Nuclear reactor - Nuclear reactor - Coolant system: The function of a power reactor installation is to extract as much heat of nuclear fission as possible and convert it to useful power, generally electricity. Advanced gas-cooled reactors (AGR), achieving much higher efficiencies of conversion (about 40 per cent) by using for cooling C02 at higher temperatures and pressures (42 kg/cm2 and 650°C) but fuelled with 2–5 per cent enriched uranium, are now at the demonstration stage at the industrial scale. In the following, the discussion centres on Magnox (Section 12.2) and AGR plant (Section 12.3), and follows with a brief discussion of HTR and future systems (Section 12.5). They purchase them based on actual performance and their ability to meet certain specified requirements. The reactor pressure vessel of gas-cooled reactors is enormous by comparison with typical water reactor plant. In this regard, the UK’s Magnox design was superseded by the Advanced Gas-cooled Reactor(AGR), which is similarly cooled but includes changes to improve its economic performance. 1.39. 12.10, the carbon dioxide circulates through the core, absorbing the heat from the fuel elements and reaching 650∘C. dioxide gas is used for cooling instead of water, it was not economical. The new generation of GCR, the ACR (or advanced gas reactors), use enriched uranium as fuel. They were also used for producing electricity for the civil market. Oxidation will now result in the formation of a non-protective oxide and, as this grows, the oxide/metal interface will move into the body of the metal until the chromium level reaches about 18.5% when a protective oxide will once again form (Lobb and Evans, 1983 [14]). Subsequent plants used low-enriched uranium–oxide fuel clad with stainless steel. A gas reactor or GCR (English gas cooled reactor) is a type of nuclear nuclear reactor of nuclear fission. At burn-ups beyond about 10 to 15 GWd/t differential fuel swelling (due to the inexorable production of solid fission products) takes over from differential creep shortening as the major source of pin bowing. in which fuel and moderator are separated moderator being highly pressurised, e.g. Commercial GCRs use a graphite neutron moderator, which absorbs fewer neutrons than water-moderated reactors. Dawson, M. Phillips, in Nuclear Fuel Cycle Science and Engineering, 2012. J.W. Each station is supplied with twin-reactors, the site of Heysham has two Cutaway of a 36-pin AGR fuel assembly. 28–29). In high temperature (>500°C) CO2 the steel forms a protective oxide, the composition of which ranges from Fe3O4 on the outside to mixed spinels closest to the metal substrate. The main reason for doing this was to minimise contamination of the boilers by the highly radioactive oxide dust. The UK Windscale Piles operated in the 1950s until the Pile 1 fire in 1957. At burn-ups of 15 GWD/t the ductility may be reduced from its pre-irradiation value of 20–40% to values of 5% or less (Clay and Beere, 1985 [9]). Even so, it is quite possible that if, in future, peak clad temperatures are allowed to rise, the greater oxide thicknesses will allow the spalling threshold to be crossed. This temperature gradient is believed to be the primary cause of pin bowing (Crossland, 1982 [12]). The coolant system plays a pivotal role in performing this function. Thus although the present AGRs are not considered to be other than base load and hence decoupled, there is an inherent capability that can be exploited. In the UK the first eight Magnox reactors (four each at Chapelcross and Calder Hall) were used for the manufacture of weapons grade plutonium, and in the case of Chapelcross were also used for the manufacture of tritium for military purposes until shut down. TABLE 1.13. This produces a small but steadily increasing pin bow which is directed outwards towards the graphite sleeve. If there is a cross-clad temperature difference, this process will occur more rapidly on the hotter side, so that the interpellet gaps will become wedge-shaped and the pin will bow. At clad temperatures below about 650°C axial creep effects are negligible and the main cause of pin bowing is differential thermal expansion (thermal bowing) of the pellet stack and/or the clad. Fortunately the design of the fuel is such that thermal bows, even including feedback, are very small in CAGR. The 13-MWe AVR reactor has been successfully operated for 21 years in Germany demonstrating application of HTGR technology for electric power production. Diffusion from the fuel compact or graphite block to the coolant 12.6.5. Prismatic core reactor/graphite block - HTR-GT example 12.6.1. New!! The main operating parameters for the CAGRs are shown in Table 1.13. Schematic diagram of a GCR. Brain plants in the United States. The high-temperature gas-cooled reactor (HTGR) is similar in concept to the AGR. The essential differences between the AGR, Magnox and UNGG models are the fuel they use and the coating around the pellets. As already mentioned, creep shortening is the process whereby axial