Zobrazeno 1 - 10
of 21
pro vyhledávání: '"Chris M. Allison"'
Autor:
Roxana-Mihaela Nistor-Vlad, Marina Perez-Ferragut, Chris M. Allison, Judith K. Hohorst, Daniel Dupleac
Publikováno v:
2021 10th International Conference on ENERGY and ENVIRONMENT (CIEM).
Publikováno v:
Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics.
Various small modular reactor (SMR) designs such as Micro Modular Reactor (MMR), Stable Salt Reactor - Wasteburner (SSR-W) and the Natrium reactor utilize an intermediate molten salt loop for heat transport and thermal energy storage (TES). This tech
Publikováno v:
Nuclear Engineering and Design. 337:341-350
Autor:
Judith Hohorst, Marina Perez-Ferragut, Chris M. Allison, Ludwik Pieńkowski, Katarzyna Skolik, Mateusz Malicki, A.K. Trivedi
Publikováno v:
Progress in Nuclear Energy. 134:103648
Small Modular Reactors (SMRs) are currently being developed and licensed in many countries. The innovations in the designs provide many significant features, such as decreased construction cost and time, enhanced safety, modularity, possibility of fa
Publikováno v:
Annals of Nuclear Energy. 151:107948
The scope of this work comprises the study of the mathematical nature of the RELAP5 two-fluid model (TFM) for two-component (water and non-condensable gas (helium)) and two phases (liquid and vapor) mixture flows, and to predict the accuracy of the m
Publikováno v:
Annals of Nuclear Energy. 149:107720
System thermal-hydraulic code RELAP5 is based on a two-fluid, non-equilibrium, and non-homogeneous hydrodynamic model for simulation of transient two-phase behavior. The code model includes six governing equations to incorporate the mass, energy, and
Publikováno v:
Nuclear Engineering and Design. 305:222-229
The AP1000 is a Westinghouse 2-loop pressurized water reactor (PWR) with all emergency core cooling systems based on natural circulation. Its core design is very similar to a 3-loop PWR with 157 fuel assemblies. Westinghouse has reported their result
Publikováno v:
Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation.
RELAP/SCDAPSIM is a nuclear reactor simulator and accident analysis code that has been used in the nuclear energy industry for many years. Currently, Innovative Systems Software is developing a new tool that will show the behavior of the core compone
Publikováno v:
Volume 6B: Thermal-Hydraulics and Safety Analyses.
The NuScale Small Modular Reactor (SMR) is an integrated Pressurized Water Reactor (iPWR) with the coolant flow based on the natural circulation. The reactor core consists of 37 fuel assemblies similar to those used in typical PWRs, but only half of
Autor:
Marina Perez-Ferragut, Daniel Dupleac, Chris M. Allison, Roxana-Mihaela Nistor-Vlad, Judith K. Hohorst, Ilie Prisecaru
Publikováno v:
Volume 9: Student Paper Competition.
RELAP/SCDAPSIM is a best-estimate nuclear tool designed to analyze the behaviour of reactor systems during normal and accident conditions. Three main versions of RELAP/SCDAPSIM are currently used by program members and licensed users to support a var