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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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Former NRC commissioners lend support to efforts to eliminate mandatory hearings
A group of nine former nuclear regulatory commissioners sent a letter Wednesday to the current Nuclear Regulatory Commission members lending support to efforts to get rid of mandatory hearings in the licensing process, which should speed up the process by three to six months and save millions of dollars.
Koichi Okuno, Masayoshi Kawai, Hitoshi Yamada
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 545-552
Shielding Materials | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9241
Articles are hosted by Taylor and Francis Online.
Neutron shielding is very important for neutron facility construction. Concrete is usually used for neutron shielding. Although concrete is inexpensive, massive thickness is required. In the present work, a novel neutron shielding concrete using colemanite rock and peridotite rock was developed. Its shielding performance was evaluated through the transmission experiments by using 252Cf spontaneous fission source and the calculations with the MCNP5 code. The results show that a neutron 1/100 attenuation length of the neutron concrete shield with a typical colemanite content of 10 wt% is shorter by a factor of 1.7 than that of normal concrete. The results show that the shielding performance becomes better when the thickness is still thicker and the incident neutron spectrum is softer.The colemanite-peridotite concrete (neutron shielding concrete) was applied to biological shields of the Versatile High Intensity Total Diffractometer on the Japan Proton Accelerator Research Complex. Using this concrete permitted a reduction in the thickness of the shielding wall by a maximum of 25 cm compared to the normal concrete and a reduction of the iron in the beam dump.