članak: 1 od 1  
Nuclear Technology and Radiation Protection
2005, vol. 20, br. 2, str. 45-60
jezik rada: engleski
naučni članak
doi:10.2298/NTRP0502045P

Studija korozije nuklearno čistih aluminijumskih legura u običnoj vodi - deo drugi
Institut za nuklearne nauke Vinča

e-adresa: mpesic@vin.bg.ac.yu

Sažetak

U okviru koordiniranog istraživačkog projekta Međunarodne agencije za atomsku energiju "Korozija aluminijumske košuljice ozračenog nuklearnog goriva istraživačkih reaktora u vodi", počevši od 2002. godine, izvršena su ispitivanja korozije legura nuklearno čistog aluminijuma u vodi bazena za odlaganje ozračenih gorivnih elemenata reaktora RA. Uzorci su bili izloženi uticaju vode u periodu od šest meseci do šest godina. Drugi deo studije obuhvata rezultate ispitivanja efekata korozije koji su dobijeni detaljnim vizuelnim i mikroskopskim ispitivanjima površine uzoraka i čini integralnu celinu sa prvim delom izveštaja o istraživanju, prikazanom u ovom časopisu.

Ključne reči

korozija; legure aluminijuma; SAV-1 legura; košuljica goriva; RA istraživački reaktor; obična voda

