The delayed neutron emission rates of U-235 and Pu-239 samples were measured
accurately from a thermal fission reaction. A Monte Carlo calculation using the Geant4
code was used to demonstrate the neutron energy independence of the detector used in the
counting station.
A set of highly purified actinide samples (U-235 and Pu-239) was irradiated in these
experiments by using the Texas A&M University Nuclear Science Center Reactor. A fast
pneumatic transfer system, an integrated computer control system, and a
graphite-moderated counting system were constructed to perform all these experiments.
The calculated values for the five-group U-235 delayed neutron parameters and the
six-group Pu-239 delayed neutron parameters were compared with the values
recommended by Keepin et al. (1957) and Waldo et al. (1981). These new values differ
slightly from literature values. The graphite-moderated counting station and the
computerized pneumatic system are now operational for further delayed neutron
measurement.
| Identifer | oai:union.ndltd.org:tamu.edu/oai:repository.tamu.edu:1969.1/ETD-TAMU-1134 |
| Date | 15 May 2009 |
| Creators | Chen, Yong |
| Contributors | Reece, W. Dan |
| Source Sets | Texas A and M University |
| Language | en_US |
| Detected Language | English |
| Type | thesis, text |
| Format | electronic, application/pdf, born digital |
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