Russian Federation
Russian Federation
Russian Federation
The article summarizes and presents an analysis of international experience in solving the problem of formation of radioisotopes of antimony in the primary circuit of reactor facilities of various types. The experience of twelve countries operating power units with VVER, PWR, BWR, and PHWR reactors in identifying sources of stable antimony isotopes in the primary circuit and implementing measures to eliminate them is reviewed. The recommendations of international organizations and requirements of normative documents of individual countries established to limit the formation of radioisotopes of antimony in the primary circuit and their implementation in new designs of reactor facilities of foreign design have been analyzed. A list of the main possible sources of antimony in the primary circuit is determined.
nuclear power plant, primary circuit coolant (PCC), radioisotope, antimony, activation, deposits, specific activity
1. Organisation for Economic Co-operation and Development, Radiation Protection Aspects of Primary Water Chemistry and Source-Term Management Report, NEA/CRPPH/R(2014)2.
2. Karl-Heinz Neeb. The Radiochemistry of Nuclear Power Plants with Light Water Reactors. Walter de Gruyter, 1997.
3. Povarov V.P., Gusev I.N., Rosnovskiy S.V., Ivanov E.A. i dr. Opyt vnedreniya sistem ionoselektivnoy ochistki trapnyh vod ot radionuklidov na blokah 1-2 NVAS-2//ANRI. 2020. №№4(103).
4. Sharov D.A., Semenovyh A.S., Ivanov E.A., Arzhatkin V.G., Krutskih D.A., Marakulin I.I. i dr. Opredelenie istochnikov postupleniya radioizotopov sur'my v trapnye vody pri ekspluatacii reaktornoy ustanovki VVER-1200//Yadernaya i radiacionnaya bezopasnost'. 2023. № 2(108). S. 82-96.
5. Optimization of Water Chemistry to Ensure Reliable Water Reactor Fuel Performance at High Burnup and in Ageing Plant (FUWAC). IAEA-TECDOC-1666, 2011.
6. Iv. Dobrevski, N. Zaharieva, K. Minkova, G. Michaylov, P. Penev, N. Gerchev. The Main Conditions Ensured Problemless Implementation of 235U High Enriched Fuel in Kozloduy NPP (Bulgaria) - WWER-1000 Units. 8 international conference on WWER fuel performance, modelling and experimental support. Helena Resort (Bulgaria). 28 September - 2 October 2009.
7. Iv. Dobrevski. WWER-1000 Coolant Chemistry Improvement by Extended Fuel Cycles. Additional information. IAEA-TECDOC-1666 companion CD, 2011.
8. Review of VVER Primary Water Chemistry and the Potential for its Use in PWRs. Potassium Hydroxide and/or Ammonia Based Water Chemistries. Technical Report. 1003382. Final Report. EPRI, September 2002.
9. H. Stockert, H. Emmert and Ch. Meyer zu Schwabedissen, VGB-Kraftwerkstechnik, no. 67(3), 1987, 288.
10. F. Bottcher, S. Riehm, M. Bolz, A. Speck, «Impact of load follow operation on the chemistry of the primary and secondary circuit of a pressurized water reactor», VGB Power Tech, vol. 93(5), pp. 50-55, July 2013.
11. Report of the operational safety review team (OSART) mission to the Neckarwestheim Nuclear Power Plant. Germany. 8 to 24 october 2007 and follow-up visit 11 to 14 may 2009. IAEA-NSNI/ OSART/07/142F.
12. Proceedings of the workshop on how to prevent recurring events more effectively. Boettstein, Switzerland, 6-8 March 2002. NEA/CSNI/R(2002)25.
13. Occupational Exposures at Nuclear Power Plants: Thirteenth Annual Report of the ISOE Programme, 2003. NEA no. 5414, OECD 2005.
14. Y. Dundar, S. Odar, K. Streit, H. Allsop, D. Guzonas. Application of KWU antimony removal process at Gentilly-2. International conference on water chemistry of nuclear reactor systems. Bournemouth (United Kingdom), 13-17 October, 1996.