creep occurs at interpellet gaps. The first generation of reactors based on the combination of graphite and carbon dioxide that produced power on a commercial basis were known as Magnox on account of the magnesium–aluminium alloy used as the fuel cladding that resisted oxidation: ‘magnesium no oxidation’. Such a power increase will produce differential thermal expansion which may cause the pellet to strain the clad; because of ‘hourglassing’ (also known as ‘wheatsheafing’, Fig 1.36) such effects peak at the ends of pellets. According to the classification made by the International Atomic Energy Agency of the United Nations, IAEA, this type of reactors includes those of the AGR type (of the English Advanced Gas-cooled Reactor) and Magnox (of the English Magnesium Non-OXidising), both of British technology. FIG. Modifying the coolant gas composition from 85 g/mol He–Xe to 20 g/mol. Here, a large reduction in reactor power can produce plastic ratcheting strains in the clad which cause the pins to elongate (Stacey, Jones and Bradshaw, 1976 [10]). However, only in the UK were gas-cooled reactors pursued with enthusiasm. Gas-cooled reactors use graphite as a neutron moderator and carbon dioxide gas as the coolant. are contained within each pin, the clad consisting of a 0.38 mm thick stainless steel tube of about 15 mm o.d. AGR fuel elements incorporate discrete absorber cables containing gadolinia Gd2O3 powder in a stainless steel tube. The high temperature gas cooled reactor pebble-bed module (HTR-PM) is selected for the study on the precooling transient of SG. The High Temperature Gas-Cooled Reactor Next Generation Nuclear Energy. Computed response of advanced gas cooled reactor to +10% demand. This improved the thermodynamic efficiency to around 42%, compared to around 28% in a Magnox plant (and 32% in a modern PWR). IV-2. FIG. This results partly from the need to accommodate the massive graphite moderator, as well as from the reduced heat removal capacity of the coolant. international working group on gas-cooled reactors gas-cooled reactor coolant circulator and blower technology proceedings of a specialists meeting organized by the international atomic energy agency and held in san diego 30 november-2 december 1987 international atomic energy agency, vienna, 1988. The first-generation GCRs were built in the United Kingdom and France and used natural uranium metal fuel and magnesium or magnesium alloys for the cladding. CAGR main reactor parameters (after Hart 1977). With the 3% of market share, all of them are installed in the UK. Around 65 hollow, dished end, fuel pellets (14 mm o.d., 5 mm i.d.) Schematic of a dual-pressure gas-steam plant. he High Temperature Gas-cooled Reactor (HTGR) nuclear heat supply system (NHSS) is composed of three major components: a helium-cooled nuclear reactor, a heat transport system, and a cross helium or carbon dioxide, is used as the coolant. By continuing you agree to the use of cookies. The design temperature of the HTR-PM reaches 750 degrees Celsius. 14 AGR reactors have been built, located at 6 different sites and seven stations, Figure 1.1. and Table 1.1. Because they use a different fuel form and cladding, they avoid steam/zirconium cladding chemical reactions that can release explosive hydrogen gas under accident conditions in LWRs. These reactors use natural or slightly enriched uranium as a fuel. If the temperature decrease is large and/or the oxide is thick, the elastic energy associated with these stresses can be sufficient to overcome the interfacial bonding energy between the oxide and the substrate, causing the oxide to spall. The mid points and the top ends of the pins are supported by braces which are fabricated by spot welding stainless steel strip. A total of 14 AGR reactors were built on six sites in the UK (plus a small, prototype reactor). Additionally, exposing helium to neutron radiation does not make it … Heat transfer is optimised by the machining of circumferential ribs on the external surface of the clad; these are 0.4 mm square in section and have a pitch (spacing) of 2 mm. Nuclear power generation technology has undergone an evolution from fuel rods and heavy water to newer designs of reactors that can be cooled by light water and more recently by gas. Reactor gas outlet temperature is controlled via a flux reactivity loop, suitably modified by the station power demand signal. The grid, braces and pins are contained within two concentric graphite cylinders or sleeves. Its use is limited to the United Kingdom; it is sometimes known as the Magnox reactor. This is more pronounced at high clad temperatures in the presence of many small gaps (rather than a few big ones) and is generally beneficial since it helps prevent the formation of large interpellet gaps, an objective which is further aided by minimising the frequency of shut downs and reactor trips. From that of the design temperature of the HTR-PM reaches 750 degrees Celsius through the core following loss forced! 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