Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 701-720 of 913
-
60 Years in Motion: Short History of Nuclear Engineering Division
(The American Society of Mechanical Engineers (ASME), 2017)This paper presents a brief history of the ASME nuclear engineering division (NED) over the past 60 years. The technical interest of the Division naturally mirrored the main stages in nuclear-technology development and ... -
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
(The American Society of Mechanical Engineers (ASME), 2016) -
Guidance and Methodologies for Managing Digital Instrumentation and Control Obsolescence
(The American Society of Mechanical Engineers (ASME), 2016) -
Design and Performance Evaluation of a Heat Exchanger Network for a Cogeneration DMS to Various Thermal Utilization Applications
(The American Society of Mechanical Engineers (ASME), 2016)Hitachi-GE developed a 300-MWe-class modular simplified and medium small reactor (DMS) between 2000 and 2004. It was designed to have merits over traditional nuclear power plants in areas of lower initial capital investment, ... -
Investigation of Countermeasure Against Local Temperature Rise in Vessel Cooling System in Loss of Core Cooling Test Without Nuclear Heating
(The American Society of Mechanical Engineers (ASME), 2016)In the loss of core cooling test using High Temperature engineering Test Reactor (HTTR), the forced cooling of the reactor core is stopped without inserting control rods into the core and, furthermore, without cooling by ... -
Diagnostics and Life-Cycle Assessment of Medium-Voltage Cables in Nuclear Power Plants During Regular Overhaul Process
(The American Society of Mechanical Engineers (ASME), 2016)The reliability of operation of a nuclear power plant substantially depends on the reliability of its individual components. Electric cables, particularly medium-voltage cables, represent an important constituent of the ... -
Numerical Simulation of Sealing Behavior of C-Ring for Reactor Pressure Vessel
(The American Society of Mechanical Engineers (ASME), 2016) -
Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique
(The American Society of Mechanical Engineers (ASME), 2016)We present here some theoretical and experimental results about the application of the time-domain reflectometry (TDR) technique to a once-through steam generator (OTSG) bayonet-type, which is considered here, from a new ... -
Coordination of I&C Design With the Obligatory Consideration of Human Factors: A Project Management Approach
(The American Society of Mechanical Engineers (ASME), 2016)Human factors engineering (HFE), such as other engineering disciplines involved in plant design, cannot be considered retroactively. The engineering principles and methods derived from deep knowledge of the cognitive and ... -
“Making It Work”: The Vital Role of Commissioning in Nuclear Power Programs
(The American Society of Mechanical Engineers (ASME), 2016)This paper presents an overview of the duties of a nuclear power plant (NPP) commissioning organization and its special relationship with both the early stages of an NPP project and the long-term operation of such power ... -
Computational Fluid Dynamics Simulation of Direct-Contact Condensation Phenomenon of Vapor Jet in Subcooled Water Tank
(The American Society of Mechanical Engineers (ASME), 2016) -
Development of the Prediction Technology of Cable Disconnection of In-Core Neutron Detector for the Future High-Temperature Gas-Cooled Reactors
(The American Society of Mechanical Engineers (ASME), 2016)Maintenance technologies for the reactor system have been developed by using the High Temperature engineering Test Reactor (HTTR). One of the important purposes of development is to accumulate the experiences and data to ... -
Low-Power and Shut-Down Condition Medium-Break Loss-of-Coolant Accident Success Criterion Analysis for a Typical Three-Loop Nuclear Power Plant
(The American Society of Mechanical Engineers (ASME), 2016) -
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
(The American Society of Mechanical Engineers (ASME), 2016)In the field of severe accident, the description of corium progression events is mainly carried out using integral calculation codes. However, these tools are usually based on bounding assumptions because of the high ... -
CAE—The Spanish Emergency Support Center: A Centralized and Shared Emergency Support Service for Beyond Design Basis Events
(The American Society of Mechanical Engineers (ASME), 2016) -
Regulatory Framework for the Decommissioning of Indonesian Nuclear Facilities
(The American Society of Mechanical Engineers (ASME), 2017)The decommissioning of nuclear facilities in Indonesia are mainly based on Nuclear Energy Act of 1997 on, Nuclear Energy Regulatory Agency (BAPETEN) Chairman Regulation (BCR) No. 4 of 2009, and Government Regulation (GR) ... -
Computational Fluid Dynamics Simulation of Deflagration-to-Detonation Transition in a Full-Scale Konvoi-Type Pressurized Water Reactor
(The American Society of Mechanical Engineers (ASME), 2017)For the purpose of nuclear safety analysis, a reactive flow solver has been developed to determine the hazardous potential of large-scale hydrogen explosions. Without using empirical transition criteria, the whole combustion ... -
Global Neutron Calculations, by M. Makai, D. P. Kis, and J. Vegh. Bentham Science Publishers Ltd., UAE, 2015, 552 pp., eISBN 978-1-68108-027-7, ISBN978-1-68108-028-4.
(The American Society of Mechanical Engineers (ASME), 2016) -
The Effect of Intrinsic Instabilities on Effective Flame Speeds in Under-Resolved Simulations of Lean Hydrogen–Air Flames
(The American Society of Mechanical Engineers (ASME), 2017)The presented work aims to improve computational fluid dynamics (CFD) explosion modeling for lean hydrogen–air mixtures on under-resolved grids. Validation data are obtained from an entirely closed laboratory-scale explosion ... -
Analyses of the Control System Strategies and Methodology for Part Power Control of the Simple and Intercooled Recuperated Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2017)An important requirement for Generation IV Nuclear Power Plant (NPP) design is the control system, which enables part power operability. The choices of control system methods must ensure variation of load without severe ...