The fast neutron reactor fuel rod includes nuclear fuel disposed in a hermetically-sealed container in the form of a thin-walled tubular casing, and a spacing element wound in a wide-pitch spiral and secured to the casing or to the end components. The spacing element is a thin-walled tube...
Several fuel systems have been developed for use in fast-spectrum reactors. Various fuel forms, almost exclusively utilizing in stainless-steel cladding tubes, have been extensively developed for use in sodium-cooled reactors. Although extreme fast neutron fluences and high temperature conditions create...
Fast neutron reactor fuel element of the present invention is characterized by a martensite - which covering layer is formed of ferritic steels, tissue along the longitudinal direction of the steel covering layer comprises at least two areas, the top area of the fuel cladding layer The steel ...
A near term source of TRU for starting FNRs is reprocessing of used CANDU reactor fuel. TRU can also be produced by other FNRs and by Intense Neutron Generators. At this time there is almost no public awareness that, as the economic supply of natural uranium and hence U-235 is depleted,...
STATUS AND PERSPECTIVES OF FUEL DEVELOPMENTS FOR FAST NEUTRON REACTORS OF 4TH GENERATION The R and D strategy in France on future reactors gives first priority to developing a new generation of fast neutron nuclear systems and recycling technologies so as to assure a sustainable and environment frien...
美 英 n.快中子 网络高速中子;速中性子 英汉 网络释义 n. 1. 快中子 释义: 全部,快中子,高速中子,速中性子
申请(专利)号: EP19810401453 申请日期: 1981-09-18 公开/公告号: EP0048671A1 公开/公告日期: 1982-03-31 申请(专利权)人: NOVATOME 发明人: P Andre 摘要: the invention relates to a device for the transfer of fuel assemblies for nuclear reactor, fast neutron reactor.收藏...
The fast neutron spectrum increases the convert from fertile materials to fissile materials, which help to reduce the burnup reactivity loss [1]. Due to the inherent physics of small reactor and high power density, SMSFRs with MOX fuel still exhibit an important excess reactivity that is used ...
Gas-cooled fast reactor (GFR): Helium-gas-cooled, fast-neutron-spectrum reactor with closed fuel cycle and outlet temperature about 850°C (shown with direct gas-turbine Brayton power cycle).Courtesy of Generation IV International Forum. The GFR uses the same fuel-recycling processes as the SFR...
Fast neutron reactor systems have the potential to extract 60 times more energy from uranium compared to existing thermal reactors, and they contribute to a significant reduction in the burden of radioactive waste. Wide progress has been... S Patel - 《Power the Magazine of Power Generation & ...