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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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2021 Student Conference
April 8–10, 2021
North Carolina State University|Raleigh Marriott City Center
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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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A day in the life of the nuclear community
The November issue of Nuclear News is focused on the individuals who make up our nuclear community.
We invited a small group of those individuals to tell us about their day-to-day work in some of the many occupations and applications of nuclear science and technology, and they responded generously. They were ready to tell us about the part they play, together with colleagues and team members, in supplying clean energy, advancing technology, protecting safety and health, and exploring fundamental science.
In these pages, we see a community that can celebrate both those workdays that record progress moving at a steady pace and the exceptional days when a goal is reached, a briefing is delivered, a contract goes through, a discovery is made, or an unforeseen challenge is overcome.
The Nuclear News staff hopes that you enjoy meeting these members of our community—or maybe get reacquainted with friends—through their words and photos.
Alexis Jinaphanh, Nicolas Leclaire, Bertrand Cochet
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 53-68
Technical Paper | dx.doi.org/10.13182/NSE16-2
Articles are hosted by Taylor and Francis Online.
A continuous-energy sensitivity coefficient calculation to nuclear data capability has been recently developed in Version 5.C.1 of the MORET Monte Carlo code developed at Institut de Radioprotection et de Sûreté nucléaire (IRSN). The method used for implementation is the differential operator method. In this method, the estimation of the fission source derivatives is replaced by an estimation of the adjoint flux. Both methodology and tallies are described in this paper. The preliminary verification is mainly performed using code-to-code comparisons with the SCALE6.1 and MCNP6.1 software packages. Configurations used for verification are the Organisation for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA) Uncertainty Analyses for Criticality Safety Assessment (UACSA) Expert Group benchmarks, the Jezebel International Criticality Safety Benchmark Evaluation Project (ICSBEP) benchmark, and a configuration from the Matériaux en Interaction et Réflexion Toutes Epaisseurs (MIRTE) French proprietary experimental program. Results show good agreement among the different codes.
