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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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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.
Hisashi Sagawa, Kuniaki Miura, Hiroshi Kawamura, Rokuro Oyamada
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1073-1077
Analysis and Accountancy | 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-A30549
Articles are hosted by Taylor and Francis Online.
To obtain engineering data for a design of a fusion blanket, a program in which a mock-up simulating a blanket structure is irradiated is proceeded in the JMTR (Japan Materials Tasting Reactor) project.1 It is indispensable for this irradiation test to purge the tritium produced in the mock-up by the sweep gas and to measure the tritium concentration in the sweep gas on line. However, the bad effects such as tritium adsorption on the inner surface of the pipe and tritium diffusion from the pipe are apprehended, because the distance between the mock-up and an ionization chamber is about 20m long. Therefore, it is necessary to develop a sweep gas sensor which can measure the tritium concentration in the mock-up directly without the above apprehension. A sweep gas sensor had been fabricated on trial and several performance tests were carried out. From the results of the tests, it was found that this sensor could be used at the atmosphere of high temperature of 600–700°C and had good response.