On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models

Author:

Odette G.R.,Yamamoto T.,Williams T.J.,Nanstad R.K.,English C.A.

Funder

EPRI

NRC

DOE-ORNL

EDF

CRIEPI

British Energy

Rolls-Royce

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference237 articles.

1. Multiscale-multiphysics modeling of Materials : embrittlement of pressure-vessel steels;Odette;MRS Bull.,2001

2. Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants;Soneda,2014

3. Radiation Damage of Reactor Pressure Vessel Steels in R. Konings (4), Comprehensive Nuclear Materials;Hyde,2012

4. Low-Alloy Steels Low Alloy Steels, Ch 10, Structural Alloys for Nuclear Energy Applications;Williams,2019

5. Integrity of reactor pressure vessels in nuclear power plants: assessment of irradiation embrittlement effects in reactor pressure vessel steels, chapter 2;Brumovsky;IAEA Nucl. Energy Ser.,2009

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