Comparative Analysis of the Effect of Technological Defects on the Strength of Е110 Alloy Fuel Cladding under Stress Corrosion Cracking

Authors: Sotnikov A.S. Published: 23.12.2019
Published in issue: #6(129)/2019  

DOI: 10.18698/0236-3941-2019-6-138-150

Category: Power, Metallurgic and Chemical Engineering | Chapter: Nuclear Reactor Engineering, Machines, Assemblies, and Nuclear Materials Technology  
Keywords: E110 zirconium alloy, fuel cladding, corrosion, stress, internal surface, technological defect, stress corrosion cracking

The article provides comparative analysis of data on the influence of technological defects on the long-term strength of fuel cladding ∅ 9,1 × 0,65 mm of alloy E110 (Э110) under conditions of stress-corrosion cracking in the environment of iodine, obtained in recent years. The experimental results of stress corrosion cracking of fuel cladding in iodine environment are compared with the test data of fuel cladding made of alloy E110 in the state of delivery, with artificial and technological defects on the inner surface. On the basis of experimental results of stress-corrosion cracking research of irradiation fuel cladding × 9,1 × 0,65 mm E110 of the alloy E110 it is recommended to use the value of the threshold stress as σscc = ∼ 280 MPa at the temperature T = 350 °C in environment of iodine (iodine concentration ∼ 0,2 mg/sm2)


[1] Lavrenyuk P.I., Dolgov A.B. [Prospective development lines of nuclear fuel for Russian atomic power plants]. Dokl. nauch.-tekh. konf. AO "TVEL": Yadernoe toplivo novogo pokoleniya dlya AES [Proc. Sc.-Tech. Conf AO "TVEL": Nuclear fuel of new generation for atomic power plants]. Moscow, AO "VNIINM" Publ., 2016 (in Russ.).

[2] Kuznetsov V.I., Krupkin A.V. [Development of related START-RAPT code and development of fuel element 3D modelling]. Dokl. nauch.-tekh. konf. AO "TVEL": Yadernoe toplivo novogo pokoleniya dlya AES [Proc. Sc.-Tech. Conf. AO "TVEL": Nuclear fuel of new generation for atomic power plants]. Moscow, AO "VNIINM" Publ., 2016 (in Russ.).

[3] Markov D.V., Pavlov S.V. [VVER and RBMK fuel of new generation: results of postirradiation examination, substantiation of reliability and working capacity]. Dokl. IX Ross. konf. po reaktornomu materialovedeniyu [Proc. IX Russ. Conf. on Reactor Material Engineering]. Dimitrovgrad, OAO "GNTs NIIAR", 2009 (in Russ.).

[4] Filin V.M., Novikov V.V., Sotnikov A.S., et al. The features of the influence of high burn-up internal fuel rod chemistry on stress corrosion cracking behaviour of the fuel claddings. Atomnaya energiya, 2013, vol. 115, no. 5, pp. 260--264 (in Russ.).

[5] Sotnikov A.S. Vliyanie yoda i yodida tseziya na korrozionnoe rastreskivanie pod napryazheniem obolochek iz splava Zr--1%Nb tvelov vodookhlazhdaemykh reaktorov. Dis. kand. tekh. nauk [Effect of iodine and cesium iodide on corrosion cracking of fuel element shells made from Zr--1%-alloy for water-cooled reactor under tension. Cand. Sc. (Eng.) Diss.]. Moscow, VNIINM Publ., 1989.

[6] Nikulin S.A., Rozhnov A.B. Corrosion cracking of zirconium cladding tubes (a review). I. Methods of study and mechanisms of fracture. Met. Sc. Heat. Treat., 2005, vol. 47, no. 1-2, pp. 71--79. DOI: 10.1007/s11041-005-0034

[7] Programnoe sredstvo START-3A [START-3A software]. Moscow, NTTs YaRB Rostekhnadzora Publ., 2013.

[8] Materialy po otkazam tvelov vodookhlazhdaemykh reaktorov. MAGATE, 1996 (in Russ.).

[9] Anghel C., Alvarez A.M., Lysell G., at el. An out-of-pile method to investigateiodine --- induced SCC of irradiated cladding. Proc. Top Fuel, 2009, Paper 2179. DOI: 10.1051/rgn/20102057

[10] Solonin V.I., Sotnikov A.S., Sergienko I.R. Development of mechanical loading device for testing the zirconium cladding under the pellet-cladding interaction conditions. Nauka i obrazovanie: nauchnoe izdanie MGTU im N.E. Baumana [Science and Education: Scientific Publication], 2014, no. 6 (in Russ.). DOI: 10.7463/0614.0715393

[11] Sotnikov A.S., Novikov V.V., Solonin V.I., et al. The laboratory equipment for mechanical testing of fuel cladding in condition of modeling pellet-clad interaction (PCI). Voprosy atomnoy nauki i tekhniki. Seriya: Materialovedenie i novye materialy, 2014, no. 1, pp. 21--30 (in Russ.).