MELCOR Code Development Status
Abstract not provided.
Publications
MELCOR/Contain-LMR Integration
Abstract not provided.
Core Molten Pool Modeling
Abstract not provided.
Fukushima Accident Spent Fuel Pool Model in MELCOR V2.1
Abstract not provided.
MELCOR Overview
Abstract not provided.
MELCOR Code V&V and SQA
Abstract not provided.
MELCOR Source Term Calculation
Abstract not provided.
Modeling of Off-Site Consequences
Abstract not provided.
MELCOR uncertainty analysis and SOARCA
Abstract not provided.
Nuclear Severe Accident Modeling and Analysis
Abstract not provided.
MELCOR 2.1 Leak Path Factor Assessments and Guidance
Abstract not provided.
MELCOR 2.1 Leak Path Factor Assessment and Guidance
Abstract not provided.
MELCOR Code Development Status
Abstract not provided.
MELCOR 2.1 Software Quality Assurance Program
Abstract not provided.
Severe Accidents Modeling and Analysis
Abstract not provided.
MELCOR Code Development Status Code Assessment and QA
Abstract not provided.
MELCOR Code QA Practices
Abstract not provided.
Foundational development of an advanced nuclear reactor integrated safety code
This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.
MELCOR/MACCS for Severe Accident Analysis
Abstract not provided.
New model improvements in MELCOR 1.8.6 to simulate the formation and behavior of molten pools in severe accidents
Abstract not provided.
Sandia heat flux gauge thermal response and uncertainty models
ASTM Special Technical Publication
A study was performed on the Sandia Heat Flux Gauge (HFG) developed as a rugged, cost effective technique for performing steady state heat flux measurements in the pool fire environment. The technique involved reducing the time-temperature history of a thin metal plate to an incident heat flux via a dynamic thermal model, even though the gauge was intended for use at steady state. A validation experiment was presented where the gauge was exposed to a step input of radiant heat flux.
Results 101–121 of 121