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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
IAEA promoting nuclear energy with G20
The International Atomic Energy Agency launched a collaboration with the Group of 20 this week to highlight the key role that nuclear energy can play in achieving energy security and climate-change goals.
The aim of this first-of-its-kind partnership with G20—the world’s largest economic group—is to build momentum for nuclear power. This is the first time the IAEA has presented to G20 on issues relating to nuclear power.
A. Abdelghafar Galahom
Nuclear Science and Engineering | Volume 193 | Number 6 | June 2019 | Pages 638-651
Technical Paper | doi.org/10.1080/00295639.2018.1560757
Articles are hosted by Taylor and Francis Online.
This work presents a comparison between the homogeneous and heterogeneous [seed-blanket (SB)] fuel assembly used in the VVER-1200 core. The MCNPX 2.7 code with the ENDF/B-VII.0 data library was used to investigate the possible advantages that can be achieved when the SB assembly is used instead of homogeneous assembly. Thorium-232 was used as a fertile material in the blanket region and different fissile materials were investigated in the seed region. The neutronic characteristics of the presented designs were investigated by comparing four different combinations of fissile materials with (Th,U)O2 that were distributed uniformly through the whole assembly. The radial power distribution was investigated in both homogeneous and SB assemblies. The power distribution is flatter in the homogeneous assembly than the heterogeneous assembly. The suggested fuels in the SB assembly achieved a longer fuel cycle than the homogeneous assembly. Neutronic parameters related to reactor safety operation, such as control rod worth, Doppler reactivity coefficient, and effective delayed neutron fraction βeff have been investigated for the suggested fuel types. The SB assembly achieved a higher conversion ratio than the homogeneous assembly. Therefore, the fissile inventory ratio decreased more slowly with burnup in the case of SB than in the homogeneous assembly. Using 232Th instead of 238U reduced the production of the plutonium and the transuranic atoms.