Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 761-780 of 913
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Evaluation of Hydrogel Technologies for the Decontamination of 137Cs From Building Material Surfaces
(The American Society of Mechanical Engineers (ASME), 2017)One of the preparation steps for a possible radiological attack is the capability of fast and effective decontamination of critical infrastructure. This study describes the implementation of a test plan at an intermediate ... -
Fission Track Detection Using Automated Microscopy
(The American Society of Mechanical Engineers (ASME), 2017)Detection of microscopic fission track (FT) star-shaped clusters, developed in a solid state nuclear track detector (SSNTD) by etching, created by fission fragments emitted from particles of fissile materials irradiated ... -
Optimization of a Multiline Neutron Source Based on a 232Th Filter
(The American Society of Mechanical Engineers (ASME), 2017)A multiline neutron source can be produced by using a metallic 232Th filter in conjunction with a white neutron source. The multiline spectrum consists of ∼20 relatively strong intensity lines ranging from 10 to 4000 eV. ... -
Ni Interlayer to Improve Low-Pressure Diffusion Bonding of 316L SS Press Fit Tube-to-Tubesheet Joints for Coiled Tube Gas Heaters
(The American Society of Mechanical Engineers (ASME), 2017)This study suggests a new approach to diffusion bonding (DB) 316L stainless steel: a low-pressure procedure that includes a nickel interlayer. In this approach, relatively lower pressure is applied to the sample before the ... -
Detection of Combined n/γ Fission Signatures Induced by an Epithermal Neutron Source
(The American Society of Mechanical Engineers (ASME), 2017)In this paper, a method is presented for the detection of special nuclear materials (SNMs) in shielded containers, which is both sensitive and applicable under field conditions. The method uses an external pulsed neutron ... -
A Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection
(The American Society of Mechanical Engineers (ASME), 2017)A pipe-wall thinning measurement is a key inspection to ensure the integrity of the piping system in nuclear power plants. To monitor the integrity of the piping system, a number of ultrasonic thickness measurements are ... -
Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention
(The American Society of Mechanical Engineers (ASME), 2017)This paper presents the results of experimental investigations into two-phase mass transport in a coarse packed bed representing the Canada Deuterium Uranium (CANDU) end shield. This work contributes to understanding of ... -
Development of SNTA Code System for SCWR Core Steady-State Analysis
(The American Society of Mechanical Engineers (ASME), 2017)A coupled neutronics/thermal-hydraulics (N/T) three-dimensional code system SNTA is developed for supercritical water-cooled reactor (SCWR) core steady-state analysis by modular coupling the improved neutronics nodal ... -
Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System
(The American Society of Mechanical Engineers (ASME), 2017)The accelerator-driven subcritical reactor system (ADS) is a kind of nuclear reactor which can burn minor actinide waste products produced from conventional reactors with inherent safety features. In this paper, the ... -
A Review of the Turbine Cooling Fraction for Very High Turbine Entry Temperature Helium Gas Turbine Cycles for Generation IV Reactor Power Plants
(The American Society of Mechanical Engineers (ASME), 2017)The potential for high turbine entry temperature (TETs) turbines for nuclear power plants (NPPs) requires improved materials and sophisticated cooling. Cooling is critical for maintaining mechanical integrity of the turbine ... -
Special Section: Selected Papers from the 28th Conference of the Nuclear Societies in Israel
(The American Society of Mechanical Engineers (ASME), 2017) -
Current Severe Accident Research and Development Topics for Wolsong PHWR Safety in Korea
(The American Society of Mechanical Engineers (ASME), 2017)In Korea, pressurized heavy water-cooled reactors (PHWR) account for 17% of operating units and have taken an important role in providing national energy supply. The recent biggest issue in domestic PHWR community was the ... -
Handbook of Generation-IV Nuclear Reactors
(The American Society of Mechanical Engineers (ASME), 2017) -
Validation of Constant Load C-Ring Apex Stresses for Stress Corrosion Cracking Testing in Supercritical Water
(The American Society of Mechanical Engineers (ASME), 2017)In selecting the materials for the Canadian supercritical water-cooled reactor (SCWR), the effects and extent of stress corrosion cracking (SCC) on candidate alloys of construction, under various operational conditions, ... -
Adhesion of Oxides Grown in Supercritical Water on Selected Austenitic and Ferritic/Martensitic Alloys
(The American Society of Mechanical Engineers (ASME), 2017)A series of austenitic alloys (800H, H214, I625, 310S, and 347) with different surface finishes were exposed to supercritical water (SCW) at 550 °C and 2.5 × 107 Pa for 120 h, 260 h, and 450 h in a static autoclave with ... -
In-Calandria Retention of Corium in PHWR: Experimental Investigation and Remaining Issues
(The American Society of Mechanical Engineers (ASME), 2017)After the Fukushima accident, the public has expressed concern regarding the safety of nuclear power plants. This accident has strengthened the necessity for further improvement of safety in the design of existing and ... -
Effects of Filtered Containment Venting on Fission Product Releases During CANDU Reactor Severe Accidents
(The American Society of Mechanical Engineers (ASME), 2017)Severe accidents are of increasing concern in the nuclear industry worldwide since the accidents at Fukushima Daiichi (March 2011). These events have significant consequences that must be mitigated to ensure public and ... -
Analysis of Late Phase Severe Accident Phenomena in CANDU Plant
(The American Society of Mechanical Engineers (ASME), 2017)The paper overviews the analytical studies performed at Politehnica University of Bucharest on the analysis of late phase severe accident phenomena in a Canada Deuterium Uranium (CANDU) plant. The calculations start from ... -
Experimental Study of Aqueous Chemical Trisodium Phosphate-Buffered Environment Under Post-LOCA Conditions With Head Loss Measurements
(The American Society of Mechanical Engineers (ASME), 2017)An integrated chemical effects test (ICET) was designed and executed to investigate the corrosion of materials in a hypothetical post-loss of coolant accident (LOCA) environment for pressurized water reactors (PWRs) and ... -
Progression of Severe Accidents, Containment Performance, and Estimates of Releases of Radionuclides-Level-2 Probabilistic Safety Assessment IPHWR
(The American Society of Mechanical Engineers (ASME), 2017)Probabilistic safety assessment (PSA) of nuclear power plants is performed to yield insights into the safety, design, and performance of the plants and their potential environmental effects. This includes the identification ...