Zirconium alloys in nuclear power engineering

Author:

Nikulina A. V.

Publisher

Springer Science and Business Media LLC

Subject

Metals and Alloys,Mechanics of Materials,Condensed Matter Physics

Reference8 articles.

1. A. V. Nikulina, “Zirconium alloys for core elements of reactors with water under pressure,” Metalloved. Term. Obrab. Met., No. 8, 7–13 (2003).

2. M. I. Solonin, Yu. K. Bibilashvili, A. V. Nikulina, et al., “Zirconium alloy for fuel rod assemblies of new generation of VVÉR,” in: Int. Topical Meeting “Top Fuel’99,” Avignon, France, 13–15 Sept., 1999 (1999), pp. 165–177.

3. V. F. Kon’kov, A. V. Nikulina, M. M. Peregud, et al., “Factors affecting external and internal reactor corrosion of zirconium claddings of fuel elements,” in: Int. Workshop of Water Chemistry and Intrareactor Corrosion, Czech Republic, 1999, IAEA-TECDOC-1128 (1999), pp. 103–113.

4. V. F. Konovalov, V. L. Molchanov, M. L. Solonin, et al., “Nuclear fuel for power reactors,” in: Nuclear Fuel Cycle, Coll. Reports [in Russian], Minatom RF, Moscow (2000), pp. 89–100.

5. P. V. Shebaldov, M. M. Peregud, A. V. Nikulina, et al., “E110 alloy cladding tube properties and their interrelation with alloy structure-phase condition and impurity content,” in: 12th Int. Symp. “Zr in the Nuclear Industry,” ASTM, STP-1354 (2000), pp. 545–558.

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