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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.
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Nuclear and Emerging Technologies for Space (NETS 2025)
May 4–8, 2025
Huntsville, AL|Huntsville Marriott and the Space & Rocket Center
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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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Student encounters
Lisa Marshallpresident@ans.org
There is much I could have written about for this month’s issue of Nuclear News, and I have decided to reflect on conversations with our greatest asset: students. When we consider what the industry needs, I think about what students need to thrive. The educational ecosystem requires both enthusiasm and resources in and out of the classroom.
To attract and retain students, we must pay attention to cocurricular programming. Scholarships, fellowships, travel grants, internships, and co-ops—as well as our time and efforts—make a difference. Whether at schools, meetups and student conferences, or national and international meetings, we must continue to pour into our students at all levels. We also need to create an environment that pays attention to external factors that impact academic performance. This lift is a mightier one but just as important.
Naoya Matsui, Takahiro Maegawa, Kazuyuki Noborio, Ryuta Kasada, Yasushi Yamamoto, Satoshi Konishi
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 692-696
Test Blanket, Fuel Cycle, and Breeding | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A19173
Articles are hosted by Taylor and Francis Online.
Neutron transport and energy composition of neutron beam extracted from a cylindrical discharge type fusion device was studied by using the computer simulation code, MCNP. In this study, three concepts of neutron beam optics (reflector and moderator) were proposed and examined; combined reflector which consists of two layers of different materials, inserting a moderator into the reflector to thermalize the neutron beam, and bending the extraction channel to avoid direct extraction of high energy neutrons. Combined reflector system produces 3.2 times higher neutron flux than no reflector when using W and Fe as outer and inner reflectors. The beam convergence is not dependent on reflector materials. Polyethylene (PE) and Fe combination produces fast neutron beam where more than 90% of the neutrons are fast. Combination of PE and D2O produces more than 30% thermalized neutron beam, but it contains epithermal and fast neutrons. When using moderator (D2O), the thickness of which is over 30 cm, more than 90% of the neutrons are thermalized. The bend angle of 20° produces more than 80% thermalized neutron beam. Both inserting moderator and bending channel are effective to extract thermalized neutron beam. These results are useful for designing a neutron source which can produce specified neutron beam.
