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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
V. K. Gupta, Sunil Sunny
Nuclear Technology | Volume 114 | Number 3 | June 1996 | Pages 404-412
Technical Note | Radiation Protection | doi.org/10.13182/NT96-A35243
Articles are hosted by Taylor and Francis Online.
A large variety and amount of data of safety significance are routinely collected during the operation of a nuclear power plant (NPP). The data collected in the area of radiological protection have been analyzed to understand the behavior of activated corrosion products and fission products in the primary heat transport system of a pressurized heavy water reactor (PHWR). A correlation between the fuel integrity and the normalized external collective dose to maintenance work groups is clearly established. These studies should help in optimal work planning to keep the radiation exposure of work forces as low as reasonably achievable. The performance indicators introduced by the World Association of Nuclear Operators have been in use for the assessment of the operation and safety of NPPs in the member countries. This, however, helps only in the intercomparison of the operating and safety parameters of the operating NPPs. It was, therefore, felt necessary to work out a scheme that utilizes the data routinely collected at the NPP during the operating phase and also uses the safety analysis performed during design. With this in view, a new concept of safety indices (SIs), for overall assessment of the safety of the operating NPP has been evolved, including SIs in the areas of occupational collective dose, public dose, and fuel reliability, with a view to obtain a direct assessment of the safety of the plant operations, in comparison to a well-defined safety regime and/or regulatory constraints. The SIs in the aforementioned areas are discussed for the Rajasthan Atomic Power Station, an early Canada deuterium uranium PHWR, for the period from 1992 through 1993. The SIs could form a basis for communication among the utilities, the regulatory bodies, and the public, since the concept is direct and simple.