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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
Satoshi Konishi, T. Nagasaki, T. Hayashi, K. Okuno
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 668-672
Plasma Fueling and Fuel Cycle | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40234
Articles are hosted by Taylor and Francis Online.
Behavior and improvement of the ZrCo based intermetallic materials for tritium recovery, storage and supply are studied. Compound ZrCo was found to be subject to disproportionation at high temperature under high hydrogen pressure to form ZrCo2 and ZrH2. This process is completely reversed by vacuum treatment at temperature above 500°C for several hours. Kinetics of the disproportionation was described to be similar to phase transition that have apparent incuvation time to take place. The logarithmic reaction rate constant was related to the reciprocal temperature. With some precautions drawn from the results, this reaction is not a problem in practice. For the application that needs prolonged supply of relatively high-pressure tritium, solid solution of ZrCo and HfCo was developed as an improvement of the material. Materials otained by arc melting with compoistion of Zr(1−x)HfxCo (0<x<0.5) exhibits single plateaus in pressure - composition isotherms when hydrogenated. Repeated hydrognation - dehydrogenation cycles did not generate separate ZrCo and HfCo phases. The equilibrium hydrogen pressure in the plateau regions are expressed as a functio of reciprocal temperature and increases with increasing HfCo contents. This material provides controlled equilibrium hydrogen pressure required for specific applications of tritium storage nad supply.
