Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 601-620 of 913
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Functional Information of System Components Influenced by Counteractions on Computer-Based Procedure
(The American Society of Mechanical Engineers (ASME), 2018)In an emergency condition of nuclear power plant, operators have to mitigate the accident in order to remove the decay heat and to prevent the release of radioactive material to the environment following the emergency ... -
Application of Monte Carlo Simulation to Design of Sampler and Detector in Radiation Monitoring System
(The American Society of Mechanical Engineers (ASME), 2018)In this study, the applicability of Monte Carlo code particle and heavy ion transport code system (PHITS) [Sato et al. (2013, “Particle and Heavy Ion Transport Code System PHITS, Version 2.52,” J. Nucl. Sci. Technol., ... -
Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water
(The American Society of Mechanical Engineers (ASME), 2018)The authors look for an attractive light water reactor (LWR) concept, which achieves high breeding performance with respect to the compound system doubling time (CSDT). In the preceding study, a high breeding fast reactor ... -
Special Issue: Special Edition ICONE-25
(The American Society of Mechanical Engineers (ASME), 2018) -
Numerical Investigations of the Effect of Radial Power Distribution and Inlet Orifice on the Stability Behavior of Parallel Multichannel Type Natural Circulation Boiling Water Reactor
(The American Society of Mechanical Engineers (ASME), 2018)In a natural circulation boiling water reactor (BWR), the core power varies in both axial and radial directions inside the reactor core. The variation along the axial direction is more or less constant throughout the ... -
Causes and Radiological Consequences of the Chernobyl and Fukushima Nuclear Accidents
(The American Society of Mechanical Engineers (ASME), 2018)In this paper, the causes and the radiological consequences of the explosion of the Chernobyl reactor occurred at 1:23 a.m. (local time) on Apr. 26, 1986, and of the Fukushima Daiichi nuclear disaster following the huge ... -
Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure
(The American Society of Mechanical Engineers (ASME), 2018)While supercritical water is a perfect coolant with excellent heat transfer, a temporary decrease of the system pressure to subcritical conditions, either during intended transients or by accident, can easily cause a boiling ... -
Special Issue: Selected Papers from the 8th International Symposium on Supercritical Water-Cooled Reactors
(The American Society of Mechanical Engineers (ASME), 2018)pecial issue of the ASME Journal of Nuclear Engineering and Radiation Science comprises selected papers from the eighth International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-8), held from Mar. 13 to 15, ... -
Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code
(The American Society of Mechanical Engineers (ASME), 2018)This work attempts to investigate the thermal hydraulic safety of lithium lead ceramic breeder (LLCB) test blanket system (TBS) in International Thermonuclear Experimental Reactor (ITER) with the help of modified thermal ... -
Microstructure Study of NiCrAlY and FeCrAlY Exposed to Superheated Steam at 800 °C
(The American Society of Mechanical Engineers (ASME), 2018)Supercritical water-cooled reactor (SCWR) was chosen as Generation IV reactor concept in Canada to utilize Canada's expertise and technical capabilities from past research and designs. The conceptual design of Canadian ... -
Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations
(The American Society of Mechanical Engineers (ASME), 2018)The Canadian supercritical water-cooled reactor (SCWR) design is part of Canada's Generation IV reactor development program. The reactor uses batch fueling, light water above the thermodynamic critical point as a coolant ... -
The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations1
(The American Society of Mechanical Engineers (ASME), 2018) -
Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U3O8-Al, U3Si2-Al, and UN-Al
(The American Society of Mechanical Engineers (ASME), 2018)The understanding of the radial distribution of temperature in a fuel pellet, under normal operation and accident conditions, is important for a safe operation of a nuclear reactor. Therefore, in this study, we have solved ... -
Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration
(The American Society of Mechanical Engineers (ASME), 2018)The present experimental investigation in a scaled facility of an Indian pressurized heavy water reactors (PHWRs) is focused on the heat transfer behavior from the calandria vessel (CV) to the calandria vault during a ... -
Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water
(The American Society of Mechanical Engineers (ASME), 2018)Within the Generation-IV International Forum, Canadian Nuclear Laboratories (CNL) led the conceptual fuel bundle design effort for the Canadian supercritical water cooled reactor (SCWR). The proposed fuel rod assembly for ... -
Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2018)The realistic study of dynamic accident context is an invaluable tool to address the uncertainties and their impact on safety assessment and management. The capacities of the performance evaluation of teamwork (PET) procedure ... -
Professor Pavel Leonidovich Kirillov on His 90th Birthday
(The American Society of Mechanical Engineers (ASME), 2018) -
Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events
(The American Society of Mechanical Engineers (ASME), 2018)Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP;The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental ... -
Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions—Case Supercritical Water
(The American Society of Mechanical Engineers (ASME), 2018)The presented work consists of a test setup study of a new pneumatic material testing device based on double bellows (DBs) loading device and with miniature autoclaves enabling applications at temperature and pressure up ... -
Comprehensive Seismic Evaluation of HTTR Against the 2011 Off the Pacific Coast of Tohoku Earthquake
(The American Society of Mechanical Engineers (ASME), 2018)On Mar. 11, 2011, the 2011 off the Pacific coast of Tohoku Earthquake of magnitude 9.0 occurred. When the great earthquake occurred, the high temperature engineering test reactor (HTTR) had been stopped under the periodic ...