journal article·2000-06

Influence of irradiation on KISCC of Zr–1%Nb claddings

Yu.K Bibilashvili, A.V Medvedev, B.I Nesterov, V.V Novikov, V.N Golovanov, S.G Eremin, A.D Yurtchenko

Journal of Nuclear Materials· Volume 280· Issue 1
Publisher page

Abstract

Abstract Experimental results on iodine induced stress corrosion cracking (SCC) in irradiated claddings from Zr–1%Nb alloy are analyzed. Fatigue cracks were grown at their inner surfaces. The irradiation was carried on in the liquid sodium cooled BOR-60 to the fluence not lower than 10 22 n/cm 2 . The SCC-test was carried at 350°C, in argon gas at constant pressure and iodine surface concentration of 0.2 mg/cm 2 . The threshold stress intensity factor for the irradiated Zr–1%Nb claddings was determined to be ∼2.0 MPa√m.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Thermodynamic and Structural Properties of Metals and Alloys

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (12)

Show source-provided references
1. Bibilashvili · J. Nucl. Mater. · 1995 · 224 · 30710.1016/0022-3115(95)00114-X ↗
2. A.V. Nikulina, V.A. Markelov, M.M. Peregud, Y.K. Bibilashvili, V.A. Kotrekhov, A.F. Lositsky, N.V. Kuzmenko, Y.P. Shevnin, V.K. Shamardin, G.P. Kobylyansky, A.E. Novoselov, Zirconium Alloy E635 as a Material for Fuel Rod Cladding and Other Components of VVER and RBMK Cores. in: E.R. Bradley, G.P. Sabol (Eds.), Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, Am. Soc. Testing and Mater., 1996, pp. 785–80410.1520/STP16201S ↗
3. Newman · Trans. ASME Ser. J J. Pressure Vessel Technol. · 1980 · 102 · 34210.1115/1.3263343 ↗
4. Y. Murakami (Editor-in-chief), Stress Intensity Factors Handbook, Jpn. Soc. Mater. Sci., Pergamon, Oxford, 1987
5. Schuster · Nucl. Eng. Design. · 1995 · 156 · 34310.1016/0029-5493(94)00958-2 ↗
6. D. Cubicciotti, R.L. Jones, EPRI-NASA Cooperative Project on Stress Corrosion Cracking of Zircaloys/EPRI-NP-717, SAI International, Menlo Park, CA, (USA), March 197810.2172/5127487 ↗
7. Pettersson · J. Nucl. Mater. · 1982 · 107 · 11710.1016/0022-3115(82)90564-5 ↗
8. Norring · J. Nucl. Mater. · 1982 · 105 · 23110.1016/0022-3115(82)90379-8 ↗
9. V.N. Shishov, A.V. Nikulina, V.A. Markelov, M.M. Peregud, A.M. Kozlov, S.A. Averin, S.A. Kolbenkov, A.E. Novoselov. Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys. in: E.R. Bradley, G.P. Sabol (Eds.), Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, Am. Soc. Testing and Mater., 1996, pp. 603–62210.1520/STP16192S ↗
10. B. Cox, J.C. Wood, Iodine Induced Cracking of Zircalloy Fuel Cladding, in: Fd.C.S. Tedmon Jr. (Ed.), Proceedings of the Electrochemical Society Symposium on Corrosion Problems in Energy Conversion and Generation, ECS, New York, 1974, p. 275
11. V.V. Novikov, Yu.N. Sokurskyi, Yu.K. Bibilashvili, M.V. Vladimirova, A.S. Sotnikov, Yu.V. Bobkov, I.A. Kulikov, Study of Crack Initiation and Propagation Mechanism on SCC of Zr–1%Nb VVER Fuels. in: Proceedings of the Internatinal Conference on Radiation Materials Science, Alushta, USSR, 22–25 May 1990, vol. 8 , p. 158
12. Kubo · J. Nucl. Mater. · 1985 · 132 · 110.1016/0022-3115(85)90386-1 ↗