KRUSTY neutronics

Has anyone done the neutronics analysis of KRUSTY ? If possible can I please get the ipython file?

I do not have a model, but you might reach out to the authors of this recent paper:

title = {Multi-physics coupling analysis of test heat pipe reactor KRUSTY based on MOOSE framework},
journal = {Nuclear Engineering and Design},
volume = {414},
pages = {112597},
year = {2023},
issn = {0029-5493},
doi = {Redirecting},
url = {},
author = {Hongli Chen and Weixiang Wang and Aoguang Wu and Kefan Zhang and Rui Pan and Wenshun Duan and Guangliang Yang and Chong Qin and Xiao Luo},
abstract = {The heat pipe reactor utilizes heat pipes for passive heat transfer, eliminating the need for any moving parts. This feature significantly enhances its safety characteristics. Given the intricate nature of the heat pipe reactor system, a comprehensive multi-physics coupling simulation is necessary to study its safety features. In this study, a high-fidelity multi-physics coupling analysis incorporating a neutronic-thermal–mechanical-heat pipe coupling model is conducted. The work is based on the multi-physics coupling framework MOOSE, which integrates the Monte Carlo code OpenMC for neutronic analysis and built-in modules for 3-dimensional thermal–mechanical analysis. Furthermore, a heat pipe simulation method called the Thermal Resistance Grid Method is implemented within the MOOSE framework and employed in the multi-physics coupling analysis. To facilitate transient analysis, the Point Kinetics method is also integrated into the MOOSE framework to account for the time-varying power factor during reactor transients. The various modules and physical fields are coupled together using either loose or tight coupling strategies. These coupling strategies are applied to assess a test heat pipe reactor known as KRUSTY. Steady-state simulations are conducted for both normal operation and single heat pipe failure conditions, enabling the calculation of fission power distribution, temperature distribution, stress and strain profiles, as well as power and temperature redistribution following a heat pipe failure. Moreover, a load-following transient of KRUSTY is simulated, demonstrating its capability for load following without reactivity control. The aforementioned calculations validate the feasibility of the coupling framework utilized in this study and highlight its ability to accurately capture local phenomena within the reactor core.}