Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 661-680 of 913
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Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction
(The American Society of Mechanical Engineers (ASME), 2018)Critical heat flux (CHF) experiment with uniform heating was performed in a tube of 8.2 mm in inner diameter and 2.4 m in heated length. The water flowed upward through the test section. The pressure covered the range from ... -
Transmutation Study of Minor Actinides in Mixed Oxide Fueled Typical Pressurized Water Reactor Assembly
(The American Society of Mechanical Engineers (ASME), 2018)The management of long-lived radionuclides in spent fuel is a key issue to achieve the closed nuclear fuel cycle and the sustainable development of nuclear energy. The partitioning-transmutation method is supposed to ... -
Research Works on Iodine and Ruthenium Behavior in Severe Accident Conditions
(The American Society of Mechanical Engineers (ASME), 2018) -
Corrosion Behaviour of Bare and NiCrAlY Coated Alloy 214 in Supercritical Water at 700 °C
(The American Society of Mechanical Engineers (ASME), 2018)Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have resulted in renewed interest in nuclear energy as an essential part of the energy mix for the future. Many countries ... -
Fukushima Unit 2 Accident Simulation With MELCOR 2.1
(The American Society of Mechanical Engineers (ASME), 2018)A VTT Fukushima Daiichi Unit 3 (1F3) method for estimation of liquids and consequences of releases (MELCOR) model was modified to simulate the Fukushima Daiichi Unit 2 (1F2) accident. Five simulations were performed using ... -
Planning the Selection and Assignment of Security Forensics Countermeasures
(The American Society of Mechanical Engineers (ASME), 2018)Cybersecurity incidents are stressful, complex in nature, and are frequently not systematically considered in daily tasks. When correctly managed, operational readiness procedures ensure the availability of data required ... -
Neutronic Study of Burnable Poison Materials and Their Alternative Configurations in Fully Ceramic Microencapsulated Loaded Pressurized Water Reactor Fuel Assembly
(The American Society of Mechanical Engineers (ASME), 2018)Use of FCM fuel in light water reactors is an attractive option for existing and future generations of these reactors to make them accident tolerant in nature. This work focuses on the neutronic study of the use of burnable ... -
Special Section: Selected and Revised Papers From ICONE-24
(The American Society of Mechanical Engineers (ASME), 2018)pecial Section in this issue of the ASME Journal of Nuclear Engineering and Radiation Science is dedicated to selected papers from the 24th International Conference on Nuclear Engineering (ICONE-24) held in Charlotte, NC ... -
Large Eddy Simulation Study on Forced Convection Heat Transfer to Water at Supercritical Pressure in a Trapezoid Annulus
(The American Society of Mechanical Engineers (ASME), 2018)It is now well known that heat transfer to fluid at supercritical pressure in a confined channel shows complex behaviors. This is due to the strong variations of the thermal–physical properties resulting from the changes ... -
Intelligent Identification of Boiling Water Reactor State Utilizing Relevance Vector Regression Models
(The American Society of Mechanical Engineers (ASME), 2018)Modernization of reactor instrumentation and control systems is mainly characterized by the transition from analog to digital systems, expressed by replacement of hardware equipment with new software-driven devices. Digital ... -
Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions
(The American Society of Mechanical Engineers (ASME), 2018)A new experimental program using nontransfer (NTR) type plasma heating is under consideration in Japan Atomic Energy Agency (JAEA) to clarify the uncertainty on core-material relocation (CMR) behavior of boiling water ... -
Dose Rates From the Accidental Withdrawal of a Fuel Element From an Open Pool-Type Reactor
(The American Society of Mechanical Engineers (ASME), 2018)This paper studies the radiological consequences resulting from withdrawal of nuclear fuel element (FE) from a core of open pool type reactor during normal operation. The FE withdrawal accident may be occurred due to human ... -
Backbone: A Multiphysics Framework for Coupling Nuclear Codes Based on CORBA and MPI
(The American Society of Mechanical Engineers (ASME), 2017)Recent trends in nuclear reactor performance and safety analyses increasingly rely on multiscale multiphysics computer simulations to enhance predictive capabilities by replacing conventional methods that are largely ... -
Analyses of a High Pressure Ratio Intercooled Direct Brayton Helium Gas Turbine Cycle for Generation IV Reactor Power Plants
(The American Society of Mechanical Engineers (ASME), 2017)The intercooled cycle (IC) as an alternative to the simple cycle recuperated (SCR) and intercooled cycle recuperated (ICR) is yet to be fully analyzed for the purpose of assessing its viability for utilization within ... -
Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis
(The American Society of Mechanical Engineers (ASME), 2017)This article conducts optimization and sensitivity analysis for the cold-end system of a nuclear power plant (NPP) with a sea water circulating system, using the minimum annual cost method by dynamic economical analysis. ... -
Validation of the Onsite Used Operational Code Against Burnup Measurement
(The American Society of Mechanical Engineers (ASME), 2017)A spectrometric system was developed for spent fuel burnup evaluations at the LVR-15 research reactor, which employed highly enriched (36%) IRT-2M-type fuel. Such a system allows the measurement of fission product axial ... -
Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code
(The American Society of Mechanical Engineers (ASME), 2017)The key objective of the test blanket module (TBM) program is to develop the design technology for DEMO and future power-producing fusion reactors. The proposed first wall of the test blanket system (TBS) is a generalized ... -
A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor
(The American Society of Mechanical Engineers (ASME), 2017)This work focuses on the safety analysis of a typical pressurized water reactor (PWR) for reactivity-initiated transients. These transients result from withdrawal of six sets of groups of control rods that may occur under ... -
Monitoring Pump Parameters in Small Modular Reactors Using Electric Motor Signatures1
(The American Society of Mechanical Engineers (ASME), 2017)Small modular nuclear reactors (SMRs) are designed for long-term operation with minimum outages and for possible deployment in remote locations. To achieve this operational goal, the SMRs may require remote and continuous ... -
Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel
(The American Society of Mechanical Engineers (ASME), 2017)The supercritical water reactor (SCWR) is one of the Generation IV designs. The SCWR is characterized by its high efficiency, low waste production, and simple design. Despite the suitable properties of supercritical water ...