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Keywords: Next generation reactors
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Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021109.
Paper No: NERS-19-1064
Published Online: February 24, 2020
... for the regimes of normal, deteriorated and mixed heat transfer is made. e-mail:  videev@mephi.ru e-mail:  vskharitonov@mephi.ru e-mail:  baisov75@gmail.com e-mail:  churkin@grpress.podolsk.ru 13 04 2019 25 12 2019 24 02 2020 next generation reactors supercritical fluids...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041020.
Paper No: NERS-17-1289
Published Online: September 10, 2018
..., this work contributes to a realistic analysis of nuclear safety. 1 Corresponding author. Manuscript received November 6, 2017; final manuscript received July 16, 2018; published online September 10, 2018. Assoc. Editor: Juan-Luis Francois. 06 11 2017 16 07 2018 Next generation...
Journal Articles
Journal Articles
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
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031003.
Paper No: NERS-17-1197
Published Online: May 16, 2018
...; final manuscript received February 17, 2018; published online May 16, 2018. Assoc. Editor: Tomio Okawa. 26 10 2017 17 02 2018 Advanced reactors Next generation reactors Nuclear safety Thermal hydraulics Security During the material relocation phase of a hypothetical...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031005.
Paper No: NERS-17-1045
Published Online: May 16, 2018
... Schulenberg. 30 04 2017 03 10 2017 Next generation reactors Fig. 2 Canadian SCWR fuel channel with fuel assembly The fuel cladding is designed to be collapsible. The collapsible cladding allows the full 25 MPa pressure of the coolant to be supported by the fuel pellets...
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
... 23 03 2018 Fuel cycle Next generation reactors Nuclear fuels Nuclear safety Research reactors Radioactive waste management Decommissioning Materials Security Figure 2 provides the κ e f f of Al dispersed fuels with 5, 10, 15, 30, and 50 vol % concentrations...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031021.
Paper No: NERS-17-1098
Published Online: May 16, 2018
... Corresponding author. Manuscript received August 28, 2017; final manuscript received January 14, 2018; published online May 16, 2018. Assoc. Editor: Leon Cizelj. 28 08 2017 14 01 2018 Computational fluid dynamics Next generation reactors Thermal hydraulics In the late 1980s...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031015.
Paper No: NERS-17-1262
Published Online: May 16, 2018
... confirmed that the proposed impurity precipitation model can simulate the impurity precipitation phenomenon regardless of the cell size which were tested in this investigation. Computational fluid dynamics Next generation reactors Thermal hydraulics In the Chapman–Enskog analysis, the velocity...
Journal Articles
Journal Articles
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021003.
Paper No: NERS-17-1010
Published Online: March 5, 2018
... the channel at an average temperature of 625 °C. The 25 MPa coolant in the channel is separated from the 0.3 MPa heavy water moderator by a series of liners, ceramic insulator, and zirconium-based pressure tube (Fig. 1 [ 3 ]). Advanced reactors Coupled codes Next generation reactors Nuclear...
Journal Articles
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2018, 4(2): 024501.
Paper No: NERS-17-1105
Published Online: March 5, 2018
.... The results show that the MCNP model is credible and can be used in future safety review of CEFR. Advanced reactors Next generation reactors 03 09 2017 21 12 2017 Copyright © 2018 by ASME 2018 2332-8983/2018/4(2)/024501/4/ $25.00 ...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021006.
Paper No: NERS-17-1123
Published Online: March 5, 2018
.... , and El-Genk , M. S. , 2006 , “ Submersion Criticality Safety of Fast Spectrum Space Reactors: Potential Spectral Shift Absorbers ,” Nucl. Eng. Des. , 236 ( 3 ), pp. 238 – 254 . 10.1016/j.nucengdes.2005.07.005 Advanced reactors Next generation reactors Small Modular Reactors...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020906.
Paper No: NERS-16-1104
Published Online: March 5, 2018
.... If the graphite block in reactor core is damaged by the earthquake, flow channel is blocked by the fragments of graphite blocks. Therefore, the pressure difference of the core was compared with the past data. Next generation reactors Nuclear safety Research reactors Security The high temperature...
Journal Articles
Publisher: ASME
Article Type: Editorial
ASME J of Nuclear Rad Sci. January 2018, 4(1): 010204.
Paper No: NERS-17-1169
Published Online: December 4, 2017
... publications listed below). 20 10 2017 22 10 2017 Advanced reactors Current reactors Next generation reactors Nuclear education Nuclear engineering Research reactors Thermal hydraulics Public acceptance Nuclear knowledge management For his outstanding work, Professor P. L...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011005.
Paper No: NERS-17-1026
Published Online: December 4, 2017
.... 03 04 2017 16 09 2017 Next generation reactors Thermal hydraulics The high performance light water reactor is a supercritical water-cooled reactor (SCWR) concept worked out by a consortium of European partners in 2006–2010. As described by Schulenberg and Starflinger [ 1...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011003.
Paper No: NERS-17-1024
Published Online: December 4, 2017
... Next generation reactors Thermal hydraulics Supercritical fluids (SCFs) have been widely applied in energy and chemical engineering. In the frame of the GEN-IV nuclear energy system development, supercritical water and supercritical CO 2 have been considered as coolant in the nuclear reactor...