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2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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My story: Stanley Levinson—ANS member since 1983
Levinson early in his career and today.
As a member of the American Nuclear Society, I have been to many conferences. The International Conference on Probabilistic Safety Assessment and Analysis (PSA ’25), embedded in ANS Annual Meeting in Chicago in June, held special significance for me with the PSA ’25 opening plenary session recognizing the 50th anniversary of the publication of WASH-1400, which helped define my career. Reflecting on that milestone sent me back to 1975, when I was just an undergraduate student studying nuclear engineering at Rensselaer Polytechnic Institute (RPI) in Troy, N.Y., focusing on my mechanics, fluids, and thermodynamic classes as well as my first set of nuclear engineering classes. At that time—and many times since—the question “Why nuclear engineering?” was raised.
Yoshiyuki Asaoka, Kunihiko Okano, Tomoaki Yoshida, Ryouji Hiwatari, Seiji Mori
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 1018-1022
Safety and Environment | doi.org/10.13182/FST01-A11963376
Articles are hosted by Taylor and Francis Online.
Radioactive waste generated from the CREST reactor has been evaluated. Activation of blankets and shields used during a plant lifetime was evaluated by an activation calculation code taking into accounts of the distribution of neutron wall loading and the scenario of blanket replacement. Limits on surface dose limits define the feasibility of recycling by remote handling (RHR) and by hands-on operation (HOR). After 50 years for decay of activated components, surface dose rate of most of components exceeds 10 mSv/h and cannot be recycled. Some of shields are lower than 10 mSv/h and have a possibility of RHR. After 100 years, surface dose rate of all components is lower than 3 mSv/h, and RHR is feasible. Half of shields are lower than 0.01 mSv/h and have a possibility of HOR. After 125 years, dose rate of all components is lower than 1 mSv/h. RHR with a relatively simple shielding precaution may be feasible. In the cases of 150 years or later, little degradation of dose rate can be expected. Therefore, the used components should be managed within approximately 125 years by suitable methods.