Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes

Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes

This paper describes the methodology used to create a fuel data library comprising safeguards-relevant quantities that may be useful for verification of spent nuclear fuel (SNF) produced by simulating a concept Molten Salt Reactor (MSR). The Monte-Carlo particle transport code, Serpent2 and the calc...

Full description

Bibliographic Details
Main Authors: Vaibhav Mishra, Zsolt Elter, Erik Branger, Sophie Grape, Sorouche Mirmiran
Format: Article
Language:English
Published: Elsevier 2024-06-01
Series:Data in Brief
Subjects:
Nuclear safeguards
Safeguards verification
Molten salt reactors
Spent fuel
Burnup
Serpent
Online Access:http://www.sciencedirect.com/science/article/pii/S235234092400283X

Internet

http://www.sciencedirect.com/science/article/pii/S235234092400283X

Similar Items