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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
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.