Modeling a Hypothetical Fusion Blanket Design Using MELCOR-TMAP

Riet, Adriaan Anthony; Eklund, Matthew D

doi:10.13182/pbnc24-45018

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Modeling a Hypothetical Fusion Blanket Design Using MELCOR-TMAP

Riet, Adriaan Anthony·Eklund, Matthew D

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Abstract

MELCOR (not an acronym) is a nuclear safety code developed by Sandia National Laboratories for the Nuclear Regulatory Commission. Idaho National Laboratory collaborates with Sandia to maintain and develop a version of MELCOR specifically for fusion device applications. Most recently, the tritium migration analysis program (TMAP) has been incorporated into MELCOR for fusion, in a version called MELCOR-TMAP. We show the results applying MELCOR-TMAP to model steady-state inventory and tritium retention in a liquid immersion blanket design for a hypothetical fusion device under steady-state operation.

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70 PLASMA PHYSICS AND FUSION TECHNOLOGY FLiBe fusion MELCOR Tritium

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BibTeX RIS

Riet, Adriaan Anthony, Eklund, Matthew D. 2024-10-09. Modeling a Hypothetical Fusion Blanket Design Using MELCOR-TMAP. https://doi.org/10.13182/pbnc24-45018

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