Shelemetiev V.M., Martynov P.N., Storozhenko A.N., Chernov M.E., Ulyanov V.V. 
A.I. Leypunsky Institute of Physics and Power Engineering, Obninsk, Russia
 
Currently,  the  new  nuclear  power  plants  (NPP)  are  developed  in  Russian  Federation  wherein  are used different liquid metal, sodium and heavy lead-based liquid-metal, as coolants. In respect to these NPP control tools of hydrogen and oxygen in gas environment are required. For sodium-cooled NPP the usage of hydrogen and oxygen control tools is required for solution of the security problems at a steam leak and depressurization of cooling circuit. For NPP with a heavy liquid-metal coolant the hydrogen  control  tools  are  required  is  not  only  for  control  of  possible  a  steam  leak  in  steam generator, but also for conducting the technological actions using hydrogen for cleaning of a coolant and the first cooling circuit. Oxygen control is required to diagnose the development of the various negative processes (occurrence of depressurization of cooling circuit, oxygen and air leaks, etc.) at the early stages. Also, oxygen control allows to perform indirect identification of the thermodynamic activity  of  oxygen  in  the  melt,  the  beginning  and  the  degree  of  completion  of  the  oxidation  of  the molten liquid metal. In depends on the type of a coolant, control hydrogen and oxygen tools meet the different requirements for sensitivity and response speed. For example, the most important parameter for hydrogen and oxygen control tools in sodium-cooled NPP is the response speed and for NPP with the lead-based coolant is hydrogen sensitivity.
IPPE  has  a  great  many-years'  experience  in  the  development  of  various  control  devices  both  for liquid  and  gaseous  media.  The  most  promising  oxygen  and  hydrogen  control  tools  are  solid electrolyte sensors. Also conductometric sensors (the principle of operation of which is based on the ability  of  palladium  alloys  reversibly  absorb  hydrogen  gas  from  the  surrounding  environment  and thus  change  its  electrical  resistance  depending  on  the  partial  pressure  of  hydrogen)  show  good results in control of hydrogen.
At the moment, these devices have been applied to the existing nuclear power plants in Russia and abroad, in the hydrogen safety systems for beyond design basis accidents. 
 1.  Blokhin V.A., Budylov E.G., Velikanovich R.I. et al. The experience of development and operation of solid-electrolyte  activity  meters  of  oxygen  in  lead-bismuth  coolant.  Trudy  konferentsii  "Tyazhelye zhidkometallicheskie  teplonositeli  v  yadernykh  tekhnologiyakh"  [Proceedings  of  the  Conference  on Heavy Liquid Metal Coolants in Nuclear Technologies]. Obninsk, 1999, p.631. (In Russian). 
2.  Martynov P.N., Chernov M.E., Storozhenko A.N. et al. The development pf new generation systems of oxygen and hydrogen control in the circuits with Pb and Pb-Bi coolants on the basis of solid-electrolyte oxygen  sensors  of  capsule  type.  Trudy  konferentsii  "Tyazhelye  zhidkometallicheskie  teplonositeli  v yadernykh tekhnologiyakh"  [Proceedings of the Conference on Heavy Liquid Metal Coolants in Nuclear Technologies]. Obninsk, 2008, p.57. (In Russian). 
3.  Martynov  P.N.,  Chernov  M.E.,  Storozhenko  A.N.,  Shelemetiev  V.M.,  Sadovnichiy R.P.  Oxygen  and hydrogen  control  sensors  in  liquid  metal  coolants  of  NPP  on  the  basis  of  solid-electrolyte  nanostructured oxygen sensors. Novye promyshlennye tekhnologii – New Industrial Technologies, 2008, no.4, pp.36-39. (In Russian). 
4.  Bogdanov S.V. Razrabotka i eksperimental'noe obosnovanie oborudovaniya sistemy kontrolya vodorodnoy bezopasnosti AES.  Diss. kand. tekhn. nauk  [Development and experimental substantiation of equipment of hydrogen safety control system of NPP. Cand. tech.sci.diss.]. Obninsk, IPPE Publ., 2009.  
5.  Legkikh  A.Yu.,  Martynov  P.N.,  Askhadullin  R.Sh.,  Simakov  A.A.  Devices  for  providing  the  predetermined  oxygen  mode  in  the  primary  circuit  of  nuclear  power facilities  with  a  heavy  liquid  metal coolant. Trudy Nauchno-tekhnicheskoy konferentsii molodykh spetsialistov po yadernym energeticheskim ustanovkam  [Proceedings  of  the  Scientific  and  Technical  Conference  of  young  specialists  in  nuclear power facilities]. Podolsk, 2012. (In Russian). 
6.  Komlev  O.G.,  Tormyshev  I.V.,  Toshinsky  G.I.  SVBR-100:  coolant  potential  energy  and  NPP  safety. Bezopasnost' yadernykh tekhnologiy i okruzhayushchey sredy.  –  Safety of nuclear technologies and the environment, 2012, no.2. (In Russian). 
7.  Verkhovodko S.Z., Zamukov V.V. The experience of designing, operation and disposal of nuclear power facilities  with  a  liquid  metal  coolant  for  "Alpha"  submarines.  Trudy  konferentsii  "Tyazhelye zhidkometallicheskie  teplonositeli  v  yadernoy  tekhnologii"  [Proceedings  of  the  Conference  on  Heavy Liquid Metal Coolants in Nuclear Technology]. Obninsk, 1999, p.18. (In Russian). 
8.  Gromov  B.F.,  Grigoriev  O.G.,  Dedul  A.V.,  Zrodnikov  A.V.,  Toshinsky G.I.,  Chitaikin V.I.  The application of the technology of marine reactors with a liquid metal coolant in the civil nuclear power engineering  of  Russia.  Trudy  konferentsii  "Tyazhelye  zhidkometallicheskie  teplonositeli  v  yadernoy tekhnologii"  [Proceedings of the Conference on Heavy Liquid Metal Coolants in Nuclear Technology]. Obninsk, 1999, p.44. (In Russian). 
9.  Gromov B.F., Toshinsky G.I., Chekunov V.V., Orlov Yu.I. et al. The development of reactors with leadbismuth  coolant  for  submarines.  Brief  history.  The  summarized  results  of  the  operation.  Trudy konferentsii "Tyazhelye zhidkometallicheskie teplonositeli v yadernoy tekhnologii"  [Proceedings of the Conference on Heavy Liquid Metal Coolants in Nuclear Technology]. Obninsk, 1999, p.14. (In Russian). 
10.  Chernov  E.I.,  Baboshin  A.V.,  Chernov  M.E.  High-temperature  gas  analyzers  on  the  basis  of  solidelectrolyte  sensors  (the  experience  of  development  and  putting  in  production).  Trudy  konferentsii "Toplivnye elementy i energeticheskie ustanovki na ikh osnove"  [Proceedings  of the Conference on Fuel Elements and Fuel Element-Based Power Facilities]. Obninsk, 2000. (In Russian). 
11.  Kochetkova  E.A.,  Leshkov  V.V., Kornilov  V.P., Kalyakin  S.G., Drobyshev  A.V., Skomorokhova  S.N., Bogdanov  S.V.  Electroconductometric  gas  analyzers:  multi-year  experience  of  their  operation.  Trudy mezhdunarodnoy  konferentsii  "Teplofizicheskie  aspekty  bezopasnosti  VVER"  [Proceedings  of  the International Conference on  Thermophysical Aspects of Safety of VVER Reactors]. Obninsk, 2007.  (In Russian).