Authors & Affiliations
Makhin V.M.
Experimental and Design Organization "GIDROPRESS", Podolsk, Russia
Makhin V.M. - Chief Expert, Dr. Sci. (Tech.), OKB "GIDROPRESS".
Contacts: 21, Ordzhonikidze st., Podolsk, Moscow region, Russia, 142103. Tel.: (903) 670-99-71; e-mail:
Abstract
The article deals with design of reactors with nuclear steam superheating under subcritical pressure of the coolant (BORAX–V, BONUS and Pathfinder-foreign reactors, AMB-100 and AMB-200 at Beloyarsk NPP, RF) and their operation experience. The mentioned reactors have not become prot otypes of future power reactors but their operation experience is useful for designing the reactor plants of the next generation “Generation-4” with supercritical coolant parameters (SCWR) which differ from the reactor plants of the 20th century in the coolant increased pressure (?>?crit), first of all. It was noted that boiling reactor VK-50 with coolant natural circulation in the core was designed not only for study of operation peculiarities of reactors with coolant boiling in the core but also for study of processes with steam “nuclear” superheating. In practice, for ~50 years, the reactor is used only under conditions of boiling in the core. The database obtained with the VK-50 reactor is of interest for verification of computer codes applicable for connected neutron-physical and thermal-hydraulic calculations typical for SCWR. Experience of design and operation of VK-50 is important for SCWR development.
Keywords
supercritical water-cooled reactor, experimental justification, boiling vessel reactor, operation experience
Article Text (PDF, in Russian)
1. Sokolov I.N., Gritskov V.I., Bogdanovich P.N., et. al. Opytnyy reaktor korpusnogo tipa dlya izucheniya kipeniya i peregreva para [The test reactor of vessel type for studying boiling water and reheat of vapour]. Trudy 3 Zhenevskoy konferentsii po mirnomu ispol'zovaniyu atomnoy energii [Proc. 3th Int. Conf. on the Peaceful Uses of Atomic Energy]. Geneva, 1964, p.237-247.
2. ?aljakin S.G., Kirillov P.L., Baranaev J.D. et. al. Perspektivy razrabotki innovatsionnogo vodookhlazhdaemogo yadernogo reaktora so sverkhkriticheskimi parametrami teplonositelya [Development perspectives of an innovative water-cooled nuclear reactor with coolant supercritical parameters]. Teploenergetika – Thermal Engineering, 2014, no. 8, pp. 13-19.
3. Kochetkov L.A. The first Beloyarsk Plants. Available at: http://atominfo.ru/newsh/o0800.htm. (accessed 14.08.2016)
4. Kochetkov L.A. K istorii pervoy ocheredi Beloyarskoy AES. Istoriya atomnoy energetiki, vol. 1. [To a first-order history of the Beloyarsk atomic power plant. A history of atomic engineering, vol. 1]. Moscow, IzdAT Publ., 2001. pp. 117-133.
5. Saltanov E. Steam-Reheat Option for Supercritical-Water-Cooled Reactors. Diss. master's degree. Ontario, Nuclear Engineering University of Ontario Institute of Technology Publ., 2010. 196 ?.
6. Shamanov N.P., Pejch N.N., Djadik A.N. Sudovye yadernye paroproizvodyashchie ustanovki [Nuclearpowered installations for ships]. Leningrad, Sudoctroenie Publ., 1990. 368 p.
7. Sokolov I.N., Kramerov A.J., Kulikov E.V., et. al. Opytnyy reaktor korpusnogo tipa i nekotorye rezul'taty ego energopuska [The test reactor of vessel type and some results of operational in-use life]. Teploenergetika – Thermal Engineering, 1968, no. 5, pp. 62-67.
8. Kirillov P.L. Spravochnik po teplogidravlicheskim raschetam v yadernoy energetike. Tom 2. Yadernye reaktory, teploobmenniki, parogeneratory [Handbook on thermal and hydrodynamic calculations in nuclear power. Volume 2. Nuclear reactors, heat exchangers, steam generators]. Moscow, IzdAT Publ., 2013. 688 p.
9. Eshcherkin V.M., Letnitski U.A. Istoriya reaktornoy ustanovki VK-50 [History of reactor V?-50]. Dimitrovgrad, SSC RIAR Publ., 2006.
10. Antonov S.N., Semidotski I.I., Turtaev N.P., Shmelev V.E. Kharakteristiki aktivnoy zony reaktora VK-50 s povyshennym vodno-toplivnym otnosheniem [Characteristics of reactor core V?-50 with increased water-fuel relation]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2005, no. 3, pp. 3-11.
