Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes

Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes

This paper describes the creation and description of a nuclear fuel isotopics dataset for irradiated fuel salt from a Molten Salt Reactor (MSR). The dataset has been created using simulations carried out using the Monte-Carlo particle transport code, Serpent 2.1.32 (released February 24, 2021) and t...

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Bibliographic Details
Main Authors: Vaibhav Mishra, Zsolt Elter, Erik Branger, Sophie Grape, Sorouche Mirmiran
Format: Article
Language:English
Published: Elsevier 2024-02-01
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/S235234092300879X

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http://www.sciencedirect.com/science/article/pii/S235234092300879X

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