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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Hiromasa Iida, Yasushi Seki
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 302-307
Technical Paper | doi.org/10.13182/NSE80-A21320
Articles are hosted by Taylor and Francis Online.
In using a Monte Carlo transport code, particle fluxes are underestimated with a calculational model using specular reflection boundaries when a point detector estimator that scores only the direct contribution to the detector from a collision point within the model is used. This underestimation occurs because the contributions from collision points outside the calculational model are neglected. An additional scoring scheme is developed to compensate for the discrepancy; the new scheme is implemented to three-dimensional Monte Carlo transport code MORSE-GG. Validity of the method is shown by test calculations with ANISN and revised MORSE-GG.