Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 681-700 of 913
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Computational Fluid Dynamic Simulation of the Moderator Flow in CANDU-6 Nuclear Reactors
(The American Society of Mechanical Engineers (ASME), 2017)For CANada Deuterium Uranium (CANDU) nuclear reactors, the characterization of the moderator thermal-hydraulic behavior under both normal and abnormal operating conditions constitutes an important safety issue. For normal ... -
Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants
(The American Society of Mechanical Engineers (ASME), 2017)As a nongreenhouse gas-emitting source, the benefits of nuclear as a main power-generation alternative are yet to be fully explored; part of the reason is due to the significant implementation costs. However, with cycle ... -
SMR Fuel Cycle Optimization Using LWROpt
(The American Society of Mechanical Engineers (ASME), 2017)This article describes the light water reactor optimizer (LWROpt), a fuel cycle optimization code originally developed for BWRs, which has been adapted to perform core fuel reload and/or operational control rod management ... -
The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor
(The American Society of Mechanical Engineers (ASME), 2017)The iron cross-section in thermal regions influences the thermal neutron flux prediction in steel structural components of reactors and also in regions adjoining them. The thermal neutron flux level is proportional to pin ... -
Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor
(The American Society of Mechanical Engineers (ASME), 2017)The high-temperature engineering test reactor (HTTR) is a block-type high-temperature gas-cooled reactor (HTGR), which was constructed in Japan. The operating data of HTTR with burn-up to about 370 EFPD (effective full-power ... -
Innovation of Irradiation Equipment at the LVR-15 Nuclear Research Reactor
(The American Society of Mechanical Engineers (ASME), 2017)This paper describes the design and use of a new irradiation facility for the LVR-15 nuclear research reactor. The CHOUCA MT irradiation rig was produced in France according to a design of the ÚJV Group (ÚJV Řež and Research ... -
Full-Scope Probabilistic Safety Assessment of Balakovo Unit 1 in Russia
(The American Society of Mechanical Engineers (ASME), 2017)The Balakovo Nuclear Power Plant operating in Russia has four operating units of a VVER-1000 type. The first unit was connected to the grid on Dec. 28, 1985, and put in commercial operation on May 23, 1986. According to ... -
Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle
(The American Society of Mechanical Engineers (ASME), 2017)Deterministic and Monte Carlo methods are regularly employed to conduct lattice calculations. Monte Carlo methods can effectively model a large range of complex geometries and, compared to deterministic methods, they have ... -
Integrated Chemical Effects Head Loss Experiments Using Multiconstituent Fibrous Debris Beds
(The American Society of Mechanical Engineers (ASME), 2017)The chemical head loss experiment (CHLE) program has been designed to acquire realistic material release and product formation in containment under post-loss of coolant accident (LOCA) conditions and their impact on the ... -
Influence of Pleat Deformation on Pressure Drop for a High-Efficiency Particulate Air Filter: A Small-Scale Experimental Approach
(The American Society of Mechanical Engineers (ASME), 2017)For industrial or domestic applications, the wide range of use of pleated filters makes the understanding of their airflow behavior a major issue for designer and users. In all industrial installations dealing with radioactive ... -
A Methodology to Analyze the Safety of a Coastal Nuclear Power Plant Against Typhoon External Flooding Risks
(The American Society of Mechanical Engineers (ASME), 2017)For the protection of a coastal nuclear power plant (NPP) against external flooding hazard, the risks caused by natural events have to be taken into account. In this article, a methodology is proposed to analyze the risk ... -
Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor
(The American Society of Mechanical Engineers (ASME), 2017)The high-temperature engineering test reactor (HTTR) is a block-type high-temperature gas-cooled reactor (HTGR). There are 32 control rods (16 pairs) in the HTTR. Six of the pairs of control rods are located in a core ... -
Editorial Greeting to Journal Readers 2017
(The American Society of Mechanical Engineers (ASME), 2017) -
Transfer and Storage of Molten Salt for the Pyroprocessing of Used Nuclear Fuel
(The American Society of Mechanical Engineers (ASME), 2017)A vacuum-induced salt transfer and storage (VISTAS) system is being evaluated to improve transfer and storage of molten electrorefiner (ER) salts at Idaho National Laboratory (INL). Salt is transferred by vacuum through a ... -
Design of a Tritium-In-Air Monitor Using Field-Programmable Gate Arrays
(The American Society of Mechanical Engineers (ASME), 2016) -
Bypass Flow Resistance in Prismatic Gas-Cooled Nuclear Reactors
(The American Society of Mechanical Engineers (ASME), 2017)Available computational fluid dynamics (CFD) predictions of pressure distributions in the vertical bypass flow between blocks in a prismatic gas-cooled reactor (GCR) have been analyzed to deduce apparent friction factors ... -
List of Reviewers for 2016
(The American Society of Mechanical Engineers (ASME), 2017) -
Research of Nuclear Power Plant In-Service Maintenance Based on Virtual Reality
(The American Society of Mechanical Engineers (ASME), 2016) -
Metastable Liquid Cavitation Control (With Memory) Apparatus, Methodology, and Results: For Radiation Detection, Reactor Safety, and Other Industrial Applications
(The American Society of Mechanical Engineers (ASME), 2017)We present a method to simultaneously pressurize fluid filled containers from outside and within, results of experiments with temporary 2 h of fluid precompression followed by overpressure removal before testing for ... -
Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop
(The American Society of Mechanical Engineers (ASME), 2017)In this study, transient analysis code of SCWRs (TACOS), with the ability of simulating transients or accidents under both supercritical water (SCW) conditions and subcritical water conditions, has been developed with ...