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Considerations on the relationship between dosimetry metrics and experimental conditions

IEEE Transactions on Nuclear Science

Vehar, David W.; Cooper, Philip J.; King, Donald B.

Analysts, experimenters, and facilities have fallen into some poor practices in reporting many dosimetry metrics. While the experienced dosimetrist often knows the caveats that apply for a given dosimetry application, without proper reporting critical information is often lost before the data is received by the dosimetrist. In addition, the newcomers to the application of dosimetry are not being educated in the importance of a variation in the irradiation conditions. This paper captures some of the cases where care must be taken in expressing the proper context for a dosimetry metric. Examples focus on the interpretation of the response of a diamond photoconducting detector and a silicon transistor and highlight some common mistakes and some not-so-clear misinterpretations that even the experienced person often makes in this field. A careful study of the underlying physics reveals the non-intuitive trends in some metrics. Suggestions are made on how the community can minimize the chance of a dosimetry-related misinterpretation. © 2007 IEEE.

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MCNP/MCNPX model of the annular core research reactor

Depriest, Kendall R.; Cooper, Philip J.; Parma, Edward J.

Many experimenters at the Annular Core Research Reactor (ACRR) have a need to predict the neutron/gamma environment prior to testing. In some cases, the neutron/gamma environment is needed to understand the test results after the completion of an experiment. In an effort to satisfy the needs of experimenters, a model of the ACRR was developed for use with the Monte Carlo N-Particle transport codes MCNP [Br03] and MCNPX [Wa02]. The model contains adjustable safety, transient, and control rods, several of the available spectrum-modifying cavity inserts, and placeholders for experiment packages. The ACRR model was constructed such that experiment package models can be easily placed in the reactor after being developed as stand-alone units. An addition to the 'standard' model allows the FREC-II cavity to be included in the calculations. This report presents the MCNP/MCNPX model of the ACRR. Comparisons are made between the model and the reactor for various configurations. Reactivity worth curves for the various reactor configurations are presented. Examples of reactivity worth calculations for a few experiment packages are presented along with the measured reactivity worth from the reactor test of the experiment packages. Finally, calculated neutron/gamma spectra are presented.

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9 Results
9 Results