Reference

Idjaković, Z., Milonjić, S., Čupić, S. (2001) Quality of water from the pool, original containers and aluminum drums used for storage of spent nuclear fuel. Nuklearna tehnologija, 16, 2, str. 46-49
International Atomic Energy Agency (1997) Appendix II to IAEA Mission Report to VINČA Institute in February 1997. Vienna
International Atomic Energy Agency (2003) Corrosion of research reactor aluminum-clad spent fuel in water. Technical Report Series (TRS), Vienna, br. 418
Kopečni, M., Mataušek, M.V., Vukadin, Z., Maksin, T. (1996) Corrosion problems in the research reactor RA spent fuel storage pool. u: NATO AR Workshop Microbial Degradation Processes in Radio active Waste Repository and in Nuclear Fuel Storage Area, Budapest, Hungary
Krupchitskij, P.A. (1962) Use of ITEP heavy water reactor for nuclear physics and reactor physics research, review. Moscow: Institute of Theoretical and Experimental Physics, in Russian, Report br. 121
Maksin, T., Dobrijević, R., Iđaković, Z., Pešić, M. (2003) Corrosion of research reactor aluminum-clad spent fuel in water: Chemical and microbiological influence. u: 4th Yugoslav Nuclear Society International Conference-YUNSC 2002, Belgrade, September 30 - October 4, Proceedings on CD ROM, str. 389-392
Mataušek, M.V., Vukadin, Z., Pavlović, S., Maksin, T., Iđaković, Z., Marinković, N. (1997) Detection of fission products release in the research reactor RA spent fuel storage pool. u: Proceedings, Annual Meeting on Nuclear Technology, Aachen, Germany, str. 415-418
Mataušek, M.V., Marinković, N., Vukadin, Z. (1996) Research reactor RA at VINČA Institute of nuclear sciences: Ageing, refurbishment and irradiated fuel storage. u: Proceedings of the ENS Topical Meeting Research Facilities for the Future of Nuclear Energy, Brussels, Belgium: World Scientific Publishing, str. 69-78
Milošević, M., Martinc, R. (1978) Research reactor Ra: Technical characteristics and exploitation possibilities. u: Conference on Utilization of Nuclear Reactors in Yugoslavia, Yugoslavia, May 17-20, Belgrade, Proceedings, str. 81-97
Pešić, M.P., Maksin, T., Dobrijević, R., Iđaković, Z. (2003) Study on influence on corrosion at aluminum-clad spent fuel of research reactor transaction. u: The ENS 7th International Topical Meeting on Research Reactor Fuel Management - ENS RRFM'2003, Aix-En-Provence, France, March 9-12, str. 240-244
Pešić, M.P., Maksin, T., Dobrijević, R., Iđaković, Z. (2005) Corrosion of aluminum-clad spent fuel at RA research reactor. u: International Conference on Research Reactor Utilization, Safety, Decommissioning, Fuel and Waste Management, Santiago, Chile, November 10-14, Proceedings, Vienna, paper br. IAEA-CN-100-136, IAEA STI/PUB/1211, str. 677-688
Pešić, M.P., Maksin, T., Jordanov, G., Dobrijević, R. (2004) Corrosion of aluminum alloy test coupons in water of the spent fuel storage pool at the RA reactor. VINČA Bulletin, vol. 7, Supplement 2
Pešić, M.P., Maksin, T., Jordanov, G., Dobrijević, R. (2004) Corrosion of spent nuclear fuel aluminum cladding in ordinary water. u: Proceedings 26th International Meeting on Reduced Enrichment for Research and Test Reactors RERTR Vienna, November 7-12, USA: ANL, posted at RERTR Program web page www.rertr.anl.gov/RERTR26/pdf/P12-Pesic.pdf, to be published
Pešić, M.P., Maksin, T., Dobrijević, R., Jordanov, G., Iđaković, Z. (2005) Corrosion of aluminum-clad spent fuel in the research reactor RA storage pool. u: 3rd RCM on Corrosion of Research Reactor Aluminum-Clad Spent Fuel in Water (Phase II), IAEA, Vienna, December 12-16, Progress Report May 2004 - October 2005 on the IAEA CRP br. 11968/RBF Corrosion of Research Reactor Aluminum-Clad Spent Fuel in Water (Phase II)
Pešić, M.P. (1999) RB reactor: Lattices of 2%-enriched uranium elements in heavy water. u: International Handbook of Evaluated Criticality Safety Benchmark Experiments, Paris: OECD, NEA/NSC/DOC(95)03/IV, vol. IV, Contribution LEU-MET-THERM-002, OECD/NEA, str. 2-146
Pešić, M.P. (2000) RB reactor: Lattices of 80%-enriched uranium elements in heavy water. u: International Handbook of Evaluated Criticality Safety Benchmark Experiments, Paris: OECD, NEA/NSC/DOC(95)03/II, vol. II, Contribution HEU-COMP-THERM-017, OECD/NEA, str. 2-189
Pešić, M.P., Cupać, S., Vukadin, Z. (2000) Management of ageing research reactors in the Vinča institute. u: IAEA International Symposium on Research Reactor Utilization, Safety and Management, Lisbon, Portugal, September 6-10, 1999, Vienna, paper IAEA-SM-360/042P, CD ROM CSP-4/C, pp. 042P.1-042P.9
Pešić, M.P. (2000) Corrosion of irradiated fuel elements in storage pool of the RA research reactor. u: Contribution YU-001 at IAEA TCM on 1st Meeting of Coordinators for the Incident Reporting System for Research Reactors (IRSRR), November 20-24, Working Material - Limited Distribution, Vienna: IAEA, str. 80-89
Pešić, M.P., Plećaš, I., Pavlović, R., Pavlović, S., Šokčić-Kostić, M. (2001) An attempt to estimate gamma-ray dose rate from radioactive waste storage cask. u: Proceedings 5th International Symposium on Conditioning of Radioactive Operational & Decommissioning Wastes - KONTEC Berlin, March 28-30, pp. 754-762
Pešić, M.P., Kolundžija, V., Ljubenov, V., Cupać, S. (2001) Causes of extended shutdown state of RA research reactor in Vinča Institute. u: Regional Workshop on Extended Shut down and Decommissioning of Research Reactors, Proceedings, Riga, Latvia, November 26-30, to be published as the IAEA TECDOC, IAEA Technical Co-Operation Project RER/9/058: Safety Review of Research Reactor Facilities, str. 001-011
Pešić, M.P., Maksin, T. (2002) Corrosion of aluminum-clad spent fuel in the research reactor RA storage pool. u: The IAEA 1st RCM on Corrosion of Research Reactor Aluminum-Clad Spent Fuel in Water (Phase II), Buenos Aires, Argentina, October 28 - November 1, The IAEA CRP br. 11968/RBF Corrosion of Research Reactor Aluminum-Clad Spent Fuel in Water (Phase II), CD ROM edition
Pešić, M.P., Maksin, T.N., Jordanov, G., Dobrijević, R., Iđaković, Z.E. (2004) Studija korozije nuklearno čistih aluminijumskih legura u običnoj vodi, deo prvi. Nuclear Technology and Radiation Protection, vol. 19, br. 2, str. 77-93
Pešić, M.P., Maksin, T., Dobrijević, R., Jordanov, G., Iđaković, Z. (2004) Corrosion of aluminum-clad spent fuel in the research reactor RA storage pool. u: The IAEA 2nd RCM on Corrosion of Research Reactor Aluminum-Clad Spent Fuel in Water (Phase II), Almaty, Kazakhstan, June 14-18, Progress Report on the IAEA CRP br. 11968/RBF Corrosion of Research Reactor Aluminum-Clad Spent Fuel in Water (Phase II), CD ROM edition, str. 001-037
Šotić, O., i dr. (1984) Research reactor RA: Operation and maintenance report in 1984. Belgrade: Boris Kidrič Institute of Nuclear Sciences, Internal Report, in Serbian
The Boris Kidrič Institute of Nuclear Sciences (1960-1984) Annual reports of the RA reactor operation. Belgrade: Institute of Nuclear Sciences 'Vinča', in Serbian
The Boris Kidrič Institute of Nuclear Sciences (1984) Study on spent fuel storage pool of the reactor RA. Belgrade: Institute of Nuclear Sciences 'Vinča', Internal Report Z5.A1.4, in Serbian