摘要:
A straight shell and tube heat exchanger utilizing double wall tubes and three tubesheets to ensure separation of the primary and secondary fluid and reliable leak detection of a leak in either the primary or the secondary fluids to further ensure that there is no mixing of the two fluids.
摘要:
A steam generator, used in a helical coil type steam generator for a sodium-cooled fast reactor which has heat transfer tubes of a double-wall tube structure, with high heat transfer efficiency and a heat transfer tube damage detection unit that can detect on-line in real-time whether the heat transfer tube is damaged or not. The heat transfer tube of a steam generator for a sodium-cooled fast reactor, includes an inner tube formed with a first material; an outer tube formed with a second material that is in close contact with the inner tube and which has a thermal expansion coefficient less than that of the first material; and a plurality of helium flow grooves formed between the inner tube and the outer tube along a lengthwise direction of the heat transfer tube for flowing helium gas. The inner tube and the outer tube are identically due to heat for the temperature difference generated during normal operation of the steam generator, so the degree of close contact between the inner tube and the outer tube does not decrease, and the decrease of heat transfer efficiency can be prevented.
摘要:
A nuclear reactor is provided characterized by a circulating liquid metal cooling system comprising a heat exchanger having a closed intermediate heat transfer fluid circuit in the form of a helical coil juxtaposed with the liquid metal coolant system, which effectively transfers heat through the intermediate circuit to a secondary fluid circuit. The intermediate heat transfer fluid circuit, which completely separates the liquid metal cooling system from the secondary fluid circuit, prevents potentially dangerous reactions between the primary liquid metal coolant and the secondary fluid (e.g., water).The efficiency, reliability and safety of the heat exchanger features eliminates the need for many secondary heat removal and emergency components in the design of the nuclear reactor.
摘要:
A double-wall tube for a heat exchanger and method for producing same, the tube being formed by two tubular walls (1, 2) mounted one inside the other with a very small clearance (3)and then made to have a tight fit therebetween, the outer surface of the inner wall (2) and the inner surface of the outer wall (1) being interconnected by a thin layer of brazing metal in regions (4) which are discontinuous both in the circumferential direction and in the longitudinal direction of the tube. The brazed regions (4) represent 5 to 15% of the confronting surfaces of the inner wall (2) and outer wall (1) of the tube. The invention is in particular applicable to steam generators of fast neutron nuclear reactors.
摘要:
A steam generator for a nuclear reactor cooled with liquid metal, comprising a bundle consisting of double-walled tubes (20) arranged inside an enclosure in which the liquid metal circulates. The tubes (20) which are substantially straight and directed in the axial direction of the steam generator enclosure are each formed by at least two successive sections (20a and 20b) in the axial direction. Each section (20a or 20b) comprises an outer tube (27a or 27b) welded at one of its ends to at least one leakage collecting chamber (25) arranged wholly inside the enclosure. The adjacent sections of the outer tubes (27a, 27b) are not joined together. Each section also comprises an inner tube (28a or 28b) welded to the adjacent inner tube, inside the chamber (25). The leakage space between the tubes (27 and 28) communicates solely with the inner space of at least one collecting chamber (25). The invention applies in particular to fast neutron nuclear reactors cooled with liquid sodium.
摘要:
The leak detection device is adapted to test the tightness of an inner tank (24) of a valve cell (20) of the vacuum deposition apparatus, either at its filling flange (25) or at its inner tank valve (28). A vacuum deposition apparatus equipped with a helium detector (51) mounted as a by-pass of the output of a high-flow-rate turbomolecular pump (42) which is connected to the vacuum deposition chamber (30) of the vacuum deposition apparatus by a slide gate valve (43). A valve-cell vacuum deposition apparatus equipped with a helium-based leak detection device including gas injection elements (52, 53) adapted to inject a gaseous mixture into the outer enclosure, the gaseous mixture being consisted of pure helium and an inert gas, and a method for detecting a leak in a valve-cell vacuum deposition apparatus are also described.
摘要:
A steam generator installation comprises an envelope, first and second tube plates defining an intermediate fluid discharge chamber; a bundle of external tubes connected to the tube plate, an internal tube being arranged within each external tube, a liquid metal circulating outside the external tube, an admission chamber for the water, which is introduced into the internal tubes, a discharge chamber for the steam and an admission chamber for the intermediate fluid. This fluid circulates between the internal tubes and the external tubes. The intermediate fluid discharge chamber is connected to the inlet of a heat exchanger, which cools it. The intermediate fluid admission chamber is connected to the outlet of this exchanger.
摘要:
In a heat exchanger having a tube bundle comprising a plurality of inner tubes and a plurality of cooling tubes, each of the inner tubes being arranged within each of the cooling tubes and passed therethrough to provide a double tube structure. The inside of the inner cooling tubes are gas tightly connected to both inlet and outlet chambers for high temperature fluid and the outside of the inner cooling tubes are gas-tightly connected to both inlet and outlet compartments for heat transfer medium as open ends, a high pressure lower temperature fluid is passed through the outside of the outer cooling tubes, a fluid having a high thermal conductivity, for example, molten lead, lead alloy, tin, tin alloy bismuth, sodium, salts of mercury or of sodium in a molten state, is passed through the outside of the inner cooling tubes as the heat transfer medium in ordinary case, and a gas having a low thermal conductivity is passed therethrough as a heat transfer medium when the inner tubes are required to be maintained at a high temperature.