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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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.
Ulrich Hesse
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 173-186
Technical Paper | Fuel Cycle | doi.org/10.13182/NT88-A34106
Articles are hosted by Taylor and Francis Online.
Reliable prediction of the characteristics of irradiated light water reactor fuels (e.g., afterheat power, neutron and gamma radiation sources, final uranium and plutonium contents) is needed for many aspects of the nuclear fuel cycle. Two main problems must be solved: the simulation of all isotopic nuclear reactions and the simulation of neutron fluxes setting the reactions in motion. In state-of-the-art computer techniques, a combination of specialized codes for lattice cell and burnup calculations is preferred to solve these cross-linked problems in time or burnup step approximation. In the program system OREST, developed for official and commercial tasks in the Federal Republic of Germany nuclear fuel cycle, the well-known codes HAMMER and ORIGEN are directly coupled with a fuel rod temperature module. Starting with a zero-dimensional burnup code such as ORIGEN, the importance of one- and more-dimensional neutron flux calculations in the field of isotope generation and depletion calculation is shown. OREST results are compared with measured isotope concentrations of depleted uranium dioxide samples and of mixed oxide (MOX) rods irradiated in different assembly positions. In addition, published results from two lattice cell burnup program systems are shown. Currently, ORIGEN (1973 version) is applied by many users in a stand-alone mode. The achievable accuracies are discussed. Only a few measurements of irradiated MOX fuels have been available. Considering the actual projects for reprocessing and recycling of nuclear fuels, further and fully documented isotope analyses are needed.
