Behavior of Grade 91 material specimens with and without defect at elevated temperature

Author:

Lee Hyeong-Yeon,Kim Woo-Gon,Kim Nak-Hyun

Funder

National Research Foundation of Korea

nternational Research & Development Program Foundation NRF grant

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference18 articles.

1. Conceptual design report of SFR Demonstration Reactor of 600MWe capacity;Kim,2012

2. Evaluation of creep-fatigue damage for Hot Gas Duct structure of the NHDD Plant;Lee;J Press Vessel Technol Trans ASME,2010

3. Rules for construction of nuclear power plant components, div. 1, subsection NH, class 1 components in elevated temperature service;ASME Boiler and Pressure Vessel Code,2013

4. Reactor components, its auxiliary systems and supports, Section III Tome 1 Subsection B;RCC-MRx,2012

5. Guide for prevention of fast fracture;RCC-MRx,2012

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