Zobrazeno 1 - 10
of 32
pro vyhledávání: '"Gordon Kohse"'
Autor:
Ryotaro Okabe, Shangjie Xue, Jayson R. Vavrek, Jiankai Yu, Ryan Pavlovsky, Victor Negut, Brian J. Quiter, Joshua W. Cates, Tongtong Liu, Benoit Forget, Stefanie Jegelka, Gordon Kohse, Lin-wen Hu, Mingda Li
Publikováno v:
Nature Communications, Vol 15, Iss 1, Pp 1-13 (2024)
Abstract Radiation mapping has attracted widespread research attention and increased public concerns on environmental monitoring. Regarding materials and their configurations, radiation detectors have been developed to identify the position and stren
Externí odkaz:
https://doaj.org/article/fc5b1415373949fd88b6ece1d25af13e
Autor:
Ryotaro Okabe, Shangjie Xue, Jiankai Yu, Tongtong Liu, Benoit Forget, Stefanie Jegelka, Gordon Kohse, Lin-Wen Lu, Mingda Li
In recent years, radiation mapping has attracted widespread research attention and increased public concerns on environmental monitoring. In terms of both materials and their configurations, radiation detectors have been developed to locate the direc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f2e92517d9aef3fcf69783660c2d6ada
https://doi.org/10.21203/rs.3.rs-2561877/v1
https://doi.org/10.21203/rs.3.rs-2561877/v1
Publikováno v:
Fusion Science and Technology. 71:549-554
The MIT Nuclear Reactor Laboratory (NRL) has irradiated lithium-beryllium fluoride (flibe) salt as part of an on-going U.S. Department of Energy-funded Integrated Research Project to develop a Fluoride Salt High-Temperature Reactor (FHR). As part of
Autor:
Mitchell K. Meyer, Kurt A. Terrani, Gordon Kohse, Mehdi Balooch, Donald R. Olander, David Carpenter, Dennis D. Keiser
Publikováno v:
Journal of Nuclear Materials. 486:381-390
Three hydride mini-fuel rods were fabricated and irradiated at the MIT nuclear reactor with a maximum burnup of 0.31% FIMA or ∼5 MWd/kgU equivalent oxide fuel burnup. Fuel rods consisted of uranium-zirconium hydride (U (30 wt%)ZrH1.6) pellets clad
Autor:
Brenda L. Garcia-Diaz, Lingfeng He, Darin J. Tallman, Robert L. Sindelar, E. N. Hoffman, Gordon Kohse, Michel W. Barsoum
Publikováno v:
Journal of Nuclear Materials. 468:194-206
Herein we report on the characterization of defects formed in polycrystalline Ti 3 SiC 2 and Ti 2 AlC samples exposed to neutron irradiation – up to 0.1 displacements per atom (dpa) at 350 ± 40 °C or 695 ± 25 °C, and up to 0.4 dpa at 350 ± 40
Publikováno v:
Progress in Nuclear Energy. 80:37-44
The Massachusetts Institute of Technology Reactor (MITR) is a 6 MW tank-type reactor with a compact core design. It is moderated and cooled by light-water and has a heavy-water reflector. The MITR is a unique test bed for a wide range of nuclear mate
Autor:
Robert L. Sindelar, El’ad N. Caspi, E. N. Hoffman, Brenda L. Garcia-Diaz, Michel W. Barsoum, Gordon Kohse, Darin J. Tallman
Publikováno v:
Acta Materialia. 85:132-143
Herein we report on the effect of neutron irradiation – of up to 0.1 displacements per atom at 360(20) °C or 695(25) °C – on polycrystalline samples of Ti3AlC2, Ti2AlC, Ti3SiC2 and Ti2AlN. Rietveld refinement of X-ray diffraction patterns of th
Publikováno v:
Nuclear Engineering and Design. 277:1-14
Hydride metallic fuel is known to have several advantages compared to uranium oxide fuel, including enhanced thermal conductivity, large negative temperature reactivity coefficient, and reduced requirement for water moderator. In order to investigate
Autor:
Gordon Kohse, D. L. Knudson, Brandon S. Fox, Keith G. Condie, Heng Ban, Joshua Daw, Joy L. Rempe
Publikováno v:
IEEE Transactions on Nuclear Science. 57:2653-2661
A key component of the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) effort is to develop and evaluate in-pile instrumentation capable of providing real-time measurements of key parameters during irradiation. This paper describ
Publikováno v:
Nuclear Technology. 160:150-168
This paper describes an irradiation test of high-power-density internally and externally cooled annular fuel samples in the 5-MWMassachusetts Institute of Technology (MIT) research reactor MITR-II. The design of the irradiation facility is briefly re