Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 641-660 of 913
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Design of Severe Accident Management Systems for Beyond Design Basis External Hazards at Paks Nuclear Power Plant
(The American Society of Mechanical Engineers (ASME), 2018)Paks Nuclear Power Plant (NPP) identified the post-Fukushima actions for mitigation and management of severe accidents caused by external events that include updating of some hazard assessments, evaluation of margins of ... -
Crack Growth and Tolerance of Stainless Steel Canisters in the Marine Environment
(The American Society of Mechanical Engineers (ASME), 2018)Most of the dry storage cask systems that are used to contain nuclear fuel are austenitic stainless steel canisters. Past experience suggests that stainless steel is susceptible to stress corrosion cracking (SCC) in the ... -
Power Management and Distribution System for a Mars Surface Fission Power Reactor
(The American Society of Mechanical Engineers (ASME), 2018)This paper presents a power management and distribution system (PMAD) for a growing Martian colony. The colony is designed for a 15-year operation lifetime, and will accommodate a population that grows from 6 to 126 ... -
Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents
(The American Society of Mechanical Engineers (ASME), 2018)One of the key elements in probabilistic risk assessment is the identification and characterization of uncertainties. This paper suggests a procedure to identify influencing factors for uncertainty in source term evaluation, ... -
The Need for Integrated Cybersecurity and Safety Training
(The American Society of Mechanical Engineers (ASME), 2018)Companies involved in the nuclear energy domain, like component and platform manufacturers, system integrators, and utilities, have well-established yearly trainings on Nuclear Safety Culture. These trainings are typically ... -
Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures
(The American Society of Mechanical Engineers (ASME), 2018) -
Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes
(The American Society of Mechanical Engineers (ASME), 2018)The estimation of fission products (FPs) release from the containment system of a nuclear plant to the external environment during a severe accident (SA) is a quite complex task. In the last 30–40 yr, several efforts were ... -
Setup of the Supercritical CO2 Test Facility “SCARLETT” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System
(The American Society of Mechanical Engineers (ASME), 2018)Supercritical fluids show great potential as future coolants for nuclear reactors, thermal power, and solar power plants. Compared to the subcritical condition, supercritical fluids show advantages in heat transfer due to ... -
Analyses of Long-Term Off-Design Performance Strategy and Operation of a High-Pressure Ratio Intercooled Brayton Helium Gas Turbine Cycle for Generation IV Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2018)The intercooled cycle (IC) is a simplified novel proposal for generation IV nuclear power plants (NPP) based on studies demonstrating efficiencies of over 45%. As an alternative to the simple cycle recuperated (SCR) and ... -
Development of a Seismic Probabilistic Safety Assessment Quantification Tool
(The American Society of Mechanical Engineers (ASME), 2018)Shanghai Nuclear Engineering Research and Design Institute (SNERDI) has been studying seismic risk analysis for nuclear power plant for a long time, and completed seismic margin analysis for several plants. After Fukushima ... -
Particle Deposition by Thermophoresis Under High-Temperature Conditions in a Helium Flow
(The American Society of Mechanical Engineers (ASME), 2018)The continuous generation of graphite dust particles in the core of a high-temperature reactor (HTR) is one of the key challenges of safety during its operation. The graphite dust particles emerge from relative movements ... -
Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant
(The American Society of Mechanical Engineers (ASME), 2018)During a severe accident (SA) in a nuclear power plant (NPP), there are several challenges that need to be faced. To coup with a containment overpressure, the venting action will lower the pressure but it will release ... -
Effect of Soil-Structure Interaction on the Seismic Fragility of a Nuclear Reactor Building
(The American Society of Mechanical Engineers (ASME), 2018)Recently, the nuclear industry has made a tremendous effort to assess the safety of nuclear power plants (NPP), as advances in seismology have led to the perception that the potential earthquake hazard in the U.S. may be ... -
Power Cycle Assessment of Nuclear Systems, Providing Energy Storage for Low Carbon Grids
(The American Society of Mechanical Engineers (ASME), 2018)The intermittency of renewable power generation systems on the low carbon electric grid can be alleviated by using nuclear systems as quasi-storage systems. Nuclear air-Brayton systems can produce and store hydrogen when ... -
The Study of Nanosized Cu–Mn Precipitates Contribution to Hardening in Body Centered Cubic Fe Matrix
(The American Society of Mechanical Engineers (ASME), 2018)In order to study the contribution of manganese (Mn) atoms in copper (Cu) precipitates to hardening in body centered cubic (BCC) structure iron (Fe) matrix, the interactions of a 1/2 〈111〉 {110} edge dislocations with ... -
Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-Neutral Beam Injection
(The American Society of Mechanical Engineers (ASME), 2018)During the process of beam extraction in positive ion source under high voltage region, a large number of electrons are produced in the gaps of grids. After back-streaming acceleration, these electrons go back to arc chamber ... -
Burnable Poison Design for Supercritical Water Cooled Reactor With Annular Fuel
(The American Society of Mechanical Engineers (ASME), 2018)Burnable poison (BP) is used to control excess reactivity in supercritical water cooled reactor (SCWR). It helps reduce the number of control rods. Over all BP designs, the design in which rare-earth oxide mixes with fuel ... -
Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant
(The American Society of Mechanical Engineers (ASME), 2018)In this paper, a new technique to handle solid radioactive materials inside a liquid matrix is presented. The conceptual design of the device profits of the experience and know-how gained in decontamination procedures. The ... -
Insight From Recent Experimental and Empirical-Model Studies on Flow-Regime Characteristics in Debris Bed Formation Behavior
(The American Society of Mechanical Engineers (ASME), 2018)Studies on debris bed formation behavior are important for improved evaluation of core relocation and debris bed coolability that might be encountered in a core disruptive accident (CDA) of sodium-cooled fast reactors ... -
Research Challenges of Heat Transfer to Supercritical Fluids
(The American Society of Mechanical Engineers (ASME), 2018)Supercritical fluids (SCFs) become more and more important in various engineering applications. In nuclear power systems, SCFs are considered as coolant of the reactor core such as the supercritical water-cooled reactor ...