11. S?dulin V.P. Turbinno-neytronnyy metod izmereniya raskhoda teplonositelya v teplovyde-lyayushchikh sborkakh korpusnogo kipyashchego reaktora VK-50 [“Turbine-neutron” flowmeter for measurement of coolant flow in boiling reactor V?-50 fuel assembly]. Voprosy atomnoy nauki i tekhniki. Ser. Obespechenie bezopasnosti AES – Problems of atomic science and technology. Series: Safety assurance of NPP, 2009, no. 25, pp. 126-134.
12. Antonov S.N., Semidotski I.I., Turtaev N.P., et. al. Modernizatsiya aktivnoy zony reaktora VK-50 [Engineering and technical modernization of an active zone of reactor V?-50]. Trudy 4 MNTK "Obespechenie bezopasnosti AES s VVER" [Proc. 4th ISTC “Safety of a nuclear power station with VVER”]. Podolsk, 2005, pp. 165.
13. Antonov S.N., Vaneev J.E., Svjatkina N.A., Shirokov S.V., et. al. Primenenie kodov dlya raschetnogo soprovozhdeniya ekspluatatsii reaktora VK-50 [Application of codes for settlement support of reactor V?-50 operation]. Trudy 4 MNTK "Obespechenie bezopasnosti AES s VVER" [Proc. 4th ISTC “Safety of a nuclear power plant with VVER”]. Podolsk, 2005, pp. 155-156.
14. Spasskov V.P., Dragunov Yu.G., Ryzhov S.B., et. al. Printsipy sozdaniya AES maloy moshchnosti s kipyashchim korpusnym reaktorom [Creation principles of small sized atomic power station with a boiling reactor]. Trudy 2 MNTK "Obespechenie bezopasnosti AES s VVER" [Proc. 2th ISTC “Safety of a nuclear power station with VVER”]. Podolsk, 2001, 115 p.
15. Antonov S.N., Eshcherkin V.M., Turtaev N.P., et. al. Opyt ekspluatatsii RU VK-50 dlya proektirovaniya ATETs s korpusnym kipyashchim reaktorom [VK-50 operating experience for small sized atomic power station with a boiling reactor designing]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2005, no. 3, pp. 46-57.
16. Kurski A.S., Eshcherkin V.M., Svjatkin M.N., et. al. Kompleksnoe ispol'zovanie tekhnicheskikh resheniy, otrabotannykh pri 45-letney ekspluatatsii energobloka s reaktorom VK-50, dlya sozdaniya sovremennykh ATETs s reaktorami VK-100 v regional'noy atomnoy energetike [Complex use of the technical fulfilled at 45-years operation reactor VK-50 decisions, for creation modern NPP with reactors VK-100]. Moscow, Science Publ., 2011, pp. 214-226.
17. Kurski A.S, Kalygin V.V., Semidotski I.I. Perspektivy atomnoy teplofikatsii v Rossii [Perspectives of nuclear central heating for using in Russia]. Teploenergetika – Thermal Engineering, 2012, no. 5, pp. 3-9.
18. Kurski A.S, Eshcherkin V.M., Kalygin V.V. Korpusnye kipyashchie reaktory dlya atomnoy teplofikatsii [Vessel boiling reactors for nuclear central heating]. Atomnaya energiya – Atomic Energy, 2011, vol. 111, no. 5, pp. 297-302.
19. Kurski A.S. Obosnovanie bezopasnosti korpusnogo kipyashchego reaktora pri krupnykh techakh kontura teplonositelya na primere reaktora VK-50 [Safety substantiation of a small boiling reactor at LB LOCA by example of reactor V?-50 test]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2013, no. 4, pp. 100-106.
20. Semidotski I.I. Raschetno-eksperimental'noe obosnovanie bezopasnosti issledovatel'skogo reaktora VK-50. Diss. cand. tech. nauk [Theoretical and experimental evidence of research reactor V?-50 safety. Cand. Sci. (Tech.) Diss.]. Moscow, NRNU MEPhI Publ., 2007.
21. Semidotski I.I., Kurski A.S. Osobennosti rezhima s poterey pitatel'noy vody v reaktore VK-50 [Feature of a loss-of-flow (LOF) for a reactor VK-50 feedwater]. Trudy 7 MNTK "Obespechenie bezopas-nosti AES s VVER" [Proc. 7th ISTC "Safety of the atomic power station with VVER"]. Podolsk, 2009, p. 126.
