IAEA CRP I31033 : Status Report SNL
Abstract not provided.
Publications
SCALE/MELCOR Non-LWR Accident Progression and Source Term Analysis
Abstract not provided.
Integral System-Level Source Terms and their Consequence
Abstract not provided.
IAEA CRP I31033 :SNL Year 1 Progress
Abstract not provided.
MELCOR and Integral Reactor Safety Assessment
Abstract not provided.
Mechanistic Source Term Considerations for Advanced Non-LWRs
This report is a functional review of the radionuclide containment strategies of fluoride-salt-cooled high temperature reactor (FHR), molten salt reactor (IVISR) and high temperature gas reactor (HTGR) systems. This analysis serves as a starting point for further, more in-depth analyses geared towards identifying phenomenological gaps that still exist, preventing the creation of a mechanistic source term for these reactor types. As background information to this review, an overview of how a mechanistic source term is created and used for consequence assessment necessary for licensing is provided. How mechanistic source term is used within the LMP is also provided. Third, the characteristics of non-LWR mechanistic source terms are examined This report does not assess the viability of any software system for use with advanced reactor designs, but instead covers system function requirements. Future work within the Nuclear Energy Advanced Modeling and Simulations (NEAMS) program will address such gaps.
Contribution to OECD/NEA Fukushima-Related Projects: Uncertainty Analyses of 1F1 & 1F2
Proposed Modelling Evolution Based on Involvement in OECD/NEA Projects Related to the FDNPS Accident Rev. 1
Abstract not provided.
Proposed Modeling Scope for Task 1 of ARC-F
Abstract not provided.
Sandia Fire Research Program
Abstract not provided.
State-of-the-Art Severe Accident Analysis ? Evolution of Reactor Safety after Fukushima Daiichi
Abstract not provided.
Results 26–36 of 36