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UNT Digital Library

UNT Digital Library

Aug 04, 2020 · The UNT Digital Library is a centralized repository for the rich collections held by the libraries, colleges, schools, and departments at the University of North Texas.

Transient Analyses of sCO Cooled KAIST-Micro Modular .

Transient Analyses of sCO Cooled KAIST-Micro Modular .

1 The 5th International Symposium - Supercritical CO 2 Power Cycles Transient Analyses of sCO 2 Cooled KAIST-Micro Modular Reactor with GAMMA+ code Nuclear & Quantum Engineering, KAIST Presenter: Bong Seong Oh Yoon Han Ahn, Seong Gu Kim, Seong Jun Bae, Seong Kuk Cho

Transient analyses of S-CO2 cooled KAIST Micro Modular .

Transient analyses of S-CO2 cooled KAIST Micro Modular .

NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety Gyeongju, Korea, October 9-13, 2016. N11A0092 1/14 Transient analyses of S-CO 2 cooled KAIST Micro Modular reactor with GAMMA+ code. Bong Seong Oh, Jeong Ik Lee*

CNS | Conference Proceedings Database

CNS | Conference Proceedings Database

J. Kim (Korea Advanced Institute of Science and Technology), Y. Kim (Department of Nuclear and Quantum Engineering, KAIST), K. Kim (Korea Hydro & Nuclear Power Co.), Saint John, Canada: 35th Annual CNS Conference: 2015: May 31 - June 3: CANDU6 PCR EVALUATION WITH A DETAILED 3-D MONTE CARLO ANALYSIS

1. Introduction

1. Introduction

Supercritical CO2(s-CO 2) Brayton cycle is a promising power conversion technology, which has advantages like compact system configuration compared to steam generation system, higher efficiency, and less need of water consumption.It has aroused great interests among industry and academia of different energy types, especially in nuclear and solar energy

Serpent - A Monte Carlo Reactor Physics Burnup Calculation .

Serpent - A Monte Carlo Reactor Physics Burnup Calculation .

Ahimsa, M. (2017) "Design Analysis of Fuel Assembly and Reactor Core of Floating Nuclear Power Plant KLT-40S using SERPENT." B.Sc. Thesis, Universitas Gadjah Mada, 2017. • Alam, S. (2018) "The Design of Reactor Cores for Civil Nuclear Marine Propulsion." Ph.D. Thesis, University of Cambridge, 2018. • Alameri, S. (2015) "A coupled nuclear reactor thermal energy storage system for enhanced .

Volumes | International Conference on Nuclear Engineering .

Volumes | International Conference on Nuclear Engineering .

Methodology for Identification of the Coolant Thermalhydraulic Regimes in the Core of Nuclear Reactors. L. G. Sharaevsky, E. I . Computational fluid dynamics, Computer software, Turbulence, Air flow, Gas cooled reactors, Gas flow, Generation IV . Application of Image Analysis With Noise Removal for Supercritical CO2. J. Ota, K .

Seong Gu Kim - Korea | Professional Profile | LinkedIn

Seong Gu Kim - Korea | Professional Profile | LinkedIn

This study suggests an innovative concept of a reactor directly cooled by supercritical carbon dioxide (S-CO2) with S-CO2 Brayton cycle as a power conversion system, namely KAIST MMR (Micro .

Theses and Dissertations Available from ProQuest | Theses .

Theses and Dissertations Available from ProQuest | Theses .

Lin, Ching-Sheng (2018) Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimization . Lindsay, Amelia M (2018) CAN-Based Forage Yield Mapping . Lin, Hao (2018) Large Scale Data Analysis in Parallel R and Its Use in Efficiently Scheduling Batch Jobs in the Cloud

Nuclear power - Wikipedia

Nuclear power - Wikipedia

Nuclear power is the use of nuclear reactions that release nuclear energy to generate heat, which most frequently is then used in steam turbines to produce electricity in a nuclear power plant.Nuclear power can be obtained from nuclear fission, nuclear decay and nuclear fusion reactions. Presently, the vast majority of electricity from nuclear power is produced by nuclear fission of uranium .