22. Konjashov V.V., Krasnov A.M. Opyt ekspluatatsii RU VK-50 s negermetichnymi tvelami [Operating experience reactor V?-50 with vented fuel elements]. Dimitrovgrad, 2000, vol. 3, pp. 47-60.
23. Krasnov A.M., Konjashov V.V., Gordetskii K.A. Metodika rascheta vykhod radioaktivnykh produktov deleniya iz negermetichnykh tvelov vodookhlazhdaemogo reaktora [Method of fission product definition from water-cooled reactor vented fuel elements]. Dimitrovgrad, 2000, vol. 3, pp. 61-81.
24. Antonov S.N., Makhin V.M., Semidotski I.I., Shmelev V.E. Razrabotka bazy dannykh eksperimental'nykh rezhimov issledovatel'skogo reaktora VK-50 [Database of research reactor V?-50 experimental modes]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2005, no. 1, pp. 63-68.
25. Semidotski I.I., Antonov S.N., Koshkina S.P., Makhin V.M., Shmelev ?.?. O primenenii eksperimental'nykh rezhimov VK-50 dlya modelirovaniya evolyutsionnykh i innovatsionnykh yadernykh vodookhlazhdaemykh ustanovok [About application of experimental modes V?-50 for modelling evolutionary and innovative nuclear water-cooled installations]. Trudy nauchno-tekhnicheskoy konferentsii, posvyashchennoy 50-letiyu NIIAR [Proc. sci. conf. devoted to the 50th anniversary of Atomic Reactors]. Dimitrovgrad, 2006.
26. Semidotskiy I.I., Antonov S.N., Zhitelev V.A., Kotov N.P., Makhin V.M. Otsenka vozmozhnostey korrelyatsionnogo metoda dlya opredeleniya parametrov dvukhfaznogo teplonositelya v TVS reaktora VK-50 po dannym vnutrizonnykh datchikov pryamogo zaryada [Assessment of the correlation method for determining the parameters of two-phase coolant in a VK-50 core]. Trudy OAO OKB «GIDROPRESS» 2008, Vypusk 9 v 3 chastyakh [Proc. OKB "GIDROPRESS" 2008, Issue 9, in 3 parts]. Podolsk, 2009, Part 2, p. 425-430.
27. Semidotski I.I., Antonov S.N., Zhitelev V.A., Kotov N.P., Makhin V.M., Kebadze B.V., Shurupov V.A. Otsenka vozmozhnostey korrelyatsionnogo metoda dlya opredeleniya parametrov dvukhfaznogo teplonositelya v aktivnoy zone VK-50 [Assessment of the correlation method for determining the parameters of two-phase coolant in a VK-50 core]. Atomnaya energiya – Atomic Energy, 2011, vol. 110, no. 5, pp. 316-322.
28. Semidotski I.I. Opyt primeneniya teplogidravlicheskogo koda RELAP5/MOD3.2 dlya modelirovaniya staticheskikh i dinamicheskikh rezhimov korpusnogo kipyashchego reaktora VK-50 [Experience of application thermohydrodynamic code RELAP5/MOD3.2 for modelling static and dynamic modes of boiling reactor V?-50]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2005, vol. 1, pp. 28-38.
29. Semidotski I.I., Makhin V.M. Vliyanie prostranstvennoy gidrodinamiki i stokhasticheskikh effektov na ustoychivost' raschetnoy modeli korpusnogo kipyashchego reaktora VK-50 na osnove teplogidravlicheskogo koda RELAP5/MOD3.3. [Influence of spatial hydrodynamics and stochastic effects on stability of boiling reactor V?-50 settlement model on a basis code RELAP5/MOD3.3]. Voprosy atomnoy nauki i tekhniki. Seriya: Obespechenie bezopasnosti AES – Problems of atomic science and technology. Series: Safety assurance of NPP, 2007, no. 19, pp. 101-112.
30. Semidotski I.I., Makhin V.M., Zhitelev V.A., Antonov S.N., et. al. Identifikatsiya dinamicheskikh kharakteristik kodov RELAP5 i KORSAR na chastote osnovnogo rezonansa rabochego rezhima korpusnogo kipyashchego reaktora VK-50 [Identification of dynamic characteristics of codes RELAP5 and the CORSAR on frequency of boiling reactor VK-50 the basic resonance]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2007, no. 1, pp. 98-103.
