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...
This study addresses the application of a full
reactor system computer code to simulate the reactor
primary and secondary loop thermal hydraulics, plant
control and protection systems during the steam generator
tube rupture (SGTR) events. The Trojan nuclear plant
which is owned and operated by the Portland General
Electric (PGE)...
A study regarding steady-state conditions in boiling water
reactors was conducted in order to provide consistent initial conditions
for transient analysis using the computer simulation code,
RETRAN. Consistent steady states were generated with the RETRAN
model of the system by first establishing a reference state, and then
obtaining other steady...
In this study a method has been demonstrated by which
the departure from nucleate boiling ratio (DNBR) can be
readily determined for nuclear transients through application
of the COBRA-IIIC/MIT computer code. For input,
boundary conditions were specified relating the time-dependent
variations of core inlet coolant temperature,
system pressure, core heat...
Pressurized water reactors are presently controlled
by the use of materials which absorb neutrons as their
only effect; this reduces the neutron economy of the
system, since these neutrons are lost without helping to
maintain the chain reaction. The system examined in
this study replaces these absorbing materials with a...
The limiting conditions of operation with regard to system stability for BWRs are presently set using computer models which employ conservative assumptions regarding the mechanisms which affect stability. Development of BWR models using "best estimate" codes, such as RETRAN, may allow more exact stability limits to be determined and precise...
A detailed formulation of the momentum equation
including the Baroczy model for two phase friction is
presented in this thesis. Numerical techniques for solving
this equation along with the remainder of the describing
equations are also presented. This model has been
incorporated into an existing thermal hydraulic code for
simulating...
A vital safety concern in the analysis of nuclear power reactors
is the thermal hydraulic behavior of the reactor coolant system
under steady state and transient conditions. The goal of this
study has been to develop an appropriate model for the U-tube type
steam generators in a typical pressurized water...