Supercritical CO2-cooled micro modular reactor

Supercritical CO2-cooled micro modular reactor

Mar 09, 2016 · The presentresearch aims to overcome these issues by adopting a supercritical COcooled micro modular reactor (KAIST MMR) concept that uses a long period core, which runs for more than 20 years .

Safety evaluation of supercritical CO2 cooled micro .

Safety evaluation of supercritical CO2 cooled micro .

Dec 01, 2017 · To overcome this limitation of current SMR designs, Korea Advanced Institute of Science and Technology (KAIST) research team has developed a concept of fully modularized nuclear reactor with supercritical CO 2 (S-CO 2) as a coolant as well as the power conversion system fluid, namely KAIST Micro Modular Reactor (MMR) (Kim et al., 2016a). The .

Volumes | International Conference on Nuclear Engineering .

Volumes | International Conference on Nuclear Engineering .

Methodology for Identification of the Coolant Thermalhydraulic Regimes in the Core of Nuclear Reactors. L. G. Sharaevsky, E. I . Computational fluid dynamics, Computer software, Turbulence, Air flow, Gas cooled reactors, Gas flow, Generation IV . Application of Image Analysis With Noise Removal for Supercritical CO2. J. Ota, K .

Advanced High-Temperature Reactors for Cogeneration of .

Advanced High-Temperature Reactors for Cogeneration of .

A 600 MW nuclear reactor with steam generator outlet temperature of 600°C is specified for the conceptual design. The system is designed to deliver process steam at two pressure levels: the high pressure process steam at 500°C (or 550°C if there is no intermediate reboiler) and low .

AnnexI - IAEA

AnnexI - IAEA

3.3. Gas-cooled reactors (GCRs) In the United Kingdom, nuclear electricity is mostly generated by CO2-cooled, graphite-moderated Magnox and advanced gas-cooled reactors. In several countries, prototype and demonstration GCR plants with helium coolant using the Rankine steam cycle for electric power generation have been built and operated.

METHODS AND SYSTEMS FOR LARGE SCALE CARBON DIOXIDE .

METHODS AND SYSTEMS FOR LARGE SCALE CARBON DIOXIDE .

Nov 30, 2017 · What is claimed is: 1. A method for obtaining and utilizing carbon dioxide gas from a body of water containing dissolved carbon dioxide gas and methane gas, said method comprising the steps of: (a) extracting water from at least one extraction depth of the body of water to obtain extracted water; (b) degassing the extracted water in at least one stage of .

KAIST research team proposes micro modular nuclear reactor .

KAIST research team proposes micro modular nuclear reactor .

Mar 11, 2016 · The KAIST research aims to overcome these issues by adopting as S-CO 2-cooled micro modular reactor (S-CO 2 MMR) concept that uses a long period core, which runs for more than 20 years without refueling, with supercritical CO 2 as coolant and uranium-nitride as fuel. By actively adopting the supercritical CO2 power system, the team simplified the .

1. Introduction

1. Introduction

Supercritical CO2(s-CO 2) Brayton cycle is a promising power conversion technology, which has advantages like compact system configuration compared to steam generation system, higher efficiency, and less need of water consumption.It has aroused great interests among industry and academia of different energy types, especially in nuclear and solar energy

The Oil Drum | Russia's Unique SVBR-100 Nuclear Reactor

The Oil Drum | Russia's Unique SVBR-100 Nuclear Reactor

Images 1 and 3 from G.I. Toshinsky, et. al. Small modular lead-bismuth cooled fast reactor for multi-purpose use: SVBR-75/100, which is published in Innovative small and medium sized reactors; Design features, safety approaches and R & D trends, May 2005. – .

(PDF) A Conceptual Study of a Supercritical CO2-Cooled .

(PDF) A Conceptual Study of a Supercritical CO2-Cooled .

