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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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ANS’s Mentor Match applications open
Applications are now open for the American Nuclear Society’s newly redesigned mentoring program. Mentor Match is a unique opportunity available only to ANS members that offers year-round mentorship and networking opportunities to Society members at any point in their education.
The deadline to apply for membership in the inaugural summer cohort, which will take place July 1–August 31, is June 20. The application form can be found here.
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%.
