Comparison of Маster curve with normative method of estimating WWER-1000 reactor pressure vessel metal fracture toughness

Author:

,Revka V.M.,Chyrko L.I.

Abstract

The paper considers the generalized temperature dependence of the stress intensity factor KJC in the WWER-1000 reactor pressure vessel metal, which was derived based on the surveillance test data for fracture toughness. The consistency of the shape of the Master curve and 95 % upper and lower confidence bounds with the experimental dependence of crack resistance parameters on temperature was studied. From the point of view of the level of conservatism and acceptability, a comparison of the normative curves of fracture toughness according to NPRR (Nuclear Power Rules and Regulations) G-7-002-86 and SOU NNEGC (Standard of organization of Ukraine, National Nuclear Energy Generating Company) 177:2019 with a 5 % confidence bound of the Master curve was carried out. The possibility of using RT0 temperature as a temperature index instead of TK for the normative fracture toughness curve of SOU NNEGC 177:2019 was considered.

Publisher

National Academy of Sciences of Ukraine (Co. LTD Ukrinformnauka) (Publications)

Reference11 articles.

1. 1. V. Revka, E. Grynik, L. Chyrko The use of master curve method for statistical re-evaluation of surveillance test data for WWER-1000 reactor pressure vessels. Strength Mat. 42 (2010) 705. https://doi.org/10.1007/s11223-010-9257-6

2. 2. Standard Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range. ASTM E1921-19. ASTM Book of Standards. Vol. 03.01:2019. https://doi.org/10.1520/E1921-19

3. 3. Use of Fracture Toughness Test data to Establish Reference Temperature for Pressure Retaining Materials. Section XI, Division 1. Code Case N 629 (New York, ASME, 1999). https://cstools.asme.org/csconnect/CodeCaseForm.cfm?Action=View&CaseNumber=2496&NoToolbar=yes

4. 4. Master Curve Fracture Toughness Application for Point Beach Nuclear Plant Unit 2. Consulting Report, ATI-021-030-2003-1 (January 2003).

5. 5. B.-S. Lee. Life extension programme for Kori-1 nuclear power plant. In: Proceedings of Regional workshop on Structure, Systems and Components Integrity. Belo Horizonte, Brazil, 23 - 26 June 2009.

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