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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
George Houghton, Clyde Jupiter, Gerald Trimble, David Spielberg, Paul G. Klann, Water A. Paulson
Nuclear Technology | Volume 6 | Number 1 | January 1969 | Pages 81-92
Technical Papers and Note | doi.org/10.13182/NT69-A28271
Articles are hosted by Taylor and Francis Online.
The absolute gamma dose was measured at 60 locations within the Tungsten Water-Moderated Reactor critical assembly. The neutron dose was measured at 30 locations. Graphite wall thimble ionization chambers filled with carbon dioxide were used for gamma measurements and polyethylene wall chambers filled with ethylene were used for mixed gamma and neutron fluxes. The chambers were absolutely calibrated in a bremsstrahlung beam against a secondary calibration standard and in a reactor against a water-filled calorimeter. These calibrations were used to determine the absolute gamma and neutron responses for the chambers; this permitted partitioning the measured mixed radiation dose into a neutron dose. The measured gamma doses were compared with an ATHENA Monte Carlo calculation. Good agreement was found for the 16 locations compared. The average deviation was 10%. In addition, the measured neutron doses were compared with a first-collision calculation of the dose. The calculated neutron doses were uniformly low with an average deviation from the measurement of 18%.