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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Robert E. Einziger, Carl Beyer
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 134-146
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3860
Articles are hosted by Taylor and Francis Online.
Current risk assessments of spent fuel in storage and transportation casks use the properties of light water reactor fuel below 45 GWd/t U. Fuel is being driven to higher burnups that may influence the source term in cask accidents. To achieve these burnups the manufacturers are introducing new assembly designs and cladding alloys. As a result, at the higher burnups (50 GWd/t U) some of the characteristics of the fuel pellets, cladding, and assembly design used in the safety analysis have changed. The fuel pellet has developed a fine-grained, Pu-rich rim zone on its exterior surface. The source term may increase by up to three orders of magnitude over that expected from the particulate size distribution based on the fracture of the body of the pellets. The actual increase will depend on the fracture characteristics of the rim and number of fracture sites in the cladding. The cladding may acquire hydrogen contents up to 700 parts per million by weight during the increased exposure. Embrittlement of the cladding with subsequent loss of ductility may occur, especially if there is hydride reorientation. As a result, there may be a greater propensity for fracture of the rods upon impact, with subsequent release of fuel particulate and gas. Significantly improved source terms can be developed if additional data on fuel rim fracture as a function of impact energy, the dependence of cladding ductility for Zircaloy and the newer cladding alloys as a function of hydride reorientation, and release characteristics for fractured rods are obtained. Chalk River unidentified deposit spallation characteristics only make a significant contribution to the source term if the rods do not fracture in the accident or if a fire-only accident occurs.