A computer code capable of modeling the burnup dependent static behavior
of a boiling water reactor was developed. The code calculates
three-dimensional quarter core power distributions using a simulated
two-group diffusion theory model. Thermal-hydraulic calculations account
for the interaction between power, coolant flow, and void fraction
distributions. Cross sections are...
Independent fission product yields are primary input nuclear
data in the evaluation of nuclear reactor after-heat when using a
nuclide-decay summation method. The error in yield values is one
of the major causes of uncertainty of this calculation. Since only
a small fraction of the fission product yields has been...
The development of nuclear reactors as an energy source
requires a substantial investment in capital and effort. This
development depends heavily on accurate calculational
methods.
Space-energy flux synthesis, also variously called the
spectral synthesis method, modal method, and overlapping
group method, is one possible method. In this method the
energy...
A standard fast reactor spectrum can be created by the partial moderation of the U-235 fission spectrum in an air cavity. Spherical natural uranium shells are driven by thermal neutrons from a thermal column. The uranium is placed at the center of a spherical graphite hohlraum to reduce the anisotropic...
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...
A method is presented for appraising the hazards to nuclear
power plants from missiles from surface traffic accident explosions.
Due to the infrequency with which surface traffic accident explosions
occur and the poor records kept concerning them, a probabilistic
method is chosen to investigate the overall hazards potential to
nuclear...
The gamma contribution to reactor afterheat
depends on gamma energy since high-energy commas are
more likely to escape from tilt. fuel. The objective of
this work is to investigate the gamma-energy spectrum
of a pure U-235 fission reactor.
Fission-product nuclides are first listed in order'
of importance as contributors to...
Unit cell or pin cell calculations form the basis for
most nuclear core modeling. Because of this, it is of primary
importance to perform these unit cell calculations
accurately.
The subject of this thesis is the analysis of one of
the major approximations made in unit cell modeling, the
infinite...
A recent review of nuclear reactor emergency core
cooling systems has required renewed investigations into
the present knowledge of experiments which have measured
after-heat. Of special interest are some experiments which
were performed after Shure's 1961 evaluation, upon which
the American Nuclear Society (ANS) recommended after-heat
curves are based.
Experiments...