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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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.
G. R. Keepin, C. W. Cox
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 670-690
Technical Paper | doi.org/10.13182/NSE60-A25852
Articles are hosted by Taylor and Francis Online.
The reactor kinetic equations are reduced to an integral form convenient for explicit numerical solution, involving no approximations beyond the usual space-independent assumption. Numerical evaluation is performed by the RTS (Reactor Transient Solution) code, written in FORTRAN II for the IBM-704 computer. The characteristic roots and residues which arise in this method of solution have been computed and are tabulated in detail for each of the main fissile species. Analytic or point-function reactivity variation may be introduced, together with constant or time-varying reactivity compensation, and the resulting power response, total energy release, and compensated reactivity computed precisely as functions of time. The code solves the general non-equilibrium kinetics problem with extraneous sources, the customary equilibrium solution being a special case of the general solution. Practical use of the method is demonstrated through computed response curves for representative reactivity-addition functions in various types of chain-reacting systems.