fire model of SPECTRA is accessed through the benchmark analysis of the F…
View article: MELCOR Code Change History (Revision 14959 to 18019)
MELCOR Code Change History (Revision 14959 to 18019) Open
This document summarily provides brief descriptions of the MELCOR code enhancement made between code revision number 14959and 18019. Revision 14959 represents the previous official code release; therefore, the modeling features described w…
View article: MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant
MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant Open
The work presented in this paper applies the MELCOR code developed at Sandia National Laboratories to evaluate the source terms from potential accidents in non-reactor nuclear facilities. The present approach provides an integrated source …
View article: Sodium Fire Analysis Using a Sodium Chemistry Package in MELCOR
Sodium Fire Analysis Using a Sodium Chemistry Package in MELCOR Open
The Sodium Chemistry (NAC) package in MELCOR has been developed to enhance application to sodium cooled fast reactors. The models in the NAC package have been assessed through benchmark analyses. The F7-1 pool fire experimental analysis is…
View article: Nuclear Facility Safety at the United States Department of Energy
Nuclear Facility Safety at the United States Department of Energy Open
Nuclear facility safety is crucial to preventing and/or reducing high consequence-low probability accidents and, thus reducing the potential risks posed by United States Department of Energy (DOE) and National Nuclear Security Administrati…
View article: Injectable Sacrifical Material Safety System to Mitigae Molten Corium in Containment.
Injectable Sacrifical Material Safety System to Mitigae Molten Corium in Containment. Open