MACSIS: A Metallic Fuel Performance Analysis Code for Simulating In-Reactor Behavior under Steady-State Conditions
Author:
Affiliation:
1. Korea Atomic Energy Research Institute Metallic Fuel Design Development Team, P.O. Box 105 Yusong, Taejon, Korea 305-600
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT98-A2887
Reference20 articles.
1. W. F. MURPHY et al. “Postirradiation Examination of U-Pu-Zr Fuel Elements Irradiated in EBR-II to 4.5 Atomic Percent Burnup,” ANL-7602, Argonne National Laboratory (1969).
2. Fuel constituent redistribution during the early stages of U-Pu-Zr irradiation
3. Demixing of U-Zr alloys under a thermal gradient
4. Temperature gradient driven constituent redistribution in UZr alloys
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