|dc.contributor.author||Kempf, Stephanie A.||
|dc.contributor.other||MIT Reactor Redesign Program||en_US
|dc.description.abstract||In response to increasing demands for the services of research reactors, a 5 MW LEUfueled
research reactor core is developed and optimized to provide high thermal flux
within specified limits upon thermal hydraulic performance, cycle length, irradiation
utilization, and manufacturability.
A novel fuel assembly concept which makes use of integral flux traps is postulated to
meet these requirements. Each assembly can be rotated into one of three different
configurations to produce flux traps of different size, shape, and neutron energy spectrum
within the core.
A method for predicting and guiding the search for the optimum geometry was sought.
Kriging has been chosen to predict the values of eigenvalue and thermal flux at untested
geometric parameters. Because kriging treats all measurements as the sum of a global
deterministic function and a stochastic departure from that function, predictions come
with a measurement of uncertainty. As a result, the analyst can search the design space
for likely improvement, or probe areas of high uncertainty for improvements that might
have been missed using other methods. The technique is used in an algorithm for
constrained optimization of the design, and a set of best practices for use of this are
The optimized design produces a peak thermal flux of 1.56 x 10[superscript 14] n/cm[superscript 2]s. Safety is demonstrated by presentation of reactivity feedback coefficients and the results of loss of flow and reactivity insertion transient analysis.
A single fission target can be used to produce 96 6-day Ci of [superscript 99]Mo per week. When the reactor is oriented to take advantage of high fast flux, steels can be subjected to damage
rates of 5.76 dpa per year. Silicon carbide can be damaged at a rate of 2.79 dpa/y. The
concept is a safe, versatile, proliferation-resistant means of supplying current and future
|dc.publisher||Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program||en_US
|dc.title||Design and Optimization of a High Thermal Flux Research Reactor Via Kriging-Based Algorithm||en_US
|dc.contributor.mitauthor||Kempf, Stephanie A.||
|dspace.orderedauthors||Kempf, Stephanie A.; Hu, Lin-Wen; Forget,Benoit||en_US