Gas cooled fast reactor

Part 1 book "Nuclear hydrogen production handbook" includes content: The role of hydrogen in the world economy, nuclear hydrogen production - an overview, water electrolysis, steam electrolysis, thermochemical decomposition of water, conversion of hydrocarbons, biomass method, radiolysis of water, water reactor, high temperature gas reactor, sodium fast reactor, gas fast reactor, fluoride salt advanced high temperature reactor, STAR-H2 - A Pb-Cooled, long refueling interval reactor for hydrogen production.

395p muasambanhan09 12-03-2024 1 0   Download

A simulation-based study concerning three non-destructive approaches by which water in spent nuclear fuel assemblies might be quantified with neutrons is described. Three fuel types have been considered: thirty-six spent Advanced Gas-cooled Reactor (AGR) fuel pins contained in a stainless-steel can; a prototype fast reactor (PFR) spent fuel assembly and a light water reactor (LWR) spent fuel assembly – with the PFR and LWR assemblies containing mixed oxide fuels.

25p vironald 15-12-2022 13 4   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

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

This paper presents the neutronics characteristics of a prototype gas-cooled (supercritical CO2-cooled) fast reactor (GCFR) with minor actinide (MA) loading in the fuel. The GCFR core is designed with a thermal output of 600 MWt as a part of a direct supercritical CO2 (S-CO2) gas turbine cycle.

9p vineptune2711 04-11-2019 15 1   Download

This self-enlargement of the crack is called “self-wastage phenomena.” A stepwise numerical evaluation model of the self-wastage phenomena was devised using a computational code of multicomponent multiphase flow involving a sodium ewater chemical reaction: sodiumwater reaction analysis physics of interdisciplinary multiphase flow (SERAPHIM). The temperature of gas mixture and the concentration of NaOH at the surface of the tube wall are obtained by a numerical calculation using SERAPHIM. Averaged thermophysical properties are used to assess the local wastage depth at the tube surface.

12p minhxaminhyeu5 30-06-2019 13 1   Download

To achieve comprehensive understanding, various parameters including particle bed height, particle size, density, shape, gas pressure along with the gas-injection duration, were employed. It is found that due to the different interaction mechanisms between solid particles and the gas bubble injected, three kinds of regimes, termed respectively as the bubble-impulsion dominant regime, the transitional regime and the bed-inertia dominant regime, could be identified.

11p minhxaminhyeu3 12-06-2019 26 0   Download

The scrubbing of aerosol and vapor are modeled based on deposition mechanisms and Fick's law of diffusion, respectively. Studies were performed to determine the effect of various key parameters on wet scrubbing. It is observed that for higher vapor diffusion coefficient in gas bubble, the scrubbing efficiency is higher. For aerosols, the cut-off size above which the scrubbing efficiency becomes significant was also determined.

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This book presents a comprehensive review of studies in nuclear reactors technology from authors across the globe.

350p cucdai_1 16-10-2012 89 15   Download

CHAPTER 56 NUCLEAR POWER William Kerr Department of Nuclear Engineering University of Michigan Ann Arbor, Michigan 56.1 HISTORICAL PERSPECTIVE 56.1.1 The Birth of Nuclear Energy 56.1.2 Military Propulsion Units 56.1.3 Early Enthusiasm for Nuclear Power 56.1.4 U.S. Development of Nuclear Power CURRENT POWER REACTORS, AND FUTURE PROJECTIONS 56.2. 1 Light- Water-Moderated Enriched-Uranium-Fueled Reactor 56.2.2 Gas-Cooled Reactor 56.2.3 Heavy-Water-Moderated Natural-Uranium-Fueled Reactor 56.2.4 Liquid-Metal-Cooled Fast Breeder Reactor 56.2.

24p hadalabo 29-09-2010 78 6   Download