Development Programs on Irradiation Embrittlement of Low Alloy Pressure Vessel Steels in the Federal Republic of Germany

2009 ◽  
pp. 555-555-10
Author(s):  
D Pachur ◽  
G Sievers
Keyword(s):  
Federal Republic ◽  
Pressure Vessel ◽  
Federal Republic Of Germany ◽  
Development Programs ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels

Irradiation Embrittlement of Advanced Pressure Vessel Steels

2008 ◽  
pp. 408-408-12
Author(s):  
KS Sivaramakrishnan ◽  
S Chatterjee ◽  
S Anantharaman ◽  
UK Viswanathan ◽  
KS Balakrishnan ◽  
...  
Keyword(s):  
Pressure Vessel ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels

Estimation of Master Curve Based RTTo Reference Temperature From CVN Data

2005 ◽  
Author(s):  
Kim R. W. Wallin ◽  
Gerhard Nagel ◽  
Elisabeth Keim ◽  
Dieter Siegele
Keyword(s):  
Fracture Toughness ◽  
Pressure Vessel ◽  
Brittle Failure ◽  
Master Curve ◽  
Simple Relation ◽  
Systematic Evaluation ◽  
Data Sets ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Asme Code

The ASME code cases N-629 and N-631 permits the use of a Master Curve-based index temperature (RTTo ≡ T0 + 19.4°C) as an alternative to traditional RTNDT-based methods of positioning the ASME KIc, and KIR curves. This approach was adopted to enable use of Master Curve technology without requiring the wholesale changes to the structure of the ASME Code that would be needed to use all aspects of Master Curve technology. For the brittle failure analysis considering irradiation embrittlement additionally a procedure to predict the adjustment of fracture toughness for EOL from irradiation surveillance results must be available as by NRC R.G. 1.99 Rev. 2 e.g.: ART = Initial RTNDT + ΔRTNDT + Margin. The conservatism of this procedure when RTNDT is replaced by RTTo is investigated for western nuclear grade pressure vessel steels and their welds. Based on a systematic evaluation of nearly 100 different irradiated material data sets, a simple relation between RTToirr, RTToref and ΔT41JRG is proposed. The relation makes use of the R.G. 1.99 Rev. 2 and enables the minimizing of margins, necessary for conventional correlations based on temperature shifts. As an example, the method is used to assess the RTTo as a function of fluence for several German pressure vessel steels and corresponding welds. It is shown that the method is robust and well suited for codification.

scholarly journals Institutional approaches of the Federal Republic of Germany to post-conflict recovery, stabilization and development programs implementation

2021 ◽  
Vol 94 ◽  
pp. 03008
Author(s):  
Sergey Tishkov ◽  
Valentina Ogneva ◽  
Irina Tishkova
Keyword(s):  
Federal Republic ◽  
Development Policy ◽  
Methodological Approach ◽  
Practical Experience ◽  
Federal Republic Of Germany ◽  
Development Programs ◽  
Security Measures ◽  
Post Conflict ◽  
Foreign Office ◽  
Loan Corporation

The article studies practical approaches of the Federal Republic of Germany to the implementation of post-conflict recovery, stabilization and development programs. Noted that Germany is actively pursuing unilateral and joint programs for global sustainable development or specialized programs in different parts of the world. This good performance became possible due to a new German methodological approach based on complex and flexible usage of diplomacy, development policy and security measures. The well build institutional system under coordination of the Federal Foreign Office and the Federal Ministry for Economic Cooperation and Development is able to fulfill difficult tasks successfully. This point is illustrated by practical experience of the German Agency for International Cooperation, the Reconstruction Loan Corporation and the German Civil Peace Service. The article concludes that Germany achieved significant results in post-conflict recovery, stabilization and development activities because of bringing together efforts of different actors.

scholarly journals Mechanisms and Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels.

1998 ◽  
Vol 47 (11) ◽  
pp. 1112-1118
Author(s):  
Sumio MURAKAMI ◽  
Atsushi MIYAZAKI ◽  
Kazuki TSUGIHASHI ◽  
Mamoru MIZUNO ◽  
Morio JINCHO ◽  
...  
Keyword(s):  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

scholarly journals Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels

1997 ◽  
Vol 46 (2) ◽  
pp. 124-130
Author(s):  
Sumio MURAKAMI ◽  
Kazuki TSUGIHASHI ◽  
Atsushi MIYAZAKI ◽  
Morio JINCHO ◽  
Tetsuya SUZUKI
Keyword(s):  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Irradiation Embrittlement ◽  
Pressure Vessel Steels ◽  
Reactor Pressure
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