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Kathryn Huff stepping down from DOE Nuclear Energy post
Huff
After serving two years as the Department of Energy’s assistant secretary for Nuclear Energy, Kathryn Huff will vacate that position on May 3 and return to teaching. Huff had started at the DOE in May 2021, serving for one year as the principal deputy assistant secretary for Nuclear Energy
“Serving in this capacity has been an unparalleled privilege, and I’m immensely grateful for the opportunity to have worked alongside you--the dedicated and talented public servants in Nuclear Energy, in DOE, and across the Biden-Harris Administration,” Huff wrote in an email announcement to colleagues last week. “I chose this timing to enable the smoothest transition back to my professorship at the University of Illinois at Urbana-Champaign where my beloved research, students, husband, and dog await.”
Hong-Ming Liu, Pin-Chieh Hsu
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 919-923
Dose/Dose Rate | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Protection | doi.org/10.13182/NT09-A9327
Articles are hosted by Taylor and Francis Online.
The 10B dose in boron neutron capture therapy (BNCT) was usually determined by multiplying the thermal neutron flux by the 10B concentration and the dose conversion factor. In this kind of application, the thermal neutron flux was commonly measured using gold foil activation techniques with and without the cadmium cover, assuming that the neutron spectrum has a Maxwellian distribution in the thermal range. This always generated uncertainties because the thermal neutron energy spectrum has no Maxwellian distribution in the body. The potential to determine the 10B dose by using a single LiF thermoluminescent dosimeter (TLD) is studied.The 10B dose in BNCT derives from the reaction of the thermal neutron with the 10B element. It always dominates the irradiation dose if the 10B concentration is higher than 20 ppm. Since the trends of the 10B absorption cross sections are similar to 6Li in the thermal neutron range, the LiF-TLD can be used for 10B dose determination in BNCT if the reaction of the thermal neutron with 6Li dominates the TLD response. The MCNP code is used to simulate the energy deposition in various LiF-TLDs and to show the suitability of LiF-TLD used for 10B dose determination in BNCT.The preliminary MCNP simulation shows that the TLD response strongly depends on the 6LiF content in the TLD. Comparing the TLD response, the 10B reaction, and the thermal neutron flux, they show the same distribution as a function of depth in a phantom irradiated with the BNCT neutron. On the other hand, not only is there a thermal neutron flux depression due to self-shielding within the TLD chip, but also there is significant perturbation around the TLD if the 6LiF content in the TLD is high enough. To balance these two factors, TLD-100 was recommended as a 10B dosimeter for BNCT.