A neutronics conceptual study of a supercritical CO2-cooled micro modular reactor (MMR) has been performed in this work. The suggested MMR is an extremely compact and truck-transportable nuclear .

The application of supercritical CO2 in nuclear .

The application of supercritical CO2 in nuclear .

Apr 13, 2018 · An SCO 2-cooled micro modular reactor (MMR) is a particularly compact and truck-transportable nuclear reactor which was designed by the Korea Advanced Institute of Science and Technology (KAIST). The thermal power of MMR is 36.2 MW with a designed lifetime of 20 years without refueling. 22 The first design goal for the KAIST MMR required it to .

Science and Technology of Nuclear Installations

Science and Technology of Nuclear Installations

Supercritical CO2 Brayton cycle is a good choice of thermal-to-electric energy conversion system, which owns a high cycle efficiency and a compact cycle configuration. It can be used in many power-generation applications, such as nuclear power, concentrated solar thermal, fossil fuel boilers, and shipboard propulsion system. Transient analysis code for Supercritical CO2

Proceedings of Second International Conference on .

Proceedings of Second International Conference on .

Figure 3 shows how improved efficiency and heat storage can help coal in future competion with nuclear energy. DIVERSIFICATION Up to now, fluidised-bed combustion has primarily been aimed at coal combustion; but in the last year or so, attention has spread to the burning of heavy oil and (more lately) Jo gas combustion.

RRFM 2014 Transactions - Poster - MAFIADOC.COM

RRFM 2014 Transactions - Poster - MAFIADOC.COM

To calculate the N-16 activity in the cooling supercritical water it is possible to use a proposed MCNP LVR-15 reactor active core model with the SCW FQT-loop installed. Crosssection of this active core configuration and a vertical cut of the loop's fuel section are shown on .

Theses and Dissertations Available from ProQuest | Theses .

Theses and Dissertations Available from ProQuest | Theses .

Lin, Ching-Sheng (2018) Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimization . Lindsay, Amelia M (2018) CAN-Based Forage Yield Mapping . Lin, Hao (2018) Large Scale Data Analysis in Parallel R and Its Use in Efficiently Scheduling Batch Jobs in the Cloud

supercritical reactor

supercritical reactor

The application of supercritical in nuclear engineering . reactors 2 reactor core coolant in the Echogen power system and reactors at MIT Kaist and Japan and other applications e g hydrogen production Based on the rapid progress of research the supercritical CO 2 is considered to be the most promising material in nuclear industries Keywords Nuclear reactor supercritical CO

Advanced High-Temperature Reactors for Cogeneration of .

Advanced High-Temperature Reactors for Cogeneration of .

A 600 MW nuclear reactor with steam generator outlet temperature of 600°C is specified for the conceptual design. The system is designed to deliver process steam at two pressure levels: the high pressure process steam at 500°C (or 550°C if there is no intermediate reboiler) and low .

International Conference on Fast Reactors and Related Fuel .

International Conference on Fast Reactors and Related Fuel .

The first International Conference on Fast Reactors and Related Fuel Cycles (FR09) was held in Kyoto, Japan, in 2009 and was subtitled "Challenges and Opportunities". The second conference (FR13) was held in Paris, France, in 2013 with the theme "Safe Technologies and Sustainable Scenarios" and was attended by some 700 experts from 27 countries and 4 international organizations .

Nuclear power - Wikipedia

Nuclear power - Wikipedia

Nuclear power is the use of nuclear reactions that release nuclear energy to generate heat, which most frequently is then used in steam turbines to produce electricity in a nuclear power plant.Nuclear power can be obtained from nuclear fission, nuclear decay and nuclear fusion reactions. Presently, the vast majority of electricity from nuclear power is produced by nuclear fission of uranium .

The Economics of Future Nuclear Power (Geoffrey Rothwell .

The Economics of Future Nuclear Power (Geoffrey Rothwell .

Commercial nuclear power reactor technologies. Figure 1.1 presents a generic nuclear power unit with five systems: System1 is the balance of plant .