1-20 of 161
Design
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Journal Articles

Special Experimental Environment for Gen. IV Reactors with Graphite Reflector

Accepted Manuscript
Eva Vilimová, Tomáš Peltan, Radek Škoda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1017
https://doi.org/10.1115/1.4064124
Published Online: November 23, 2023
View Article titled, Special Experimental Environment for Gen. IV Reactors with Graphite Reflector
Open the PDF for Special Experimental Environment for Gen. IV Reactors with Graphite Reflector in another window
Topics: Graphite, Neutrons, Nuclear reactors, Design, Instrumentation, Neutron flux, Optical mirrors, Small modular reactors
Journal Articles

Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor

Huiping V. Yan, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021502.
Paper No: NERS-23-1010
https://doi.org/10.1115/1.4063388
Published Online: November 1, 2023
View Article titled, Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor
Open the PDF for Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor in another window
Topics: Coolants, Fuels, Temperature, Hydrogen, Graphite, Design, Rods, Physics
Journal Articles

Application of Level 3 Probabilistic Safety Analysis In UK HPR1000

Accepted Manuscript
Jinkai Wang, Qi Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1112
https://doi.org/10.1115/1.4063874
Published Online: October 21, 2023
View Article titled, Application of Level 3 Probabilistic Safety Analysis In UK HPR1000
Open the PDF for Application of Level 3 Probabilistic Safety Analysis In UK HPR1000 in another window
Topics: Probabilistic safety assessment, Accidents, Design, Nuclear power stations, Radiation (Physics), Radiation sources, Risk
Journal Articles

Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5

Andrej Prošek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011401.
Paper No: NERS-23-1032
https://doi.org/10.1115/1.4063009
Published Online: October 20, 2023
View Article titled, Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5
Open the PDF for Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5 in another window
Topics: Design, Feedwater, Pressurized water reactors, Pumps, Safety, Accidents, Nuclear reactor coolants
Journal Articles

Technical Evaluation Requirements on Welding-Related Nonconformance Reports

Chongzhi Wu, Mingkai Li, Zongkui Wang, Zhenguo Peng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 022101.
Paper No: NERS-23-1035
https://doi.org/10.1115/1.4063630
Published Online: October 20, 2023
View Article titled, Technical Evaluation Requirements on Welding-Related Nonconformance Reports
Open the PDF for Technical Evaluation Requirements on Welding-Related Nonconformance Reports in another window
Topics: Welding, Construction, Design
Journal Articles

Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

Accepted Manuscript
Thanh Mai Vu, Thi Hong Bui, Le Quang Linh Tran
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1046
https://doi.org/10.1115/1.4063739
Published Online: October 13, 2023
View Article titled, Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor
Open the PDF for Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor in another window
Topics: Boron, Fast neutron reactors, Rods, Absorption, Fuels, Neutrons, Safety, Control systems, Coolants, Design
Journal Articles

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Shujun Wang, Xianmin Huang, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-23-1011
https://doi.org/10.1115/1.4062500
Published Online: September 15, 2023
View Article titled, System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept
Open the PDF for System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept in another window
Topics: Coolants, Cycles, Design, Flow (Dynamics), Fuels, High temperature, Modeling, Temperature, Thermal hydraulics, Steady state
Journal Articles

Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production

Lekhnath Ghimire, Edward Waller
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2023, 9(4): 044501.
Paper No: NERS-23-1006
https://doi.org/10.1115/1.4062644
Published Online: September 15, 2023
View Article titled, Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production
Open the PDF for Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production in another window
Topics: Design, Safety, Small modular reactors, Fuels
Journal Articles

“Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”

Accepted Manuscript
Shu Jun Wang, Xianmin Huang, Yanfei Rao, Blair Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1086
https://doi.org/10.1115/1.4063240
Published Online: August 24, 2023
View Article titled, “Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”
Open the PDF for “Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)” in another window
Topics: Pressurized water reactors, Small modular reactors, Testing, Thermal hydraulics, Flow (Dynamics), Oscillations, Boilers, Design, Circuits, Heat transfer
Journal Articles

A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041107.
Paper No: NERS-22-1162
https://doi.org/10.1115/1.4062879
Published Online: July 17, 2023
View Article titled, A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors
Open the PDF for A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors in another window
Topics: Molten salt reactors, Simulation, Wall thickness, Safety, Computer simulation, Design, Temperature, Heat conduction, Melting, Solidification
Journal Articles

