This work describes the fabrication of a high uranium density fuel for the
Reduced Enrichment of Research and Test Reactors Program. In an effort to decrease
the use of high enriched uranium in research and test reactors around the world, new
fuels with high uranium densities must be developed such...
The Generation IV Very High Temperature Reactor (VHTR) design is being actively
studied in various countries for application due to its inherent passive safe design,
higher thermal efficiencies, and proposed capability of providing high temperature
process heat. The pebble bed core is one of two core designs used in gas...
A large, multi-year experimental program has been conducted to develop a strain gaging program for application to the flow testing of prototypic, plate-type fuel for high performance research reactors. This test program has resulted in the selection of appropriate strain gage construction, adhesives, and protective coatings to allow the
acquisition...
Among the candidates for the next generation of nuclear power plant is the high temperature gas reactor (HTGR). Since the HTGR does not have the same operational history as water cooled reactors do in the United States, investigation into the response of different accident phenomena is still an active area...
The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU) and Idaho National Engineering and Environmental Laboratory (INEEL) under the Nuclear Energy Research Initiative (NERI) program to address the growing demand for energy and electricity....
High Temperature Gas Reactors (HTGR) are a type of power plants that can provide industrial process heat and high efficiency, carbon-free electricity. The High Temperature Test Facility (HTTF) has been designed to provide data that can be used for the validation of system codes and verification of passive safety features...
In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear...
The Hydro-Mechanical Fuel Test Facility (HMFTF) is being built at Oregon State University to evaluate fluid flow through plate-type fuel assemblies. The first plate assembly that will be examined in the facility is the Generic Test Plate Assembly (GTPA). The GTPA consists of an array of six parallel flat plates,...
In order to support the growing satellite propulsion industry, a hybrid Particle-In-Cell (PIC) simulation with fluid treatment of electrons and neutral particles was developed to model the SPT-70 Hall thruster. The 2D, C++ code assumes azimuthal symmetry and a uniform magnetic field in the radial direction with the simulation domain...
The Very High Temperature Reactor (VHTR) has two possible core configurations, a hexagonal prismatic and a pebble bed. It is essential that an experimental facility be built for the validation of computer codes for the safe operation of the VHTR. The scaling of the prismatic core configuration has been analyzed...