TMAP7
TMAP7 was developed by the Fusion Safety Program at INL primarily as a safety analysis code, to analyze tritium retention and loss in fusion reactor structures and systems during normal operation and accident conditions. TMAP7 solves one-dimensional thermal- and mass-diffusive transport and trapping equations for transport through structures, across the interface between enclosures and structures, and zero dimensional fluid transport between enclosures.
- Short Name / Acronym:
- TMAP7
- Project Type:
- Closed Source
- Site Accession Number:
- 8311
- Software Type:
- Scientific
- Programming Language(s):
- Fortran 77
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)Primary Award/Contract Number:AC07-05ID14517
- DOE Contract Number:
- AC07-05ID14517
- Code ID:
- 120625
- OSTI ID:
- code-120625
- Country of Origin:
- United States
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