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Thermal hydraulics (also called thermohydraulics) is the study of hydraulic flow in thermal fluids. The area can be mainly divided into three parts: thermodynamics , fluid mechanics , and heat transfer , but they are often closely linked to each other.
DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant nea-1683 ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses nea-1916 FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut sets nea-0624 JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR
Entrance to the Radiation Center. The Oregon State University Radiation Center (OSURC) is a research facility that houses a nuclear reactor, Gammacell 200 irradiator, several radiation laboratories, and multiple high-bay thermal hydraulics laboratories at Oregon State University (OSU) in Corvallis, Oregon, United States.
RELAP5-3D is an outgrowth of the one-dimensional RELAP5/MOD3 code developed at Idaho National Laboratory (INL) for the U.S. Nuclear Regulatory Commission (NRC). The U.S. Department of Energy (DOE) began sponsoring additional RELAP5 development in the early 1980s to meet its own reactor safety assessment needs.
A boiling water reactor (BWR) is a type of nuclear reactor used for the generation of electrical power. It is the second most common type of electricity-generating nuclear reactor after the pressurized water reactor (PWR). BWR are thermal neutron reactors, where water is thus used both as a coolant and as a moderator, slowing down
Reactors that use lead or lead-bismuth eutectic can be designed in a large range of power ratings. The Soviet union was able to operate the Alfa-class submarines with a lead-bismuth cooled intermediate-spectrum reactor moderated with beryllium from the 1960s to 1998, which had approximately 30 MW of mechanical output for 155 MW thermal power (see below).
A fully digital Reactor Protection System (RPS) (with redundant digital backups as well as redundant manual backups) ensures a high level of reliability and simplification for safety condition detection and response. This system initiates rapid hydraulic insertion of control rods for shutdown (known as SCRAM by nuclear engineers) when needed ...
The IRIS pressure vessel and systems contained within it. The coolant system consists of a pressurizer, Steam generators, and reactor coolant pumps (RCPs).These are all located within the reactor pressure vessel, making a very small, short loop that forms the primary coolant system, see the figure on the right for the relative locations of the components.