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Neutron and Thermal Embrittlement of RPV Steels: An Overview

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Because the reactor pressure vessel (RPV) represents the first structural line of defense against the release of radiation to the public, the design and fabrication of the RPV for any nuclear reactor facility is performed at very high standards in accordance with consensus codes that are based on mechanical and physical properties of the steels used to construct the vessel. Nuclear RPVs may weigh up to 800 tons with wall thicknesses up to approximately 330 mm and are clad on the inside with stainless-steel weld metal and given a final post-weld heat treatment. The RPV is a unique structural component in that it operates under high pressures and temperatures and is exposed to relatively high neutron radiation. Although typical RPV steels and welds have excellent fracture toughness at room temperature and above when put into service, the degrading effects of high-energy neutron irradiation can cause levels of irradiation-induced embrittlement in radiation-sensitive materials of concern for the structural integrity of the RPV. In recent decades, remarkable progress has been made in developing a mechanistic understanding of irradiation embrittlement. This progress includes developing physically based and statistically calibrated models of Charpy V-notch-indexed transition temperature shifts based on results from RPV surveillance programs complemented by significant results from comprehensive research experiments performed in test reactors. In addition, advances in elastic-plastic fracture mechanics allow for a relatively small number of relatively small specimens to characterize the fracture toughness of RPV steels with statistical confidence. This paper presents a review of the primary mechanical properties, test procedures, examples of applicable codes and standards, and specimen types used to characterize RPV steels and welds, the effects of neutron irradiation on those most relevant mechanical properties, and a brief review of the effects of thermal aging on RPV materials. The paper closes with a summary.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1875336
Country of Publication:
United States
Language:
English

References (51)

Theoretical Physics in the Metallurgical Laboratory of Chicago November 1946
A physically-based correlation of irradiation-induced transition temperature shifts for RPV steels February 2013
Embrittlement of nuclear reactor pressure vessels July 2001
Recent progress in understanding reactor pressure vessel steel embrittlement June 1998
Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following Thermal Aging, Irradiation, and Thermal Annealing January 2001
The Effect of Residual Elements on the Response of Selected Pressure-Vessel Steels and Weldments to Irradiation at 550°F January 1969
Radiation Induced Microstructural Evolution in Reactor Pressure Vessel Steels January 1994
Atom probe tomography characterizations of high nickel, low copper surveillance RPV welds irradiated to high fluences June 2013
In-Service Embrittlement of the Pressure Vessel Welds at the Doel I And II Nuclear Power Plants January 1996
On the Composition and Structure of Nanoprecipitates in Irradiated Pressure Vessel Steels January 1996
Radiation embrittlement and thermal annealing behavior of CrNiMo reactor pressure vessel materials October 1995
Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects January 2004
Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views October 2010
Irradiation effects on thermal conductivity of a light-water reactor pressure vessel steel April 1983
Direct Use of the Fracture Toughness Master Curve in ASME Code, Section XI, Applications July 2013
Chemical composition and RT[sub NDT] determinations for Midland weld WF-70 December 1992
Charpy Impact Test Results on Five Materials and NIST Verification Specimens Using Instrumented 2-mm and 8-mm Strikers January 1995
Tensile and impact properties of thick-section plate and weldments August 1971
Effects of Irradiation and Thermal Annealing on Fracture Toughness of the Midland Reactor Weld WF-70 January 2000
Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens January 2012
A review of Crack Arrest Concepts for the Assessment of Pressure Vessel Integrity January 2002
An updated correlation for crack-arrest fracture toughness for nuclear reactor pressure vessel steels June 2005
Statistical Analyses of Fracture Toughness Results for Two Irradiated High-Copper Welds January 1992
Radiation Stability of WWER-440 Vessel Materials January 1993
Extended analysis of VVER-1000 surveillance data August 2002
Composition influences and interactions in radiation sensitivity of reactor vessel steels November 1985
An Analysis of Radiation Effects in Model A533B Pressure Vessel Steels Containing Copper, Phosphorus and Nickel Additions January 1999
Effects of Irradiation Temperature on Charpy and Tensile Properties of High-Copper, Low Upper-Shelf, Submerged-Arc Welds January 1994
Analysis of the Ductile-to-Brittle Transition Temperature Shift in a Commercial Power Plant With High Nickel Containing Weld Material January 2007
Atom probe tomography characterization of neutron irradiated surveillance samples from the R. E. Ginna reactor pressure vessel March 2016
An APFIM study of the microstructure of a ferrite alloy after high fluence neutron irradiation April 1993
Evolution of the nanostructure of VVER-1000 RPV materials under neutron irradiation and post irradiation annealing April 2009
Fracture Toughness Characterization of Irradiated Low Upper-Shelf Welds February 2018
Relationship Between Irradiation Hardening and Embrittlement of Pressure Vessel Steels February 2018
A model for PWR pressure vessel embrittlement January 1987
The Modelling of Irradiation Embrittlement in Submerged-Arc Welds January 1996
Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209 000 H at 260°C January 2006
Precipitation in long term thermally aged high copper, high nickel model RPV steel welds May 2012
Review of thermal ageing data and its application to operating reactor pressure vessels January 1993
Thermal ageing effects in structural steels October 1988
Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels January 2004
Temper Embrittlement, Irradiation Induced Phosphorus Segregation and Implications for Post-Irradiation Annealing of Reactor Pressure Vessels January 1999
Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels January 2008
Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels July 2006
Combined effects of phosphorus segregation and partial intergranular fracture on the ductile–brittle transition temperature in structural alloy steels April 2011
Effect of thermal aging on fracture toughness of RPV steel November 1993
Evaluation of Thermal-Aged Plates, Forgings, and Submerged-Arc Weld Metals January 1994
Mechanical property and neutron spectral analyses of the big rock point reactor pressure vessel April 1970
Effect of thermal ageing on impact ductility of the nuclear reactor pressure vessel steel SA533B and its weld metal August 1987
Interaction of neutron and thermal environmental factors in the embrittlement of selected structural alloys for advanced reactor applications April 1970
U.S. High Fluence Power Reactor Surveillance Data—Past and Future January 2014