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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Dağıstan Şahin, Kenan Ünlü, Kostadin Ivanov
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 324-339
Technical Paper | doi.org/10.13182/NT15-110
Articles are hosted by Taylor and Francis Online.
The main goal of this study is to verify the accuracy of burnup-coupled neutronic calculations when employing the Monte Carlo Utility for Reactor Evolutions (MURE) and MCNP5 codes for modeling TRIGA-type reactors, in this case the Penn State Breazeale Reactor (PSBR) core. Research and educational requirements mainly direct the PSBR operating schedule. With such operating schedules, one particular area of concern, specifically relating to nuclear analytical applications, is time-dependent changes in the neutronic characteristics of the reactor, specifically within the irradiation positions. Particular concern exists among scientists performing neutron activation analysis measurements as to whether continuous variations in reactor operations would cause significant fluctuations in the neutronic characterization parameters of the irradiation positions. A secondary objective of this study is to analyze fluctuations in the neutronic characterization parameters and their dependence on various core conditions as examined by detailed burnup-coupled neutronic simulations. In this study, a burnup-coupled neutronic simulation model of the PSBR is developed using the MURE and MCNP5 codes. The simulation results are verified by a series of experiments including measurements of the core excess reactivity starting from the first core loading in 1965 to 2012, control rod worth, fission product buildup, temperature-dependent reactivity loss, integral control rod worth curves, individual fuel element worth, and neutron flux. Local neutronic calculations of the simulation are confirmed by measuring neutronic characterization parameters for one of the irradiation positions within the PSBR core, namely, dry irradiation tube 1. Analyzing time-dependent data predicted by the simulation, the neutron temperature and the measure of the nonideal epithermal neutron flux distribution are found to be reasonably static. Conversely, the thermal-to-epithermal neutron flux ratio and spectral index are found to be relatively responsive to alterations in the core.
