Machine learning modeling of irradiation embrittlement in low alloy steel of nuclear power plants-Reference-Cited by-同舟云学术

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Machine learning modeling of irradiation embrittlement in low alloy steel of nuclear power plants

Published:2021-12 Issue:12 Volume:53 Page:4022-4032
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Lee Gyeong-Geun^ORCID,Kim Min-Chul,Lee Bong-Sang

Funder

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Regulatory Guide 1.99 Revision 1: Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessels Materials,1977

2. Regulatory Guide 1.99 Revision 2: Radiation Embrittlement of Reactor Vessel Materials,1977

3. NUREG/CR-6551: Improved Embrittlement Correlations for Reactor Pressure Vessel Steels;Eason,1998

4. NP-3319: Physically Based Regression Correlations of Embrittlement Data from Reactor Pressure Vessel Surveillance Programs;Eason,1998

5. JEAC4201-2007: Method of Surveillance Tests for Structural Materials of Nuclear Reactors,2007

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