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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Noriaki Nakao, Hiroshi Nakashima, Takashi Nakamura, Shun-ichi Tanaka, Susumu Tanaka, Kazuo Shin, Mamoru Baba, Yukio Sakamoto, Yoshihiro Nakane
Nuclear Science and Engineering | Volume 124 | Number 2 | October 1996 | Pages 228-242
Technical Paper | doi.org/10.13182/NSE96-A28574
Articles are hosted by Taylor and Francis Online.
The energy spectra of neutrons that penetrate 25- to 200-cm-thick concrete shields are measured using 40- and 65-MeV quasi-monoenergetic neutron sources at the 90-MeV AVF cyclotron of the Takasaki Ion Accelerator Facility for Advanced Radiation Application at the Japan Atomic Energy Research Institute. Source neutrons are produced at 3.6- and 5.2-mm-thick 7Li targets bombarded 43- and 68-Me Vprotons, respectively, and their spectra are measured with a proton recoil counter telescope and the time-of-flight method. In the shielding experiment, a BC501A organic liquid scintillator and a multimoderator spectrometer with a 3He counter (the Bonner Ball) are used as the neutron spectrometer. The collimated source neutrons are used to obtain the neutron spectra with the unfolding technique on the neutron beam axis and at off-center positions. MORSE Monte Carlo calculations are performed with the DLC119/HIL086 multigroup cross-section library for comparison with the measured data on the beam axis. The comparison reveals that the calculated spectra are in good agreement with the measured spectra. The measured data at off-center positions are used to check the calculational accuracy of the angular distribution of neutron scattering in the MORSE-CG, DOT3.5 discrete ordinates, and HETC-KFA2 Monte Carlo codes. The MORSE-CG code gives better results than the other two codes.