Interactions Between Molten Sodium and Standard Pipe Insulation

Accepted Manuscript
Daniel LaBrier, Jordan Harley, Morgan Robbins
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1191
https://doi.org/10.1115/1.4062798
Published Online: June 20, 2023
View Article titled, Interactions Between Molten Sodium and Standard Pipe Insulation
Open the PDF for Interactions Between Molten Sodium and Standard Pipe Insulation in another window
Topics: Pipe insulation, Sodium, Insulation, Leakage, Pipes, Heat, Binders (Materials), Design, Fire, Glass fiber insulation
Journal Articles

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041103.
Paper No: NERS-22-1137
https://doi.org/10.1115/1.4056772
Published Online: May 31, 2023
View Article titled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
Open the PDF for Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code in another window
Topics: Coolants, Design, Diluents, Fuels, Leakage, Neutrons, Supercritical carbon dioxide, Nuclear fission, Nuclides, Feedback
Journal Articles

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
Paper No: NERS-22-1145
https://doi.org/10.1115/1.4062119
Published Online: April 17, 2023
View Article titled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
Open the PDF for Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel in another window
Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
Journal Articles

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.
Paper No: NERS-22-1020
https://doi.org/10.1115/1.4056239
Published Online: February 8, 2023
View Article titled, Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres
Open the PDF for Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres in another window
Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection
Journal Articles

Novel Eddy Current Array Sensor Delivery Tool for Automated Nondestructive Examination of Spent Fuel Pool Liner

Michael Smith, Emily Abbate, Joey Phillips, Byungsik Yoon
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021701.
Paper No: NERS-21-1165
https://doi.org/10.1115/1.4055065
Published Online: September 2, 2022
View Article titled, Novel Eddy Current Array Sensor Delivery Tool for Automated Nondestructive Examination of Spent Fuel Pool Liner
Open the PDF for Novel Eddy Current Array Sensor Delivery Tool for Automated Nondestructive Examination of Spent Fuel Pool Liner in another window
Topics: Design, Eddies (Fluid dynamics), Eddy currents (Electricity), Inspection, Motors, Nondestructive evaluation, Sensors, Spent nuclear fuels, Rails, Railroad passenger cars
Journal Articles

Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant

Jindong Zhang, Chongzhi Wu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011801.
Paper No: NERS-22-1014
https://doi.org/10.1115/1.4054878
Published Online: July 19, 2022
View Article titled, Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant
Open the PDF for Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant in another window
Topics: Construction, Design, Evaluation methods, Nuclear power stations, Failure mechanisms, Nuclear power
Journal Articles

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
Paper No: NERS-21-1135
https://doi.org/10.1115/1.4053827
Published Online: June 15, 2022
View Article titled, Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
Open the PDF for Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention in another window
Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors
Journal Articles

ARKADIA—For the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Akihiro Uchibori, Takashi Takata, Akiyuki Seki, Yasuhiro Enuma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Design Innovation Paper
ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.
Paper No: NERS-21-1157
https://doi.org/10.1115/1.4054726
Published Online: June 15, 2022
View Article titled, ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
Open the PDF for ARKADIA—For the Innovation of Advanced Nuclear Reactor Design in another window
Topics: Design, Optimization, Safety, Thermal hydraulics, Nuclear design, Nuclear reactors, Computer simulation
Journal Articles

Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant

Chongzhi Wu, Haoming Sun, Zhenguo Peng, Benzheng Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Expert View
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014701.
Paper No: NERS-21-1177
https://doi.org/10.1115/1.4054169
Published Online: June 7, 2022
View Article titled, Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant
Open the PDF for Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant in another window
Topics: Design, Nondestructive evaluation, Nuclear power stations, Safety
Journal Articles

Suggestion on Improving Small Branch BOSS Joints Welding Quality

Chongzhi Wu, Ruifeng Zhu, Pengteng Yu, Haoming Sun, Qingli Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Discussions
ASME J of Nuclear Rad Sci. July 2022, 8(3): 035501.
Paper No: NERS-21-1095
https://doi.org/10.1115/1.4053690
Published Online: May 26, 2022
View Article titled, Suggestion on Improving Small Branch BOSS Joints Welding Quality
Open the PDF for Suggestion on Improving Small Branch BOSS Joints Welding Quality in another window
Topics: Design, Nondestructive evaluation, Welding