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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
2021 Student Conference
April 8–10, 2021
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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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.
Brian S. Triplett, Eric P. Loewen, Brett J. Dooies
Nuclear Technology | Volume 178 | Number 2 | May 2012 | Pages 186-200
Technical Paper | Small Modular Reactors / Fission Reactors | dx.doi.org/10.13182/NT178-186
Articles are hosted by Taylor and Francis Online.
The Power Reactor Innovative Small Module (PRISM) designed by GE Hitachi Nuclear Energy is a small, modular, sodium-cooled fast reactor. The PRISM core is located in a pool-type containment vessel and is fueled with metallic fuel. Each PRISM produces 311 MW of electricity. The PRISM is inherently safe due to its negative power reactivity feedback, large in-vessel coolant inventory, passive heat removal systems, below-grade siting, and atmospheric reactor vessel operating pressure. In NUREG-1368, "Preapplication Safety Evaluation Report for the Power Reactor Innovative Small Module (PRISM) Liquid-Metal Reactor," the U.S. Nuclear Regulatory Commission stated that "On the basis of the review performed, the staff, with the ACRS [Advisory Committee on Reactor Safeguards] in agreement, concludes that no obvious impediments to licensing the PRISM design have been identified." PRISM is able to fission electrometallurgically recycled used nuclear fuel (UNF) from light water reactors as well as weapons-grade materials. PRISM, with the associated Nuclear Fuel Recycling Center, represents a safe, diversion resistant, commercially viable technology for recycling UNF with a small modular reactor.