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Division Spotlight
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.
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.
V. Abella, R. Miró, B. Juste, G. Verdú
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 53-57
Technical Paper | Special Issue on the 16th Biennial Topical Meeting of the Radiation Protection and Shielding Division / Radiation Transport and Protection | doi.org/10.13182/NT11-A12269
Articles are hosted by Taylor and Francis Online.
This work is focused on coupling PLanUNC (PLUNC), a set of software tools for radiotherapy treatment planning (RTP), with MCNP5 Monte Carlo N-Particle transport code, utilizing the RANDO phantom as the patient model and the Elekta Precise linac as the irradiation source for comparison. Thus, the main goal of this paper is to compare the results obtained from the default calculations of the treatment plan software with those obtained via the implementation of MCNP5 calculations. Monte Carlo techniques have been proved to be a more accurate dose calculation aid than conventional treatment planning systems, having the only limitation of computer time. The implementation of MCNP5 calculations in a commercial RTP software aims to provide more accurate dose mapping of the patient in reasonable computer times. The results obtained in this paper represent a significant contribution in the development of RTP patient dose simulations.
