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Issues
October 2016
ISSN 2332-8983
EISSN 2332-8975
In this Issue
Guest Editorial
Guest Editorial:Special Issue: ICONE-23
ASME J of Nuclear Rad Sci. October 2016, 2(4): 040201.
doi: https://doi.org/10.1115/1.4034177
Topics:
Nuclear engineering
Research Papers
Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR
Yoshitomo Inaba, Kenji Sekita, Takahiro Nemoto, Yuki Honda, Daisuke Tochio, Hiroyuki Sato, Shigeaki Nakagawa, Shoji Takada, Kazuhiro Sawa
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041001.
doi: https://doi.org/10.1115/1.4034320
Topics:
Coolants
,
Heat
,
Heating
,
Pressure
,
Temperature
,
Graphite
,
Helium
,
Heat transfer
,
Stress
On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041002.
doi: https://doi.org/10.1115/1.4033697
Topics:
Instrumentation
,
Neutron flux
,
Neutrons
,
Sensors
Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041003.
doi: https://doi.org/10.1115/1.4033696
Topics:
Algorithms
,
Boilers
,
Dynamics (Mechanics)
,
Pressure
,
Sensors
,
Temperature
,
Transients (Dynamics)
,
Water
,
Flow (Dynamics)
,
Transmission lines
Computational Fluid Dynamics Simulation of Direct-Contact Condensation Phenomenon of Vapor Jet in Subcooled Water Tank
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041004.
doi: https://doi.org/10.1115/1.4033280
Topics:
Computational fluid dynamics
,
Condensation
,
Mass transfer
,
Simulation
,
Subcooling
,
Temperature
,
Vapors
,
Water
,
Flow (Dynamics)
,
Pressure
Phenomenological Analysis of Melt Progression in LWRS: Proposal of an In-Vessel Corium Progression Scenario in the Unit 1 of Fukushima Dai-ichi Nuclear Power Plant
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041005.
doi: https://doi.org/10.1115/1.4033397
Topics:
Failure
,
Fukushima nuclear disaster, Japan, 2011
,
Heat flux
,
Jet pumps
,
Nuclear power stations
,
Seas
,
Vessels
,
Water
,
Light water reactors
,
Melting
Design and Performance Evaluation of a Heat Exchanger Network for a Cogeneration DMS to Various Thermal Utilization Applications
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041006.
doi: https://doi.org/10.1115/1.4033770
Topics:
Combined heat and power
,
Design
,
Heat exchangers
,
Exergy
,
Heat
,
Flow (Dynamics)
,
Temperature
,
Water
,
Fluids
Numerical Simulation of Sealing Behavior of C-Ring for Reactor Pressure Vessel
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041007.
doi: https://doi.org/10.1115/1.4033551
Topics:
Compression
,
Computer simulation
,
Sealing (Process)
,
Deformation
,
Springs
,
Stress
,
Reactor vessels
Development of the Prediction Technology of Cable Disconnection of In-Core Neutron Detector for the Future High-Temperature Gas-Cooled Reactors
Yosuke Shimazaki, Hiroaki Sawahata, Taiki Kawamoto, Hisashi Suzuki, Masanori Shinohara, Yuki Honda, Kozo Katsuyama, Shoji Takada, Kazuhiro Sawa
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041008.
doi: https://doi.org/10.1115/1.4032597
Topics:
Cables
,
Neutrons
,
Sensors
,
Very high temperature reactors
,
Maintenance
Low-Power and Shut-Down Condition Medium-Break Loss-of-Coolant Accident Success Criterion Analysis for a Typical Three-Loop Nuclear Power Plant
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041009.
doi: https://doi.org/10.1115/1.4033669
Topics:
Accidents
,
Coolants
,
Damage
,
Nuclear power stations
,
Safety
,
Temperature
,
Simulation
,
Pressure
,
Water
,
Secondary cells
Guidance and Methodologies for Managing Digital Instrumentation and Control Obsolescence
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041010.
doi: https://doi.org/10.1115/1.4034287
Topics:
Cycles
,
Maintenance
,
Instrumentation
,
Computer software
,
Safety
Diagnostics and Life-Cycle Assessment of Medium-Voltage Cables in Nuclear Power Plants During Regular Overhaul Process
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041011.
doi: https://doi.org/10.1115/1.4032782
Topics:
Cables
,
Insulation
,
Testing
Technical Brief
“Making It Work”: The Vital Role of Commissioning in Nuclear Power Programs
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044501.
doi: https://doi.org/10.1115/1.4033729
Topics:
Design
,
Nuclear power
,
Nuclear power stations
,
Safety
,
Testing
Investigation of Countermeasure Against Local Temperature Rise in Vessel Cooling System in Loss of Core Cooling Test Without Nuclear Heating
Masato Ono, Atsushi Shimizu, Makoto Kondo, Yosuke Shimazaki, Masanori Shinohara, Daisuke Tochio, Kazuhiko Iigaki, Shigeaki Nakagawa, Shoji Takada, Kazuhiro Sawa
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044502.
doi: https://doi.org/10.1115/1.4032478
Topics:
Cooling
,
Heating
,
Temperature
,
Water
,
Cooling systems
,
Vessels
,
Flow (Dynamics)
,
Heat
Coordination of I&C Design With the Obligatory Consideration of Human Factors: A Project Management Approach
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044503.
doi: https://doi.org/10.1115/1.4033550
Topics:
Design
,
Project management
,
Human factors
,
Control rooms
CAE—The Spanish Emergency Support Center: A Centralized and Shared Emergency Support Service for Beyond Design Basis Events
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044504.
doi: https://doi.org/10.1115/1.4032641
Topics:
Computer-aided engineering
,
Emergencies
,
Nuclear power stations
,
Design
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044505.
doi: https://doi.org/10.1115/1.4034144
Design of a Tritium-In-Air Monitor Using Field-Programmable Gate Arrays
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044506.
doi: https://doi.org/10.1115/1.4033088
Topics:
Design
,
Gates (Closures)
,
Instrumentation
,
Testing
,
Carbon
,
Water
,
Radiation detectors
,
Engineering prototypes
,
Radiation (Physics)
,
Sensors
Research of Nuclear Power Plant In-Service Maintenance Based on Virtual Reality
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044507.
doi: https://doi.org/10.1115/1.4032598
Topics:
Maintenance
,
Nuclear power stations
,
Simulation
,
Virtual reality
,
Construction
,
Ergonomics
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