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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.
Bhawna Pandey, P. M. Prajapati, S. Jakhar, C. V. S. Rao, T. K. Basu, B. K. Nayak, A. Saxena, S. V. Suryanarayana
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 313-320
Technical Paper | doi.org/10.13182/NSE14-26
Articles are hosted by Taylor and Francis Online.
The radionuclide 55Fe (t1/2 = 2.73 years) is one of the radionuclides produced in large quantities inside a fusion reactor. The excitation function of the (n,p) reaction from threshold to 20 MeV and proton emission spectra from the 55Fe target at 14-MeV neutron energy are calculated using optimized input parameters in the nuclear reaction modular codes EMPIRE-3.1 and TALYS-1.4. The codes account for the major nuclear reaction mechanisms, including direct, preequilibrium, and compound nucleus contributions. The present results of 55Fe(n,p)55Mn are compared with the existing evaluated nuclear data libraries ROSFOND-2010, JEFF-3.1, and EAF-2010 along with systematics around 14-MeV neutron energy. The prediction accuracy of the present calculation is considered to satisfy the requirement for fusion reactor applications. The theoretical nuclear model calculations with a reliable parameter set up to 20 MeV are recommended to estimate the cross section of radionuclides or unstable targets in the mass region A ∼ 50 to 60. The present work is an important step to study the cross section of the 55Fe(n,p)55Mn reaction by a surrogate method.