31. Filjakin G.V., Goncharenko J.D., Shamardin V.K., Ostrovski Z.E. Izuchenie svoystv materiala chekhla kassety reaktora VK-50 posle 30 let ekspluatatsii [Material properties studying of a cover of reactor V?-50 FA after 30 years of operation]. Trudy 6 MNTK "Obespechenie bezopasnosti AES s VVER" [Proc. 6th ISTC "Safety of nuclear power plants with VVER"]. Podolsk, 2011, 33 p.
32. Grachev A.F., Eshcherkin V.M., Shmelev V.E., et. al. Sozdanie sistemy lokalizatsii vybrosov para cherez predokhranitel'nye klapany reaktora VK-50 [Creation of water steam emissions system of localization through safety valves of reactor VK-50]. Trudy inzhenerno-tekhnicheskoy konferentsii "Bezopasnost' issledovatel'skikh reaktorov" [Proc. Tech. Conf. "Safety of research reactors"]. Dimitrovgrad, 1998, pp. 67-81.
33. Kurski A.S., Tulnikov D.F., Jakshin E.K., Kizin V.D. Sozdanie avtomatizirovannoy sistemy kontrolya vybrosov RV pri avariyakh na IYaU VK-50 [Creation of the automated monitoring system of waste gas system at a reactor core disruptive accident on RNU V?-50]. Otchet NIIAR – Report RIAR. Dimitrovgrad, 2006, pp. 43-44.
34. Chechetkin Yu.V., Yakshin E.K., Eshcherkin V.M. Ochistka radioaktivnykh gazoobraznykh otkhodov AES [Cleaning of radioactive gaseous waste of the NPP]. Moscow, Energoatomizdat Publ., 1986. 152 p.
35. Chechetkin J.V., Jakshin E.K., Kobzar I.G., Kizin V.D. Raspredelenie radioaktivnosti po konturam AES VK-50 [Contours radioactivity distribution of atomic power station VK-50]. Trudy Simp. "Vodnye rezhimy vodo-vodyanykh reaktorov, radiatsionnyy kontrol' teplonositeley i sredstva snizheniya radiatsionnoy opasnosti teplonositeley" [Proc. Symp. "Water treatment and reactor chemistry control of water-water reactors, the dosimetry control of coolants and methods of decrease in radiating danger of reactors"]. Gera, 1968, pp. 79-83.
36. Kurski A.S. Metody kontrolya germetichnosti obolochek tvelov na korpusnom kipyashchem reaktore VK-50 [Monitoring methods of fractional fuel cladding defect on boiling reactor VK-50]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2013, no.4, pp. 93-99.
37. Zabelin A.I., Gordienko N.I., Yakovleva E.D. Osobennosti vodnogo rezhima AES VK-50 [Features of a water modes of atomic power station VK-50]. Trudy simpoziuma "Vodnye rezhimy vodo-vodyanykh reaktorov, radiatsionnyy kontrol' teplonositeley i sredstva snizheniya radiatsionnoy opasnosti teplonositeley" [Proc. Symp. "Water treatment and reactor chemistry control of water-water reactors, the dosimetry control of coolants and methods of decrease in radiating danger of reactors"]. Gera, 1968, pp. 72-78.
38. Shmelev V.E., Zabelin A.I. Radioliz teplonositelya v kipyashchem reaktore VK-50 [Water coolant radioliz in boiling reactor VK-50]. Atomnaya energiya – Atomic Energy, 1986, vol. 60, no. 4, pp. 248-251.
39. Baranaev Y.D., Glebov A.P., Kirillov P.L. Neutronic Characteristics of a 30 MWt SCW Experimental Reactor: From Water-Cooled Power Reactor Technology to a Direct Cycle Nuclear Reactor with Supercritical Water Parameters and Fast Neutron Spectrum. Report ISSCWR-6. Shenzhen, 2013.
40. Berkovich V.Ya., Glebov A.P., Churkin A.N., Kirillov P.L., Makhin V.M., Mokhov V.A., Nikitenko M.P. Conceptual proposals for plant-prototype of VVER-SCP reactor. Proc. 7th Int. Symp. on Supercritical Water-Cooled Reactors ISSCWR-7. Helsinki, 2015;
Makhin V.M., Mokhov V.A., Berkovich V.Ya., et. al. Kontseptual'nye predlozheniya po stenduprototipu reaktora VVER-SKD [Conceptual proposals for plant – prototype of VVER-SCP reactor]. Tyazheloe mashinostroenie – Russian Journal of Heavy Machinery, 2015, no. 6, pp. 40-45.
UDC 621.039.524.441