A detail study of a Loss of Coolant Accident (LOCA) in a Pressurized
Water Reactor was conducted in order to estimate the consequences
of the accident using the computer simulation code EMERALD.
An effort was undertaken to modify the EMERALD code and to make
it operable on the OSU CYBER...
Neutron flux and gamma-ray dose have been measured in the
experimental facilities of the Oregon State TRIGA reactor.
Thermal neutron flux measurements utilized foil activation
techniques.
The gamma-ray dose was measured with a thermoluminescent
dosimetry system. The thermoluminescent material used was LiF.
Fast neutron spectrum measurements were performed. The
fast...
A sensitive ion chamber-electrometer system was used to determine
the Oregon State University TRIGA III reactor's ⁴¹Ar production
rate as a function of steady state reactor power and production of ⁴¹Ar
due to reactivity pulses up to $3.00. The relative contributions of the
argon duct effluent and the pneumatic transfer...
A prototype deep ocean nuclear moisture meter was developed
based on the detection of epithermal neutrons backscattered from
marine sediment molecules. Development consisted of choosing a
source, a detector, containment materials, and associated counting
equipment, followed by the construction and calibration of the probe.
Thermal neutron response of the probe...
A method is developed for calculating the reactivity
worth of the heavy water coolant of the Plutonium
Recycle Test Reactor (PRTR). The coolant reactivity
worth is determined by calculating the effective multiplication
constant of the reactor core with and without
the coolant in given process tubes. The calculational
method includes...
The determinants of electrical energy demand for the State of
Oregon are represented in a mathematical model. This model is
structured to operate in parallel with a computer simulation model of
the state and is utilized independently to investigate electrical energy
consumption during various scenarios of economic activity and energy...
This study focuses on investigation of the RETRAN modeling
concepts in the analysis of a safety valve discharge transient.
Three safety valve tests conducted at the Combustion Engineering
test facility were chosen for evaluation with RETRAN. It was
essential to apply the critical flow boundary condition at the
downstream nodes...