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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Natalie Cannon is passionate about nuclear policy
Some people are born leaders, and some people make themselves leaders. Take Natalie Cannon, a fourth-year doctoral candidate in the Department of Nuclear and Radiological Engineering and Medical Physics at the Georgia Institute of Technology. She has been driven to succeed since she was a teenager in Southern California, when she was inspired by NASA’s Mars Exploration Program.
Jan Marivoet, Eef Weetjens
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 74-84
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3971
Articles are hosted by Taylor and Francis Online.
This paper presents evaluations of the impact of six advanced fuel cycles, ranging from the present "once-through" fuel cycle in light water reactors to a gas-cooled fast reactor with fully recycling of all actinides, on geological disposal in a clay formation. Both the dimensions and the radiological consequences of a geological repository for the disposal of high-level radioactive waste (HLW) and spent fuel are estimated. After a 50-yr cooling time, the thermal output of the HLW arising from advanced fuel cycles is significantly lower than that of spent fuel. This allows the dimensions of the geological repository to be reduced. The impact of advanced fuel cycles on the radiological consequences in the case of the expected evolution scenario is rather limited. The maximum dose, which is expected to occur a few tens of thousands of years after the disposal of the waste, is essentially due to fission products, and their amount is approximately proportional to the heat generated by nuclear fission. An important contributor to the total dose is 129I; the amount of 129I going into a repository strongly depends on the fraction of spent fuel that is reprocessed. By considering the evolution of the radiotoxicity of the waste, it can be expected that the radiological consequences of human intrusions into a repository will be significantly lower in the case of waste arising from advanced fuel cycles.
