(3) Bond compression is the common mechanism for the successful cold fusion reactors. (2) Compression of D-D bond can create the small D2 based on the electron orbit theory, which has been proved experimentally and theoretically. (1) Cold fusion occurs at the metal surface T site by the compression of D2 from the surrounding lattice atoms. I review my Cold fusion theory as described below, and I also propose the experiment to prove hydride bond compression theory based on the currently available reactors and propose the conceptualized Cold fusion reactors based on the cold fusion mechanism. Therefore, perhaps the most acceptable coolant option for small-sized modular reactors may be ordinary lead. Liquid metal coolant – liquid sodium requires special care in handling it due to its fire and explosion hazard, and the use of a lead-bismuth coolant leads to the formation of a large amount of hazardous radioactive polonium-210, which, in case of accidents with depressurization, can escape into the environment and lead to serious radiation consequences in the adjacent territories. The use of gas, organic heat transfer fluids or salts causes no less problems and risks. Despite the seemingly obvious choice, the use of water as a coolant carries significant risks of a heat transfer crisis in the core in emergency situations, and the possibility of an exothermic zirconium vapor reaction has led to catastrophic consequences at the Fukushima-Daiichi NPP. However, the problem of optimal choice of the type of coolant for such reactors remains unresolved. Small modular reactors installed in single or multi-unit power plants make it possible to combine nuclear and alternative energy sources, including renewable sources. One of the main directions of modern development of nuclear energy is the creation of small modular reactors. The versatility of the proposed system allows using it for different reactor plants of a wide power range, designed for various nuclear research areas. The absence of elements with mechanical moving parts can significantly reduce the equipment failures probability and increase the reliability of the cooling system while reducing its cost. The cooling circuits include only vessels, piping and heat exchangers. Such design excludes the release of the radioactive coolant into the surrounding environment for any depressurization of the circuits. The examples of the numerical assessment of transients during operation in normal and accident modes are shown to substantiate the possibility of using such system in research reactors of medium and high power, providing a neutron flux of more than 1 × 1015 cm-2/s.Ī fundamental feature of the presented passive heat removal system is the absence of active elements in the cooling circuits, such as circulation pumps, shut-off and control valves, as well as the presence of an intermediate circuit with a non-radioactive coolant, made according to the principle of operation of a heat pipe (thermic syphon). This Chapter presents à three-dimensional model, technological and design diagrams of a reactor unit. This cooling system develops the concept of a reactor plant presented in. The cooling system based on the passive principle of natural convection of the coolant.
This paper presents the results of the analysis of a universal system for cooling of the research reactors core.
Irina Uzikova, Nuclear Safety Engineer, Assystem E&OS (France) Vitaly Uzikov, Lead Ingeeneer, JSC “SSC RIAR” (Russian Federation)
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