The Nuclear Engineering and Technolog

Part 1 book "Thermal engineering in power systems" includes content: Relevance of heat transfer and heat exchangers for the development of sustainable energy systems, advanced technologies for clean and efficient energy conversion in power systems, virtual engineering and the design of power systems, steam power plants, enhancement of nuclear power plant safety by condensation-driven passive heat removal systems, modern CFD application on aerothermal engineering aspects of natural draft cooling towers.

213p dianmotminh03 17-06-2024 1 0   Download

Ebook "Engineering of Stem Cells (Advances in biochemical engineering/biotechnology, Volume 114)" stays abreast of recent developments in stem cell biology and the high expectations concerning the development of stem cell based regenerative therapies. Regenerative medicine is the focus of current biomedical research, with unique challenges related to scientific, technical and ethical issues of stem cell research, and the potential added value of connecting biomedicine with enabling technologies such as materials sciences, mechanical and nanoengineering.

249p manmanthanhla0201 26-02-2024 3 1   Download

In view of the potential deployment of demonstrators and prototypes associated with the European Sustainable Nuclear Industrial Initiative (ESNII), the present licensing framework, based on the current Light Water Reactor (LWR) technology, will have to adjust as necessary taking into account to the new safety aspects introduced by these innovative technologies.

15p vironald 15-12-2022 12 4   Download

The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand out among the other reactor concepts proposed by Generation IV International Forum (GIF) for short-term deployment. The availability of reliable computational tools in support of safety analyses and plant simulations under complex transient scenarios is essential to assure SFR’s compliance with the highest safety goals.

11p vironald 15-12-2022 12 3   Download

The International Thermonuclear Experimental Reactor (ITER) Vacuum Vessel Pressure Suppression System (VVPSS) limits the Vacuum Vessel (VV) internal pressure, in case of loss of coolant (LOCA) or other pressurizing accidents from the in-vessel components, to 150 kPa (abs).

14p vironald 15-12-2022 17 3   Download

ALLEGRO is a concept of a small nuclear reactor with the primary aim to demonstrate the viability of the Generation IV (GFR) Gas cooled Fast Reactor technology and to ensure the experimental and qualification background for its new refractory fuel.

9p vironald 15-12-2022 10 3   Download

Severe accident mitigation technology was developed and evaluated for a small integral reactor of SMART. The containment pressure and hydrogen behavior were analyzed using MELCOR computer code (Sandia National Laboratory, 2018) in the SBO (Station Black Out) sequence, which was selected from PSA (Probabilistic Safety Assessment) results for the SMART.

8p vironald 15-12-2022 20 3   Download

Spray cooling is a versatile technology for various cooling applications involving high surface heat fluxes. Experimental facility was built to study heat transfer performance of an upward multi-nozzle array of water sprays impacting a surface of heated plate made of reactor vessel grade steel.

15p vironald 15-12-2022 9 3   Download

Gas-Cooled Fast reactor (GFR) is one of the favourable Generation IV type concepts under development. ALLEGRO reactor will be a demonstrator reactor of this gas-cooled fast reactor technology. Compared to conventional gas-cooled reactors in the case of a GFR reactor the power density is one order of magnitude higher, and the high temperature fuel assemblies are cooled by a low-density coolant (He), therefore special attention is paid to the heat transfer and heat removal performance of the reactor.

15p vironald 15-12-2022 14 3   Download

Part 1 of ebook "Applied chemistry: A textbook for engineers and technologists" provide readers with content about: energy - an overview; solid fuels; crude oil; liquid fuels; alternate fuels; gaseous fuels; nuclear energy;... Please refer to the part 1 of ebook for details!

192p langmongnhu 14-12-2022 14 3   Download

Study of nuclear fuel cycle in Vietnam at the aspect of domestic production, the exploitation and process of uranium ore were began. These processes generated large amounts of radioactive waste overtiming. The naturally occurring radioactive material and technologically enhanced radioactive material (NORM/TENORM) waste, which would be large, needs to be managed and disposed reasonably by effective methods.

6p vineptune2711 04-11-2019 13 0   Download

Korea also has a plan to build one more pool-type reactor, the Kijang Research Reactor, in Kijang, Busan. The safety classification of SSCs for pool-type research reactors is proposed in this paper based on the IAEA methodology. The proposal recommends that the SSCs of pool-type research reactors be categorized and classified on basis of their safety functions and safety significance.

12p minhxaminhyeu5 30-06-2019 7 0   Download

This paper discusses Phase I, known as the “Neutronics Phase”, which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility.

30p minhxaminhyeu5 30-06-2019 19 1   Download

According to the OECD/NEA estimates, nuclear power plants (NPPs), whether with a large reactor or with small modular reactors (SMRs), are competitive with many other electricity generation technologies in a significant number of cases, one of the exceptions being natural gas in the USA with the current level of prices. However, SMRs have particular features and requirements setting conditions for their deployment. This paper presents the preliminary analysis by OECD/NEA of the economics, opportunities, and market for small nuclear reactors.

6p minhxaminhyeu5 30-06-2019 12 0   Download

Wall-thinned defects caused by accelerated corrosion due to fluid flow in the inner pipe appear in many structures of the secondary systems in nuclear power plants (NPPs) and are a major factor in degrading the integrity of pipes. Wall-thinned defects need to be managed not only when the NPP is under maintenance but also when the NPP is in normal operation. To this end, a test technique was developed in this study to detect such wall-thinned defects based on the temperature difference on the surface of a hot pipe using infrared (IR) thermography and a cooling device.

10p minhxaminhyeu5 30-06-2019 13 0   Download

The results show that the proposed method increases the applicability and user-friendliness preserving accuracy in quantifying uncertainty propagation. We expect that the proposed strategy will contribute to efficient and accurate two-step MC calculations.

8p minhxaminhyeu5 30-06-2019 10 0   Download

In this paper, the current status of test activities is described briefly and significant results are discussed. The large-scale sodium thermal-hydraulic test program, Sodium Test Loop for Safety Simulation and Assessment-1 (STELLA-1), produced satisfactory results, which were used for the computer codes V&V, and the performance test results of the model pump in sodium showed good agreement with those in water.

13p minhxaminhyeu5 30-06-2019 21 0   Download

In order to produce the high beam power from electron linear accelerator, a proper beam current is required form the electron generator. In this study, the beam current was measured by evaluating the performance of the electron generator. The beam current was determined by five parameters: high voltage at the electron gun, cathode voltage, pulse width, pulse amplitude, and bias voltage at the grid.

8p minhxaminhyeu5 30-06-2019 13 1   Download

The results showed a strong correlation between the load and the premixed mass, defined as the mass of the molten material in low void zones (void fraction < 0.75). The jet diameter and velocity that comprise the flow rate were the primary factors to determine the premixed mass and the load.

8p minhxaminhyeu5 30-06-2019 10 1   Download

This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper.

12p minhxaminhyeu5 30-06-2019 8 0   Download