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Division Spotlight
Mathematics & Computation
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Kunihiko Tsuchiya, Hideki Imaizumi, Hiroshi Kawamura, Rokuro Oyamada, Toshiyuki Kabutomori, Yuichi Wakisaka
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1431-1436
Tritium Storage, Distribution, and Transportation | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30613
Articles are hosted by Taylor and Francis Online.
An in-situ irradiation test of a fusion blanket is planned in JMTR (Japan Materials Testing Reactor) using lithium containing ceramics as the tritium breeder and beryllium as the neutron multiplier. Therefore, it is necessary to develop getters for the recovery of the tritium gas. In this study, Zr9Ni11 alloy was chosen as a getter, and pressure-composition isotherms between 20°C and 300°C, and other properties were measured for its application. The breakthrough test of hydrogen was carried out with Ar+H2 gas. The evaluation of the examined getter materials leads to the conclusion that the Zr9Ni11 alloy may be used for the in-situ irradiation test of fusion blanket.
