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Keywords: Materials
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Journal Articles
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041007.
Paper No: NERS-17-1194
Published Online: September 10, 2018
.... Assoc. Editor: Akos Horvath. 26 10 2017 05 04 2018 Current reactors Nuclear fuels Nuclear safety Radiation protection Materials Security Radiation science Nuclear reactor pressure vessels steels (RPVS) are the main components of pressurized water reactor, which...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041017.
Paper No: NERS-17-1142
Published Online: September 10, 2018
..., 2018; published online September 10, 2018. Editor: Igor Pioro. 08 10 2017 21 05 2018 Current reactors Fuel Cycle Nuclear engineering Nuclear fuels Radioactive waste management Decommissioning Materials The management of long-lived radioactive production in the spent...
Journal Articles
Journal Articles
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041022.
Paper No: NERS-17-1279
Published Online: September 10, 2018
... simulation results agree well with previous results. Manuscript received October 31, 2017; final manuscript received May 25, 2018; published online September 10, 2018. Assoc. Editor: Dmitry Paramonov. 31 10 2017 25 05 2018 Nuclear fuels Materials The materials of fusion...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031017.
Paper No: NERS-17-1071
Published Online: May 16, 2018
... , Aluminum 6063 , Aluminum 1100 , control rod poison, mild steel, and SS-304 definitions used in the models were based on definitions from Tables 3.5, 3.17, 3.15, 3.21, 3.18, and 3.19 of [ 1 ], respectively. The two materials with the highest impact on the k-eff are naturally the fuel...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031019.
Paper No: NERS-17-1269
Published Online: May 16, 2018
... Next generation reactors Nuclear engineering Nuclear fuels Materials Multipurpose hYbrid Research Reactor for High-tech Applications (MYRRHA) is a flexible fast-spectrum irradiation facility currently under development at SCK•CEN. The selected primary coolant and spallation target...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031011.
Paper No: NERS-17-1069
Published Online: May 16, 2018
.... It is speculated that uranium and zirconium oxide solid solution (U,Zr)O 2 is one of the major materials in the fuel debris from 1F. In addition, the Zr content of the fuel debris from 1F is expected to be higher than that of the debris from TMI-2 because the 1F reactors were boiling-water reactors...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031008.
Paper No: NERS-17-1103
Published Online: May 16, 2018
...; final manuscript received March 10, 2018; published online May 16, 2018. Assoc. Editor: Akos Horvath. 03 09 2017 10 03 2018 1 Corresponding author. Coupled codes Nuclear fuels Nuclear safety Materials Security Understanding and predicting the evolutionary behavior...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031020.
Paper No: NERS-17-1304
Published Online: May 16, 2018
... a reduction in the centerline temperature and temperature gradient in dispersed fuels but also reveals the maximum concentration of fissile material (U 3 O 8 , U 3 Si 2 , and UN) that can be incorporated in the Al matrix without the centerline melting. Furthermore, these predictions enable the experimental...
Journal Articles
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2018, 4(3): 034503.
Paper No: NERS-17-1278
Published Online: May 16, 2018
.... 31 10 2017 20 03 2018 Nuclear fuels Materials Uranium dioxide (UO 2 ) is the typical fuel that is used in the current nuclear power plant due to its high melting temperature and the stable fluorite structure under high dose irradiation. Fission gas atoms are produced during...
Journal Articles
Publisher: ASME
Article Type: Technology Review
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020914.
Paper No: NERS-16-1166
Published Online: March 5, 2018
.... Manuscript received December 9, 2016; final manuscript received June 10, 2017; published online March 5, 2018. Assoc. Editor: Michal Kostal. 09 12 2016 10 06 2017 Design-basis event Nuclear fuels Nuclear safety Materials Security The Chernobyl and Fukushima accidents...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011014.
Paper No: NERS-17-1029
Published Online: December 4, 2017
...; the gas conductance and radiant conductance of gap heat transfer were considered, the forced convective heat transfer on the outer surface of cladding was considered. Meanwhile, the irradiation effects and the thermal effects on the materials parameters such as thermal conductivity, specific heat...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011019.
Paper No: NERS-17-1022
Published Online: December 4, 2017
... taken at different magnifications of the sample. Manuscript received March 27, 2017; final manuscript received July 26, 2017; published online December 4, 2017. Assoc. Editor: Thomas Schulenberg. 27 03 2017 26 07 2017 Next generation reactors Nuclear fuels Materials...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011015.
Paper No: NERS-17-1039
Published Online: December 4, 2017
... a core outlet temperature of 650 °C at 25 MPa and a peak cladding temperature as high as 800 °C. Corrosion/oxidation resistance is an important factor in material selections and also coating considerations. Most of the reported supercritical water (SCW) test data have been obtained at temperatures up...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041006.
Paper No: NERS-16-1099
Published Online: July 31, 2017
... 06 2017 Nuclear fuels Materials The thermal conductivity of UO 2 has been investigated for decades [ 2 , 5 – 7 ]. Harding and Marting have summarized the experimental data and give the expression of thermal conductivity of unirradiated UO 2 [ 8 ]. Lucuta et al. have...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041004.
Paper No: NERS-16-1030
Published Online: July 31, 2017
... June 15, 2017; published online xx xx, xxxx. Assoc. Editor: Brian Ikeda. Current reactors Nuclear engineering Nuclear fuels Materials Stress corrosion cracking (SCC) of Canada deuterium uranium (CANDU ® ) fuel sheathing could be partially mitigated via chemical reactions between iodine...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041007.
Paper No: NERS-17-1008
Published Online: July 31, 2017
... was designed primarily to assess fission product transport through various graphite materials. Irradiation in the ATR started in December 2011 and finished in April 2014. Forty-eight (48) tristructural-isotropic-fueled compacts were inserted into 12 separate capsules for the experiment. The purpose...
Journal Articles
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2017, 3(3): 030914.
Paper No: NERS-16-1059
Published Online: May 25, 2017
... Technical White Paper , Crane Materials International, Atlanta, GA. http://www.isotecsecurity.com/isowp/wp-content/uploads/2016/03/aluminum_corrosion.pdf [4] Plankey , B. J. , Patterson , H. H. , and Cronan , C. S. , 1986 , “ Kinetics of Aluminum Fluoride Complexation in Acidic Water...