Systematic approach to predicting corrosion of zirconium alloys in the water coolant of nuclear reactors

Author:

Kritskii V. G.,Berezina I. G.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering

Reference27 articles.

1. Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants, IAEA-TECDOC-996, January, 1998.

2. Y-D. Kim, S-M. Bae, and K. Torrill, “Evaluation of several effects on PWR cladding corrosion performance and modeling,” in: The Intern. Topical Meeting on Light Water Reactor Fuel Performance-2000, USA, April 10–13, 2000, CD-ROM ISBN 0-89448-656X, ANS Order No. 700280.

3. V. G. Kritsky, N. G. Petrik, I. G. Berezina, and V. V. Doilnitsina, “Effect of water chemistry and fuel operation parameters on Zr + 1%Nb cladding corrosion,” in: Proc. Techn. Com. Meeting IAEA Influence of Water Chemistry on Fuel Cladding Behavior, Czech Republic, October 1993, IAEA-TECDEC-927, IAEA, Vienna (1997), pp. 23–43.

4. I. G. Berezina, “Development of methods for lowering the corrosion of cladding zirconium alloy and increasing the operational reliability of RBMK-1000 fuel assemblies and storage reliability as spent nuclear fuel,” Author’s Abstract of Candidate’s Dissertation in Technical Sciences, All-Russia Research and Design Institute of Integrated Power Technology (VNIPIET), St. Petersburg (1998).

5. I. G. Berezina, V. G. Kritskii, and P. S. Styazhkin, “Characteristics the corrosion behavior of the alloy Zr + 1%Nb in the coolant of a nuclear power plant with RBMK-1000,” Teploenergetika, No. 7, 62–67 (1998).

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