Water Cooled Reactor VVER SCP (preliminary elaboration)


Issue of journal:



Brief review on the state of nuclear power engineering on 01.01.2013 is presented here. The
project of nuclear reactor cooled with water at supercritical pressure – VVER SCP based on operation
experience of such nuclear reactors as WWER, PWR, BWR, RBMK (more than 14000 reactor–years), long
term experience of thermoelectric stations on fossil fuel, where steam at supercritical and super–
super–critical pressures is used. Advantages of such type of reactor are listed as well as scientific and
technical problems to be solved. Preliminary estimations in accordance with INPRO approach are
made. Knowledge accumulated during last 10 years in this field allows reactor concept to be specified
and the project of experimental reactor of small power to be launched.

1. WNA Reactor Database 01.01.2013.
2. The Future of the Nuclear Fuel Cycle. Massachusetts Institute of Technology. 2011.
3. Alekseev P.N., Asmolov V.G., Gagarinskij A.Ju. i dr. O strategii razvitija jadernoj jenergetiki Rossii do 2050 g. // Atomnaja jenergija. 2011. T. 111. Vyp. 4. – S. 183–196. Sm. takzhe knigu s tem zhe nazvaniem – M.: Izd–vo NIC «Kurchatovskij institut». 2012.
4. Dragunov Ju.G., Melihov V.V., Smirnov V.S., Chernecov N.G. Tehnicheskie reshenija i jetapy razrabotki RU BREST–OD–300. // Atomnaja jenergija. 2012. T. 113. Vyp. 1. S. 58–64.
5. Adamov E.O., Dzhalavjan A.V., Lopatkin D.V. i dr. Konceptual'nye polozhenija strategii razvitija jadernoj jenergetiki Rossii do 2100 g. // Atomnaja jenergija. 2012. T. 112. Vyp. 6. S. 319–331.
6. Vvedenie v ispol'zovanie metodologii INPRO dlja ocenki jaderno–jenergeticheskih sistem. – Izd–vo MAGATJe.№ NP–T–1.12. – Vena. 2011. Jel. tekst na russk. jaz. http://www–pub.iaea.org/MTCD/publications/PDF/Pub1478R_web.pdf Sm. takzhe IAEA–TECDOC–1434.
7. Takeda T., Shimazu Y. Reviev of Safety Improvement on Sodium–cooled Fast Reactors after Fukushima Accident. – Natural Science. V. 4. Special ISSUE. 2012. Pp. 921–935.
8. Mac Pherson H. The Molten Salt Reactor Adventure. – Nucl. Sci. Eng. 1985. V.90. No 4. Pp. 374– 380.
9. Proc. International Conference GLOBAL–2011. Toward and Over the Fukushima Daiichi Accident. – Japan. Makuhari. 2011.
10. Beaty R.L., Gowin P.J., Phillips J.R., Ocenic E.L. The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Paper on European Nuclear Conference (ENC 2012). – Manchester. UK. 9–12 December. 2012.
11. Le Coz P. et al. Sodium–cooled Fast Reactor the ASTRID Plant Project. – Proc. ICAPP 2011. Nice. France. 2–5 May. 2011.
12. Beils S. et al. Safety Approach and R&D Program for Future French Sodium–cooled Reactors. – Jour. Nucl. Sci. and Techn. 2011. V.48. No 4.
13. Schulenberg T. Supercritical Water–cooled Reactor (SCWR). – Report on the Working Group IAEA on SCWR Programme. – Mississauga. Toronto. Canada.19–23 September. 2011.
14. Bychkov A. Fast Reactors and Closed Fuel Cycle: Safety Technologies and Sustainability. – Proc. of IAEA – IAEA Int. Workshop on Prevention and Mitigation of Severe Accidents in Sodium–cooled Fast Reactors. Japan. Tsuruga. 11–13 June. 2012. (Cit. by [7]).
15. INPRO: Mezhdunarodnyj proekt po innovacionnym jadernym reaktoram i toplivnym ciklam. http://www.atomic–energy.ru/articles/2012/08/22/35443
16. Ingersoll D.T. Status of Physics and Safety Analyses for the Liquid–salt–cooled, Very High – Temperature Reactor (LS – VHTR). – ORNL/TM – 2005/218 (Dec. 2005). (Cit. by [7]).
17. Corradini M. Supercritical Flow and Heat Transfer in Advanced Reactor. – Nucl. Tech. 2013. V. 181. No 1. Pp. 2–10.
18. Aoto K. Uto N., Sakamoto Y. et al. Design Study and R&D Progress on Japan Sodium–cooled Fast Reactor. – Jour. Nucl. Sci. and Techn. 2011. V.48. Pp. 463–471.
19. Duffey R.B., Pioro I., Zhou X. et al. Supercritical Water–cooled Nuclear Reactors Current and Future Concepts. – Proc. ICONE–16, paper 48869. USA. Orlando. 11–15 May. 2008.
20. Dragunov Ju.G., Ryzhov S.B., Nikitenko M.P. i dr. Vodoohlazhdaemye reaktory so sverhkriticheskimi parametrami (VVJeR SKD) – perspektivnye reaktory 4–go pokolenija. – Doklad na VIII Konferencii po reaktornomu materialovedeniju. – NIIAR. Dimitrovgrad. 2007.
21. Starfinger J., Shulenberg T., Marsault P. et al. European Research Activities within the Project: “High Performance Light Water Reactor Phase 2”. – Proc. ICAPP–07, paper 7146. Nice. France. 13– 18 May. 2007. См. также работу этих авторов «High Performance Light Water Reactor–design and Analyses». – KIT Scientific Publishing. 2012.
22. Ryzhov S.B., Mohov V.A., Nikitenko M.P. et al. Concept of a Single–circuit RP with Vessel Type SCWR. – Report on 8–th Int. Symposium (ISSCWR+5). Paper PO76. – Vancouver. Canada. 13–16 March. 2011.

For full access to information log in or register here.