Cooling systems liquid metal

Other samples examined to date have included mass-transfer inclur s from liquid metal cooling systems, titanium alloy phases, and interm c... 

Liquid metal-cooled systems include those for the SFR and the lead (or lead-bismuth)-cooled fast reactor (LFR). The SFR (see a possible design in Fig. 1.3) uses liquid... 

Sodium superheat experiments were performed in a forced-convection facility employing system parameters in the range of interest for application to loop- and pot-type liquid metal-cooled fast breeder reactors (LMFBRs). The test section was... 

Considerable radioactivity is induced in the sodium in the primary cooling circuit of a liquid metal cooled fast breeder reactor (LMFBR) Na(n,y) Na, Na(n,p) Ne, etc. Na has a IS h r, and emits energetic y s. The primary cooling loop must therefore be well shielded. Its activity is a nuisance only in case of repair work in the primary system, requiring considerable waiting time before the loop can be approached. The sodium dissolves many of the corrosion and fission products eventually released. To remove these the primary loop is provided with cold trap purification systems. 

Liquid metal cooled reactors (LMR) have been under development for more than 40 years, and several have been built and operated on commercial power grids. Sodium has been generally used as the coolant in these systems, and experience with this technology has been mixed. Sodium leaks have been the most notable technical issue, and the fact that sodium is very chemically reactive with air and water has contributed to most of the concerns about LMRs. The technolo is clearly still developmental even though there is considerable valuable experience. 

This order applies to all varieties of reactors including, but not limited to light water moderated reactors, heavy water moderated reactors, liquid metal cooled reactors, gas cooled reactors and short-pulse transient reactors. Space reactor power and propulsion systems and critical facilities require special design criteria. Attachment 4 is reserved for Nuclear Safety Design for critical facilities and space reactors. 

Passive safety systems similar to gas-cooled and liquid-metal-cooled reactors engineered in the 1980s and 1990s, especially the Super Power Reactor Inherently Safe Module (S-PRISM) design developed by General Electric (GE). ... 

These three main lines, as defined by their primary coolant are water cooled, gas cooled, and liquid metal cooled. Water cooled reactors can be fiirther categorized as heavy water or light water moderated reactors. The design approach for a given system can be substantially different from another system within the same technology line. The small and medium reactor area has to deal with all technological lines and all varying approaches. The relevant reactor information for the purpose of this TECDOC has been divided into six parts ... 

Chapters 6 through 8 give an introductory look at the liquid metal cooled reactor system, the molten salt reactor, and also the small modular reactor systems. Chapter 9 introduces the Gen IV reactor design concepts that have been developed by the United States Department of Energy (USDOE). 

KNK-II was built and has been operated to serve as the nation s first fast flux irradiation facility, to gain operating experience with a liquid metal cooled fast reactor system and to conduct an extensive test programme in fast reactor environment. 

The Chapter is organized as follows. First, some fuel cycle characteristics used in comparative analysis of energy systems with different reactors are introduced. Second, open fuel cycle features and support strategies are surveyed for the nearer-term concepts. Then, the several proposed fuel cycle features and support options for the closed cycle concepts are surveyed. After that, fuel and ore resource utilization efficiencies for small reactors with long refuelling interval are discussed and are compared to those of standard light water reactors (LWRs) and typically projected liquid metal cooled fast breeder reactors (LMFBRs). Implications on fuel cycle costs are discussed, and the notion of fuel leasing is presented. 

The LFR system provides for ambient pressure single-phase primary coolant natural circulation heat transport and removal of core power under all operational and postulated accident conditions. The high boiling temperature of the Pb coolant enables heat transport by natural circulation of the primary coolant at significantly higher temperatures than with traditional liquid metal cooled reactors. External natural convection driven passive air-cooling of the guard/containment vessel is always in effect and removes power at decay heat levels. 

XXn-10] MOISSEYTSEV, A., SIENICKI, J.J., WADE, DC., Cycle analysis of supercritical carbon dioxide gas turbine Brayton cycle power conversion system for liquid metal-cooled fast reactors, ICONE-11 (11 Int. Conf. on Nuclear Engineering, Tokyo, April 20-23, 2003), Paper ICONE 11-36023. 

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