Supercritical-water-cooled reactor

Cline JA, Jonah CD, Bartels DM (2000) In The solvated electron in supercritical water spectra, yields, and reactions, Proceedings of the 1st International Symposium in Supercritical Water-cooled Reactors, Design, and Technology, Tokyo, Nov 6-9... 

Supercritical-water-cooled reactor (SWCR) (U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum 2002)... 

Supercritical-water-cooled reactor (SCWR) system... 

The supercritical-water-cooled reactor (SCWR) ( Fig. 58.21) system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectmm reactor and full actinide recycle. Both options use a high-temperature, high-pressure, water-cooled reactor that operates above the thermodynamic critical point of water (22.1 MPa, 374°C) to achieve a thermal efficiency approaching 44%. The fuel cycle for the thermal option is a once-through uranium cycle. The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle. The fast-spectrum option depends upon the materials R D success to support a fast-spectrum reactor. 

The supercritical water-cooled reactor is a normal light water reactor (LWR) that has increased temperature and pressure. The purpose is to place the water in the primary coolant loop into a supercritical state, which would dramatically increase operating efficiency. 

With these goals in mind, some 100 experts evaluated 130 reactor concepts before GIF selected six reactor technologies for further R D. These include the gas-cooled fast reactor (GFR), lead-cooled fast reactor (LFR), molten salt reactor (MSR), supercritical water-cooled reactor (SCWR), sodium-cooled fast reactor (SFR), and very high temperature reactor (VHTR). 

Supercritical water-cooled reactor NPP (one of Canadian concepts reactor coolant — light water P = 25 MPa and Ph/Pom = 350/625°C (P = 374°C) direct cycle high-temperature steam superheat Po , = 625°C possible backup — indirect supercritical-pressure Rankine steam cycle with high-temperature steam superheat). 45-50... 

Kaneda, J., Kasahara, S., Kano, F., Saito, N., Shikama, T., Matsui, H., 2011. Material development for supercritical water-cooled reactor. In Proc. ISSCWR-5, Vancouver, BC, Canada, March 13—16. 

Types of supercritical water-cooled reactor concepts and main system parameters... 

Figure 8.1 Simplified supercritical water-cooled reactor design principle with a once-through steam cycle. HP, high pressure IP, intermediate pressure LP, low pressure PH, preheater CEP, condensate extraction pumps FP, feed-water pump G, generator.

Figure 8.4 Schematic of direct steam cycle with a moisture separator reheater in a supercritical water-cooled reactor plant. HPT, high-pressure turbine IPT, intermediate-pressure turbine LPT, low-pressure turbine CEP, condensate extraction pump LP, low pressure HP, high pressure FWP, feed-water pump.

Figure 8.5 Canadian supercritical water-cooled reactor core concept, (a) Reactor core, (b) crossover piece, and (c) bottom of fuel channel.

Figure 8.11 Cross-section views of the supercritical water-cooled reactor fuel assembly concept.

Safety system in a pressure vessel-type supercritical water-cooled reactor concept... 

Guzonas, D., Novotny, R., 2014. Supercritical water-cooled reactor materials — summary of research and open issues. Progress in Nuclear Energy 77, 361—372. 

International Atomic Energy Agency, September 2014. Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs). lAEA-TECDOC-1746, Vienna, Austria, 496 pp. Eree download from http //www-pub.iaea.org/ books/IAEABooks/10731/Heat-Transfer-Behaviour-and-Thermohydraulics-Code-Testing-for-Supercritical-Water-Cooled-Reactors-SCWRs. 

Novog, D., McGee, G., Rhodes, D., Yetisir, M., 2012. Safety concepts and systems of the Canadian SCWR. In Proc. 3rd China—Canada Joint Workshop on Supercritical Water-Cooled Reactors (CCSC-2012), Xi an, Shaanxi, China. 

Rohde, M., Peelers, J.W.R., PucciareUi, A., Kiss, A., Rao, Y.F., Onder, E.N., Miihlbauer, P., Batta, A., Hartig, M., Chatoorgoon, V., Thiele, R., Chang, D., Tavoularis, S., Novog, D., McClure, D., Gradecka, M., Takase, K., 2015. A blind, numerical benchmark study on supercritical water heat transfer experiments in a 7-rod bundle. In The 7th International Symposium on Supercritical Water-Cooled Reactors lSSCWR-7, March 15—18 paper 2044, Helsinki, Einland. 

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