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...
A PC based on-line advanced plant simulator (OLAPS)
for high quality simulations of Portland General
Electric's Trojan Nuclear Facility is presented. OLAPS
is designed to simulate the thermal-hydraulics of the
primary system including core, steam generators, pumps,
piping and pressurizer. The simulations are based on a
five equation model that...
The research objective is to assess the performance of the SPN transport method, with a traditional finite volume spatial discretization in Cartesian geometry, on source detector problems relevant to urban detonation of an improvised nuclear device. In particular, we observe the character of the solution as a function of the...
In 2008, the Department of Energy (DOE) and Nuclear Regulatory Commission (NCR) decided that the Next Generation Nuclear Plant (NGNP) would be the Very High Temperature Reactor (VHTR). In support of the licensing and validation effort of the VHTR, Oregon State University was tasked with designing, building, and operating a...
The Adams-Larsen-Pomraning coupled transport model has been used to describe neutral particle transport in binary stochastic mixtures. Here, the mixing statistics are considered to be homogeneous Markovian processes. While the model is robust, the convergence behavior and efficiency of this coupled model have not been addressed. Countless iterative methods could...
A new method for accelerating the Upstream Corner Balance (UCB) discretization of the equation of transfer is introduced. The inconsistent acceleration equations for the UCB discretization are derived by applying the "Modified 4-Step" diffusion synthetic acceleration technique not to the UCB discretization, but instead to the simple corner balance (SCB)...
New low enriched uranium (LEU) fuels are being developed for replacement of high enriched uranium (HEU) fuels in high power research reactors. U-Mo LEU plate fuels have been identified as a candidate for replacement of current HEU fuels. However, U-Mo fuels tend to exhibit accelerated swelling typically at fission densities...
An important improvement in the area of reactor core neutronic modeling is the development and use of the methods based on "quasi-diffusion" (QD) low-order equations. This family of methods takes into account the transport exactly using "functionals" computed by solving transport equations, and is amenable to solution with a variety...
We present a deterministic spectral method to predict equilibrium temperature distributions, heat flux, and thermal conductivity in homogeneous and heterogeneous media. We solve the Boltzmann transport equation in a second order spatial, self-adjoint angular flux formulation. We implemented this method into the radiation transport code Rattlesnake, built using the MOOSE...