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Division Spotlight
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
M. García, J. Sanz, P. Sauvan, F. Ogando, D. López, A. Mayoral, V. Blideanu, C. Moreno
Nuclear Technology | Volume 168 | Number 1 | October 2009 | Pages 132-138
Dose/Dose Rate | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 1) / Radiation Protection | doi.org/10.13182/NT09-A9113
Articles are hosted by Taylor and Francis Online.
Before starting with the construction of the International Fusion Materials Irradiation Facility, the objective of the Engineering Validation and Engineering Design Activities (EVEDA) phase will be to demonstrate feasibility of design. For this EVEDA prototype, analysis of the dose rate evolution during the beam-off phase is necessary for radioprotection and maintenance feasibility purposes. The key points for determining the dose rates of the beam-off phase are on one hand the neutron source produced along the accelerator beam line and on the other hand the deuteron losses giving rise to this neutron source.A new methodology to compute the neutron source coming from the deuteron interactions with the intercepting material as well as with the deuterium previously implanted has been developed. This new procedure consists of evaluation of the low-energy deuteron-induced neutron source that is not calculated by most transport codes and assessment of the deuterium concentration evolution in the material, which is generally not taken into account in this type of calculation. The impact of this new approach on the neutron source and dose rate results is very relevant.In addition, different sets of deuteron losses computed during the last 3 yr have been compared and used for neutron activation and dose rate calculations. The effect of the deuteron losses upon neutron source production and residual dose rates in the vicinity of the accelerator components is evaluated, and implications for hands-on maintenance activities are discussed. The impact of the differences in the sets of deuteron losses has been found to be very important for dose rate evaluations. Using the most recent deuteron loss information, we obtain dose rate values more than one order of magnitude lower than those obtained using the former data.