In order to join efforts to develop high-fidelity multi-physics tools for research reactor
analysis, the KIT is conducting studies to modify the coupled multi-physics codes developed …

In this paper, a three-dimensional full-scale neutronic/thermal–hydraulic coupled analysis
for the plate-type reactor is proposed based on the Multiphysics Object-Oriented Simulation …

Best-estimate codes, which couple neutronic and thermal-hydraulic solvers, are mainly used
for safety analyses of nuclear power plants. During the past decade, the application of these …

Abstract A 10 MW MTR benchmark reactor is an idealized pool-type material testing reactor
(MTR) used for comparing computational methods and codes in safety-related calculations …

Computational benchmarks are an important source for verifying the codes and modeling
methodology in nuclear reactor analysis. The current study aims at utilizing the newly …

Abstract The China Mianyang Research Reactor (CMRR), with a thermal power of 20 MW, is
an important high performance research reactor operated in China. In this paper, we …

The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics
(TH)] for safety analyses of research reactors (RRs) has gained considerable momentum …

In order to perform the resonance calculation efficiently and accurately, several pin-resolved
ultra-fine-group methods combining the ultra-fine-group method and Dancoff factor have …

MODULE OF COREBN/HIST. For 30 years operation, some of the modifications to the RSG
GAS core has been done, that are changes included the type of fuel from U3O8-Al to U3Si2 …

The deterministic method has served as a standardized approach to the neutronics
modeling of nuclear reactors. To get satisfactory computational efficiency and accuracy, the …