ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Latest News
Wyoming OKs construction of TerraPower’s Natrium plant
Progress continues for TerraPower’s Natrium plant, with the latest win coming in the form of a state permit for construction of nonnuclear portions of the advanced reactor.
Kazuo Shin, Yoshitomo Uwamino, Mitsuo Yoshida, Tomonori Hyodo, Takashi Nakamura
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 294-300
Technical Paper | doi.org/10.13182/NSE79-A19066
Articles are hosted by Taylor and Francis Online.
Spectra and attenuation profiles of neutrons and gamma rays transmitted through graphite piles were measured by an organic scintillator with an n-γ discrimination technique. The neutrons and gamma rays were produced in a graphite target placed in front of the piles, which were bombarded by 52-MeV protons. The piles were 54 cm high, 90 cm wide, and 11.7, 23.5, and 44.9 cm thick. The energy spectra of neutrons and gamma rays were obtained after unfolding by the FERDO code, from pulse-height distributions. Spectra calculated by use of a Monte Carlo neutron transport code developed for neutrons of energy up to 50 MeV show good agreement with the measured spectra.