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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.
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2021 Student Conference
April 8–10, 2021
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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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Fukiushima Daiichi: 10 years on
The Fukushima Daiichi site before the accident. All images are provided courtesy of TEPCO unless noted otherwise.
It was a rather normal day back on March 11, 2011, at the Fukushima Daiichi nuclear plant before 2:45 p.m. That was the time when the Great Tohoku Earthquake struck, followed by a massive tsunami that caused three reactor meltdowns and forever changed the nuclear power industry in Japan and worldwide. Now, 10 years later, much has been learned and done to improve nuclear safety, and despite many challenges, significant progress is being made to decontaminate and defuel the extensively damaged Fukushima Daiichi reactor site. This is a summary of what happened, progress to date, current situation, and the outlook for the future there.
S. Domingo, Y. Herreras, F. Sordo, A. Lafuente, J. M. Perlado
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 710-717
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | dx.doi.org/10.13182/FST09-A8992
Articles are hosted by Taylor and Francis Online.
This paper presents a methodology for 3D neutronic calculations suitable for complex and extensive geometries. The geometry of the system design is first fully modeled with a CAD program; this modeling is then processed - requiring few simplifications - with MCNP-CAD interface in order to generate a MCNP geometry file. Neutronic irradiation results are finally achieved running the MCNP program, where the geometry input card used is directly the MCNP-CAD interface output. This methodology enables accurate neutronic calculations for complex geometries characterized by high detail levels, such as ITER or other fusion facilities (IFMIF), in which we are presently involved.This procedure has been applied to the Fast Ignition Fusion Reactor KOYO-F. We have determined the neutron fluxes and energy deposition in the reactor blanket, and obtained the front panel damage and activation for several alternative front panel materials. To carry out this calculation, KOYO-F blanket design is modeled using CATIA V5, and the selected CAD-MCNP interface is MCAM, developed by the FDS Team (China). The activation of the front panel material is finally evaluated with our code ACAB, based on the neutronic irradiation results provided by MCNP.