15. D.G. Miller, D.A. Guzonas, R. Laporte, T.A. Dereski, R.A. Speranzini. Controlling radiation fields in CANDU reactors using chemical decontamination technologies. COG, 97-472-I; AECL (Series), 11852. Chalk River Laboratories, 1997.
16. Xu Mingxia. Major Activated Corrosion Products Cobalt, Silver and Antimony in the Primary Coolant of PWR Power Plants. Nuclear Safety (Beijing), no. 1, 2012, pp. 1-9.
17. Bo Dua, Suping Yu, Qingkai Zhaoa, Xuzhou Cheng, Jiying Wei, Xuan Zhao, «The speciation analysis of colloids in the primary coolant in nuclear power plant», Radiation Physics and Chemistry, no. 159, pp. 81-88, 2019.
18. Fang Lan, Xu Chunyan, Liu Xinhua, Wu Hao, «Source Term Control Measures for Activation/ corrosion Products in PWR Primary System», Radiation protection (Taiyuan), vol. 32, no.№1, January 2012.
19. Fu Pengtao, Dai Mingliang, Zhu Zhaowen, et al. Study of annual tritium discharge in pressurized water reactor based on historical data. High Power Laser and Particle Beams, vol. 34, no. 2. Feb 2022.
20. Carola A. Gregorich. Staying Ahead of Radiation Field Changes - How to Know Your Plant’s Source Term. PWR RP/ALARA Association. 2016 Summer Meeting, San Diego, CA. June 13-15, 2016.
21. A.D. Miller, T.P. Hillmer. Decontamination and disposal of Sb-124 at Palo Verde Nuclear Generating Station. Vol. I: Low-level waste, vp, 1988, pp. 505-508; University of Arizona Nuclear Engineering Dept, Tucson, AZ (USA). Waste management ‘88: symposium on radioactive waste management; Tucson, AZ (USA); 28 February - 3 March 1988.
22. Szabolcs Osvath, Zsuzsa Molnar, Judit Groska & Nóra Vajda, «Determination of 125Sb in nuclear power plant wastes», Journal of Radioanalytical and Nuclear Chemistry, vol. 307, pp. 761-764, 2016.
23. S. Jaervimaeki, R. Kvarnstroem, M. Maekinen, K. Maekelae. Actions taken to significantly reduce activity levels on primary loop surfaces at Loviisa NPP. Proceedings of nuclear plant chemistry conference. Sapporo, 2014.
24. 2017 ISOE Country Reports. NEA/ISOE(2018)11REV9.
25. Finnish report on nuclear safety. Finnish 8th national report as referred to in Article 5 of the Convention on Nuclear Safety. STUK-B 237, July, 2019.
26. Tea Bilic Zabric, Bojan Tomic, Klas Lundgren and Mats Sjoberg. Inquiry into the radiological consequences of power uprates at light-water rectors worldwide. SSI rapport: 2007:07.
27. S. Hakkinen. (2020). Impurities in LWR fuel and structural materials. VTT Technical Research Centre of Finland. VTT Research Report No. VTT-R-00184-20.
28. H. Provens. Primary circuit contamination in nuclear power plants: contribution to occupational exposure. European IRPA Congress 2002. Florence (Italy), 8-11 Octobtr 2002.
29. Lannick Elain. Contribution à l’optimisation de la purification chimique et radiochimique du fluide primaire des centrales nucléaires à eau sous pression. école centrale des arts et manufactures. «Ecole Centrale Paris», 2004.
30. G. Gaudard, B. Gilles, F. Mesnage, F. Cattant. Improvements of primary coolant shutdown chemistry and reactor coolant system cleanup. International conference on water chemistry in nuclear reactors systems - operation optimisation and new developments. Avignon, France, 22-26 April 2002.
31. M. Berger, J.L. Bretelle, A. Rocher. Impact of main radiological pollutants on contamination risks (ALARA) optimisation of physico-chemical environment and retention techniques during operation and shutdown. Third ISOE European Workshop. Portoroz, Slovenia, 17-19 April 2002.
