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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
2021 Student Conference
April 8–10, 2021
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Nuclear Science and Engineering
Fusion Science and Technology
NC State celebrates 70 years of nuclear engineering education
An early picture of the research reactor building on the North Carolina State University campus. The Department of Nuclear Engineering is celebrating the 70th anniversary of its nuclear engineering curriculum in 2020–2021. Photo: North Carolina State University
The Department of Nuclear Engineering at North Carolina State University has spent the 2020–2021 academic year celebrating the 70th anniversary of its becoming the first U.S. university to establish a nuclear engineering curriculum. It started in 1950, when Clifford Beck, then of Oak Ridge, Tenn., obtained support from NC State’s dean of engineering, Harold Lampe, to build the nation’s first university nuclear reactor and, in conjunction, establish an educational curriculum dedicated to nuclear engineering.
The department, host to the 2021 ANS Virtual Student Conference, scheduled for April 8–10, now features 23 tenure/tenure-track faculty and three research faculty members. “What a journey for the first nuclear engineering curriculum in the nation,” said Kostadin Ivanov, professor and department head.
S. O'hira et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 621-624
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | dx.doi.org/10.13182/FST05-A1002
Articles are hosted by Taylor and Francis Online.
A new conceptual design of a tritium permeation test module assembly was developed, for simulation of tritium permeation in the real plasma facing components and validation of the models and codes for evaluation of the tritium permeation. The assembly was designed for tests using powerful ion sources, which has a capability to simulate condition relevant to that of the ITER divertor. The heat load test of the prototype module has been performed using an electron beam to verify thermal and mechanical behavior of the bonded structure and to assess its structural integrity under the cyclic heat loads. Then, the first tests using tritium ion beam generated by the TPE apparatus at TSTA/LANL with the prototype module was performed and procedure to measure tritium permeated was established. Considerations for tests using the target module with defects generated by neutron irradiation or accelerated ion beam irradiation will be also taken in the new module design.