Blanket Modeling with Tritium Accountancy using MELCOR-Fusion
Fusion devices require a “blanket” of materials that generate tritium during production to provide the source of tritium for the fusion device. We use MELCOR for fusion to demonstrate a blanket model of an ARC-class reactor with a liquid immersion blanket. We discuss major sources of uncertainty and describe ongoing experimental efforts to reduce the […]
Modeling of the AGR 3/4 PIE Experiments
TRISO Fuel Accident Scenarios Transport of Fission Products (FP) through modern nuclear-grade graphites is not well established The AGR 3/4 experimental results need to be modeled to extract FP transport characteristics A finite element model using graphite diffusivities from IAEA TECDOC-978 is compared against measured results
Safety Analysis of Fusion Power Plants
Presentation on Safety Analysis of Fusion Power Plants using MELCOR-TMAP
MELCOR-TMAP: The integration of MELCOR for fusion and TMAP4 for fusion reactor systems safety analysis and tritium inventory tracking
The design of fusion reactors requires the prediction of radioactive tritium migration during normal operating conditions and accident scenarios. Safety standards such as those from the U.S. Department of Energy (DOE) require that fusion reactor designs limit the release of hazardous material to the environment. In addition to safety requirements, the rarity of tritium supplies […]
Improved Fuel Particle and Compact Matrix Fission Product Release Prediction with Improved Mass Transfer Model
This study was motivated by the need to incorporate more physics-based mass transfer models in BISON in order to improve fuel particle and compact matrix fission product release prediction. This document details the integration of new modeling capabilities in BISON, including (1) development of sorption mass transfer models; improvement of thermal contact model by adding […]
A MELCOR-TMAP Model of the Tritium Extraction eXperiment
The MELCOR-TMAP code has been used to predict tritium transport in the Tritium Extraction eXperiment. A brief overview is given
AGR-3/4 Post-Irradiation Examination
Presentation for the TCT Review meeting
Integration of MELCOR for Fusion and TMAP4 for fusion reactor systems analysis and tritium inventory tracking
This is the poster presentation to be presented at a virtual poster presentation session at the 32nd SOFT conference. Discussed are the background and timeline of the development of the MELCOR-TMAP code developed at Idaho National Laboratory.
Comparison of AGR-3/4 Fission Product Transport Model to Measurements and Extraction of Diffusivities via Analytical Fits
A one-dimensional finite-element model based on the MOOSE framework has been constructed, and overall transport estimates are predicted based on available diffusivities and sorption isotherms in the extant literature. The predicted transport profiles are compared to experimental results, where such results are available, including total inventory analysis of gamma emitters, liquid scintillation results for Sr-90 […]
SOFE2023 Presentation: “Tritium Safety and Sensitivity Analysis of Tritium Extraction eXperiment (TEX) PbLi Loop Using MELCOR-TMAP”
The efficient extraction of tritium from the breeder blanket (BB) in a fusion reactor is vital for maintaining the tritium economy for a sustainable and self-sufficient fusion power plant. The vacuum permeator (VP) design is one of several promising technology platforms for extracting tritium from the BB with the advantages of being capable of operating […]