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Modeling a Hypothetical Fusion Blanket Design Using MELCOR-TMAP

Conference ·
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.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
74
DOE Contract Number:
AC07-05ID14517
OSTI ID:
2479713
Report Number(s):
INL/CON-24-81146-Rev000
Country of Publication:
United States
Language:
English

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