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[en] This project has been focused on the experimental and numerical investigations of the water-cooled and air-cooled Reactor Cavity Cooling System (RCCS) designs. At this aim, we have leveraged an existing experimental facility at the University of Wisconsin-Madison (UW), and we have designed and built a separate effect test facility at the University of Michigan. The experimental facility at UW has underwent several upgrades, including the installation of advanced instrumentation (i.e. wire-mesh sensors) built at the University of Michigan. These provides high resolution time-resolved measurements of the void-fraction distribution in the risers of the water-cooled RCCS facility. A phenomenological model has been developed to assess the water cooled RCCS system stability and determine the root cause behind the oscillatory behavior that occurs under normal two-phase operation. Testing under various perturbations to the water-cooled RCCS facility have resulted in changes in the stability of the integral system. In particular, the effects on stability of inlet orifices, water tank volume have and system pressure been investigated. MELCOR was used as a predictive tool when performing inlet orificing tests and was able to capture the Density Wave Oscillations (DWOs) that occurred upon reaching saturation in the risers. The experimental and numerical results have then been used to provide RCCS design recommendations. The experimental facility built at the University of Michigan was aimed at the investigation of mixing in the upper plenum of the air-cooled RCCS design. The facility has been equipped with state-of-the art high-resolution instrumentation to achieve so-called CFD grade experiments, that can be used for the validation of Computational Fluid Dynanmics (CFD) models, both RANS (Reynold-Averaged) and LES (Large Eddy Simulations). The effect of risers penetration in the upper plenum has been investigated as well.
[en] Mechanical filters are very important to ensure smooth operation of the secondary cooling system. The present condition of the mechanical filter treatment duration of PA-02 BT001 is increasing compared to other mechanical filters (PA-01 BT001 and PA-03 BT001). Seeing these conditions, it is very important to conduct an evaluation / study to find the cause and resolution through operating data starting in 2010 - 2017, collection of maintenance data starting from 2010 - 2017. After evaluation and review it can be concluded that the mechanical filter causes (PA-02 BT001) maintenance is most often compared to other mechanical filters, this is due to the location of the mechanical filter (PA-02 BT001) located on the side of the pipe straight at the far end so that dirt and lichen will be carried to the section. Besides this, PA-02 BT001 also serves cooling towers on the outside so that the growth of moss is more than the others. Based on these results, it is very important to review the mechanical filter operating schedule, maintenance scheme and the use of anti-moss in secondary cooling system water. (author)
[en] An outcome of the Joint Review Panel that evaluated the proposal by Ontario Power Generation (OPG) for the Darlington New Nuclear Project was that OPG must undertake a formal quantitative cost-benefit analysis for cooling tower versus once-through condenser cooling water systems. While OPG's analysis concluded the preference for the once-through condenser approach, the possibility for using cooling towers remains. This paper presents an analysis of the different cooling tower designs that could be used for a potential CANDU new build at the Darlington Site. The work was completed in partial fulfilment of the requirements of a capstone design project by a group of nuclear engineering students. The project considered the various cooling tower designs used in similar applications for both nuclear and thermal power plants, and identified the preferred option based on criteria such as: energy penalty, cost, thermal/aquatic effects, social acceptance and land use. (author)
[en] Repair chiller pump for indications of cooling water droplets on the seal pump is air-wasters. In the visual observation of the seal cooling water droplets above the range of 15 drops per minute, for normal conditions is permitted droplets: 10 sid 15 drop per minute. Because beyond normal limits then need immediate replacement, among others: gland packing, gland follower as it broke, shaft sleeve for wear, and rubber clutch. After the replacement chiller pump P 62303 test functions and adjustment. The result obtained by the cooling water droplets are 11 drops per minute, so that the pump can operate properly. (author)
[en] The present study provides the overview of Maisotsenko Cycle (M-Cycle) applications for gas cooling in compressor systems. Various schemes of gas cooling systems are considered regarding to their thermal efficiency and cooling capacity. Preliminary calculation of M-cycle HMX has been conducted. It is found that M-cycle HMX scheme allows to brake the limit of the ambient wet bulb temperature for evaporative cooling. It has demonstrated that a compact integrated heat and moisture exchange process can cool product fluid to the level below the ambient wet bulb temperature, even to the level of dew point temperature of the incoming air with substantially lower water and energy consumption requirements. (paper)
[en] Nuclear Technologies: • Investigation of Technological Challenges related to the Removal of Heat by Liquid Metal and Molten Salt Coolants from Reactor Cores Operating at High Temperatures (COOL); • Decay Heat Removal System for Liquid Metal Cooled Reactors (DHR); • Advanced Water Cooled Reactors (AWCR); • Performance Assessment of Passive Gaseous Provisions (PGAP). • Institutional Arrangements: • Implementation Issues for the Use of Nuclear Power in Small Grid Countries (SMALL); • INPRO Study on Legal and Institutional Issues of Transportable NPPs.
[en] Canadian Nuclear Society (CNS) and Canadian Nuclear Laboratories (CNL) hosted the 4th International Technical Meeting on Small Reactors which was held in Ottawa, Ontario, Canada, on November 2-4, 2016. Small nuclear reactors can play an important role in addressing the energy, health, safety, security and climate change goals of the world. While the water-cooled small modular reactor technology is developing rapidly, a number of non-water-cooled advanced small reactor technologies, such as the molten salt reactor, the liquid metal reactor and the high temperature gas reactor, are being developed. These small reactors have advanced passive safety features, are resistant to nuclear proliferation, have no greenhouse gas emissions and promoted as being economically competitive. They are suitable for niche and off-grid applications as well as connection to electric grids in slow-growing economies to increase capacity as needed. Next-generation research reactors are considered for multiple purposes, such as radionuclide production, silicon doping, neutron activation, neutron radiography, materials research, fuel irradiation and generating data for reactor physics code validation activities. The technical meeting covered topics of interest to designers, operators, researchers and analysts involved in the design, development and deployment of small reactors for research and power generation purposes.
[en] This paper presents the measurement and analysis results for the performance of HGCHP system using a cooling tower as a supplemental heat rejector. In order to demonstrate the performance of the hybrid approach, we installed the monitoring equipments including sensors for measuring temperature and power consumption, and measured operation parameters from February 1, 2014 to February 28, 2015. Leaving load temperatures to building showed an average value of 11.7℃ for cooling and 39.5℃ for heating, respectively. From the analysis, the daily PF of hybrid GCHP system varied from 2.6 to 6.6 over the measurement period.