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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.
J. Tommasi, G. Noguere
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 232-241
Technical Paper | doi.org/10.13182/NSE160-232
Articles are hosted by Taylor and Francis Online.
The PROFIL and PROFIL-2 experiments, performed in the Phénix demonstration fast reactor, irradiated 130 small separate samples containing almost pure isotopes. These highly accurate experiments are a very specific and powerful source of information on the nuclear data of major and minor actinides and several fission products. Their analysis is carried out using the ERANOS-2.1 code system associated to JEFF-3.1 cross-section, fission yield, and decay data. The consistency of the results demonstrates the overall good quality of the actinide nuclear data and experimental techniques used and points out where specific improvement is necessary: fission yields of 235U on neodymium isotopes (5% bias) and integral capture cross sections of the actinides 232Th, 234U, 242Pu, 244Cm, 246Cm (more than 10% bias), 233U, 237Np, 241Pu, and 243Am (bias between 5 and 10%). The optimal values of the branching ratios for 241Am capture (0.85 on 242gAm and 0.15 on 242mAm) are consistent with the latest evaluation data in the fast neutron range. A similar analysis characterized the degree of accuracy of the integral capture cross sections of 19 fission products. Two new experiments of the same kind have been irradiated in Phénix and will undergo dissolutions and isotopic analyses. When they are completed, the analysis of the results will provide additional useful data in both a standard and a slightly moderated neutron spectrum.