32. K. Petrova, L. Urbancik, V. Kulich, D. Fuchsova. Factors Contributing to the Reduction of Occupational Exposures at Dukovany NPP. European Technical Center ISOE Symposia. Turku (Finland), June 2008.
33. Occupational Exposures at Nuclear Power Plants. Eighteenth Annual Report of the ISOE Programme, 2008. NEA № 6826. OECD, 2010.
34. Sicherheitstechnische Stellungnahme zur Periodischen Sicherheitsüberprüfung 2017 des Kernkraftwerks Beznau. ENSI 14/3025. Brugg, November 2021.
35. Sicherheitstechnische Stellungnahme zur Periodischen Sicherheitsüberprüfung 2012 des Kernkraftwerks Beznau. ENSI 14/2244. Brugg, Dezember 2016.
36. Madelene Johansson. Ringhals - Operational Experience on Silver and Antimony related to doses. ISOE International Symposium.Brussels, 1-3 June 2016.
37. Ok Sung Lee. Nuclear power plants generate radioactive waste within the liquid antimony (Sb) and removal study. Dissertation. Chosun University, 2016.
38. Occupational Radiological Protection Principles and Criteria for Designing New Nuclear Power Plants. Nuclear Energy Agency (NEA) № 6975, Organisation for Economic Co-operation and Development (OECD), 2010.
39. Chemistry Programme for Water Cooled Nuclear Power Plants. IAEA Safety Standards Series № SSG-13. Specific Safety Guide, 2011.
40. Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants. IAEA Safety Standards Series № SSG-56. Specific Safety Guide, 2020.
41. HAD 102/08-2020. Design of Reactor Coolant System and Related System in Nuclear Power Plant. Chinese Industry Standard.
42. Direktiv YVL 7.18. Strålsäkerhetsfrågor som skall beaktas vid planering av ett kärnkraftverk. STUK, 26.9.2003.
43. TBM. TECHNICAL REGULATIONS FOR MECHANICAL EQUIPMENT. Edition 7, 2015-12-08.
44. Nuclear directorate. Generic design assessment - new civil reactor build. Step 3 reactor chemistry assessment of the Westinghouse AP1000. HSE Nuclear Directorate Division 6 assessment report № AR 09/035.
45. Generic Design Assessment - New Civil Reactor Build. Step 4 Reactor Chemistry Assessment of the Westinghouse AP1000 Reactor. Office for Nuclear Regulation. Assessment Report: ONR-GDAAR- 11-008. Revision 0. 11 November 2011.
46. APR1400. Design control document tier 2. Chapter 12. Radiation protection. APR1400-K-X-FS-13002. Revision 0. September 2013.
47. UK HPR1000 GDA. Pre-Construction Safety Report Chapter 22. Radiological Protection. HPR/GDA/PCSR/0022. Rev:001.
48. Avis/IRSN № 2011-51. EPR - FA3 - Instruction anticipée en vue de l’autorisation de mise en service Definitions du terme source utilise et methodologie d’evaluation.
49. Generic Design Assessment - New Civil Reactor Build. Step 4 Radiological Protection Assessment of the EDF and AREVA UK EPR Reactor. Assessment Report: ONR-GDA-AR-11-025. Revision 0. 16 November 2011.
50. Sizewell C Project. Radioactive Substances Regulation (RSR) Permit Application. Appendix A. Support Document A1 - Environment Case. 100198762. Revision 01.
51. HPC PCSR3. Sub-chapter 19.2. Definition of Radioactive Sources in the Primary Circuit. HPC-NNBOSL-U0-000-RES-100107.
52. Reshenie Nauchno-tehnicheskogo Soveta № 5 «Zamykayuschaya stadiya yadernogo toplivnogo cikla» Gosudarstvennoy korporacii po atomnoy energii «Rosatom» ot 21.12.2022 «Razrabotka tehnologiy obrascheniya s ZhRO na blokah AES».
