Abstract
The information presented in this paper is the preliminary step towards the development of a Mechanistic Source Term (MST) for Lead Cooled Fast Reactors (LFRs) which realistically models the release and transport of fission products from source to the environment. The paper also aims to summarize the current state of art on retention and transport of various fission products in Heavy Liquid Metal Coolants (HLMC), specifically focusing on the liquid Lead (Pb) and LeadBismuth Eutectic (LBE) coolants used for LFRs. Fission products are assessed based on their element group to determine where the data are lacking.
| Original language | English |
|---|---|
| Title of host publication | M&C 2017 - International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering |
| State | Published - Apr 20 2017 |
| Externally published | Yes |
| Event | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017 - , Korea, Republic of Duration: Apr 16 2017 → Apr 20 2017 |
Conference
| Conference | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017 |
|---|---|
| Country/Territory | Korea, Republic of |
| Period | 04/16/17 → 04/20/17 |
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