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Cited article:

Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3

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Springer Proceedings in Physics, Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3 285 519 (2023)

Strategies for Fast Fission Matrix Estimation with Fuel Temperature and Control Rod Feedback

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Nuclear Science and Engineering 195 (10) 1017 (2021)

A twin assemblies benchmark for coupling behavior and kinetics parameters calculations

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Annals of Nuclear Energy 162 108421 (2021)

An iterative fission matrix scheme for calculating steady-state power and critical control rod position in a TRIGA reactor

Tyler J. Topham, Adam Rau and William J. Walters
Annals of Nuclear Energy 135 106984 (2020)

Transient fission matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations

Patrick Blaise, Axel Laureau, Paul Ros, Pierre Leconte and Kornilios Routsonis
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An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor

Vincent Lamirand, Axel Laureau, Dimitri Rochman, et al.
EPJ Web of Conferences 211 03003 (2019)

Spatial analysis of unprotected transients in heterogeneous sodium fast reactors

A. Laureau, Y. Lederer, A. Krakovich, L. Buiron and B. Fontaine
Annals of Nuclear Energy 115 554 (2018)