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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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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.
B. S. Shivashankar, S. Ganesan, H. Naik, S. V. Suryanarayana, N. Sreekumaran Nair, K. Manjunatha Prasad
Nuclear Science and Engineering | Volume 179 | Number 4 | April 2015 | Pages 423-433
Technical Paper | doi.org/10.13182/NSE14-19
Articles are hosted by Taylor and Francis Online.
The 58Ni(n,p)58Co reaction cross sections have been measured relative to two monitors: the cross sections for the formation of the 97Zr fission product in neutron-induced fission of (a) 232Th and of (b) 238U. It is demonstrated how to generate and combine covariance matrices (using partial uncertainties and microcorrelations) in relative measurements at various stages like efficiency calibration of the high-purity germanium detector, using the ratio of 58Ni(n,p)58Co reaction cross section relative to monitor cross section, and in the process of normalization. We further illustrate the weighted averaging of equivalent data as applicable in relative measurements. We provide the necessary data and the corresponding table of partial uncertainties as required for compilation in the EXchange-FORmat (EXFOR) database. This helps, in principle, anyone to generate and verify the steps in the calculation of the covariance matrices in the present work. We believe that it is important for all nuclear experimental scientists to incorporate a detailed data reduction procedure, reduced data, and partial uncertainties in their publications, to the extent possible, which will be very useful in EXFOR compilation.