Publications

Abstract not provided.

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.

Abstract not provided.

L-{alpha}-alanine, a nontoxic polycrystalline amino acid, has been investigated for use in high-precision, high-level absorbed-dose measurements in mixed neutron/photon environments such as research and test reactors. The technique is based on the use of electron paramagnetic resonance spectroscopy to determine the extent of free radical production in a sample exposed to ionizing radiation, and has been successfully used for photon absorbed-dose measurements at levels exceeding 10{sup 5} Gy with high measurement precision. Application of the technique to mixed environments requires knowledge of the energy-dependent response of the dosimeter for both photons and neutrons. Determination of the dosimeter response to photons is accomplished by irradiations in {sup 60}Co and bremsstrahlung sources and by calculations of energy-dependent photon kerma. Neutron response is determined by irradiations in conjunction with CaF{sub 2}:Mn thermoluminescence dosimeters and by calculations of energy-dependent neutron kerma. Several neutron environments are used, including those provided by the Annular Core Research Reactor and Sandia Pulsed Reactor.

An automatic optical track identification/counting system has been developed for counting the total number of fission tracks on a fused quartz solid state track recorder. The system is capable of analyzing up to twenty recorders a day with an operator input of less than two hours. The uncertainty introduced by the counting system is about one percent. 6 refs., 2 figs.