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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
R. Crasta, S. Ganesh, H. Naik, A. Goswami, S. V. Suryanarayana, S. C. Sharma, P. V. Bhagwat, B. S. Shivashankar, V. K. Mulik, P. M. Prajapati
Nuclear Science and Engineering | Volume 178 | Number 1 | September 2014 | Pages 66-75
Technical Paper | doi.org/10.13182/NSE11-90
Articles are hosted by Taylor and Francis Online.
The (n,γ) and (n,2n) capture cross sections of 238U have been measured at neutron energies of 8.04 ± 0.30 and 11.90 ± 0.35 MeV from the 7Li(p,n) reaction using an activation and off-line gamma-ray spectrometric technique. The experimentally determined 238U(n,γ) and 238U(n,2n) reaction cross sections were compared with the evaluated data of ENDF/B-VII.0, JENDL-4.0, JEFF-3.1/A, and CENDL-3.1. The experimental values were found to be in agreement with the evaluated value based on ENDF/B-VII.0, JENDL-4.0, and JEFF-3.1/A but not with CENDL-3.1. The present measurement has been compared with literature data in a wide range of neutron energies. The 238U(n,γ)239U and 238U(n,2n)237U reaction cross sections were also calculated theoretically using the TALYS 1.4 computer code and compared with the experimental data.
