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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.
Marko Maucec, Matjaz Ravnik, Bogdan Glumac
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 255-264
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2867
Articles are hosted by Taylor and Francis Online.
A criticality safety study of various forms of multiplying medium based on RBMK-1000 fuel elements is presented. The calculations were performed with the Los Alamos National Laboratory Monte Carlo MCNP4B code. Continuous energy cross-section data have been taken from the ENDF/B-VI and ENDF/B-V libraries and S(,) scattering functions from the ENDF/B-IV library. A detailed three-dimensional model of the RBMK fuel element has been developed. A set of parametric calculations was performed for some hypothetical fuel conditions with the infinite model of storage lattice. Multiplying properties of homogenized mixture of fuel and moderator were also analyzed. Certain combinations of moderator (graphite-water mixture) and fuel may yield a significantly increased multiplication factor with respect to normal reactor lattice conditions. MCNP calculations were performed for fresh fuel conditions. The reduction of the multiplication factor due to burnup up to 20 GWd/TU was estimated using the WIMS/D-5 code for lattice-cell conditions. It was observed that the multiplication factor (kinf or keff) does not exceed unity if the burnup is taken into account regardless of the assumptions on the fuel conditions.
