IAEA international studies on irradiation embrittlement of reactor pressure vessel steels

Brumovsky, M; Steele, L E

Title: IAEA international studies on irradiation embrittlement of reactor pressure vessel steels

Full Record
Other Related Research

Abstract

In last 25 years, three phases a Co-operative Research Programme on Irradiation Embrittlement of Reactor Pressure Vessel Steels has been organized by the International Atomic Energy Agency. This programme started with eight countries in 1971 and finally 16 countries took part in phase III of the Programme in 1983. Several main efforts were put into preparation of the programme, but the principal task was concentrated on an international comparison of radiation damage characterization by different laboratories for steels of {open_quotes}old{close_quotes} (with high impurity contents) and {open_quotes}advanced{close_quotes} (with low impurity contents) types as well as on development of small scale fracture mechanics procedures applicable to reactor pressure vessel surveillance programmes. This year, a new programme has been opened, concentrated mostly on small scale fracture mechanics testing.

Authors:

Brumovsky, M ^[1]; Steele, L E ^[2]

Nuclear Research Institute Rez plc (Czech Republic)
Chief Scientific Investigator of the Programme, Springfield, VA (United States)

Publication Date:: Sat Feb 01 00:00:00 EST 1997

Research Org.:: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab. (BNL), Upton, NY (United States)

OSTI Identifier:: 467938

Report Number(s):: NUREG/CP-0157-VOL.2; CONF-9610202-Vol.2
ON: TI97004274; TRN: 97:008404

Resource Type:: Conference

Resource Relation:: Conference: 24. water reactor safety information meeting, Bethesda, MD (United States), 21-23 Oct 1996; Other Information: PBD: Feb 1997; Related Information: Is Part Of Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 443 p.

Country of Publication:: United States

Language:: English

Subject:: 22 NUCLEAR REACTOR TECHNOLOGY; 36 MATERIALS SCIENCE; PRESSURE VESSELS; EMBRITTLEMENT; RADIATION HARDENING; STEELS; IAEA; REACTORS; COORDINATED RESEARCH PROGRAMS

Citation Formats


                    Brumovsky, M, and Steele, L E. IAEA international studies on irradiation embrittlement of reactor pressure vessel steels.  United States: N. p., 1997. 
        Web.

Copy to clipboard


                    Brumovsky, M, & Steele, L E. IAEA international studies on irradiation embrittlement of reactor pressure vessel steels.  United States.

Copy to clipboard


                    Brumovsky, M, and Steele, L E. 1997.  
        "IAEA international studies on irradiation embrittlement of reactor pressure vessel steels".  United States.  https://www.osti.gov/servlets/purl/467938.

Copy to clipboard


                    
@article{osti_467938,

  title        = {IAEA international studies on irradiation embrittlement of reactor pressure vessel steels},

  author       = {Brumovsky, M and Steele, L E},

  abstractNote = {In last 25 years, three phases a Co-operative Research Programme on Irradiation Embrittlement of Reactor Pressure Vessel Steels has been organized by the International Atomic Energy Agency. This programme started with eight countries in 1971 and finally 16 countries took part in phase III of the Programme in 1983. Several main efforts were put into preparation of the programme, but the principal task was concentrated on an international comparison of radiation damage characterization by different laboratories for steels of {open_quotes}old{close_quotes} (with high impurity contents) and {open_quotes}advanced{close_quotes} (with low impurity contents) types as well as on development of small scale fracture mechanics procedures applicable to reactor pressure vessel surveillance programmes. This year, a new programme has been opened, concentrated mostly on small scale fracture mechanics testing.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/467938},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Sat Feb 01 00:00:00 EST 1997},

  month        = {Sat Feb 01 00:00:00 EST 1997}

}

Copy to clipboard

Conference:

View Conference (32.58 MB)

Other availability

Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

Irradiation embrittlement of pressure vessel steels: A review of activities in France

Conference Petrequin, P - Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)

Research on irradiation embrittlement in modern pressure vessel-steels was initiated at the French Atomic Energy Commission ten years ago. During this period many steel and welds were irradiated in the Triton and Siloe reactors; research was undertaken both independently and within the framework of research programs coordinated by the International Atomic Energy Agency. Mainly through tests of tensile and Charpy impact properties, the effects of chemical composition were studied, confirming the influence of copper and phosphorus and uncovering the surprisingly detrimental effect of nickel content. At the same time, new fracture mechanics testing procedures for irradiated materials were developed. Todaymore »« less
Neutron radiation embrittlement studies in support of continued operation, and validation by sampling of Magnox reactor steel pressure vessels and components

Conference Jones, R; Bolton, C

Magnox steel reactor pressure vessels differ significantly from US LWR vessels in terms of the type of steel used, as well as their operating environment (dose level, exposure temperature range, and neutron spectra). The large diameter ferritic steel vessels are constructed from C-Mn steel plates and forgings joined together with manual metal and submerged-arc welds which are stress-relieved. All Magnox vessels are now at least thirty years old and their continued operation is being vigorously pursued. Vessel surveillance and other programmes are summarized which support this objective. The current understanding of the roles of matrix irradiation damage, irradiation-enhanced copper impuritymore »« less
Full Text Available
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-HighFluence Conditions

Technical Report Odette, G.; Yamamoto, Takuya

Neutron embrittlement of reactor pressure vessels (RPVs) is an unresolved issue for light water reactor life extension, especially since transition temperature shifts (TTS) must be predicted for high 80-year fluence levels up to approximately 1,020 n/cm{sup 2}, far beyond the current surveillance database. Unfortunately, TTS may accelerate at high fluence, and may be further amplified by the formation of late blooming phases that result in severe embrittlement even in low-copper (Cu) steels. Embrittlement by this mechanism is a potentially significant degradation phenomenon that is not predicted by current regulatory models. This project will focus on accurately predicting transition temperature shiftsmore »« less
https://doi.org/10.2172/1084639

Full Text Available
Predictive Reactor Pressure Vessel Steel Irradiation Embrittlement Models: Issues and Opportunities

Journal Article Odette, George; Nanstad, Randy - Journal of Metals

Nuclear plant life extension to 80 years will require accurate predictions of neutron irradiation-induced increases in the ductile-brittle transition temperature ( T) of reactor pressure vessel (RPV) steels at high fluence conditions that are far outside the existing database. Remarkable progress in mechanistic understanding of irradiation embrittlement has led to physically motivated T correlation models that provide excellent statistical fi ts to the existing surveillance database. However, an important challenge is developing advanced embrittlement models for low fl ux-high fl uence conditions pertinent to extended life. These new models must also provide better treatment of key variables and variable combinationsmore »« less
https://doi.org/10.1007/s11837-009-0097-4
Physically based regression correlations of embrittlement data from reactor pressure vessel surveillance programs. Final report

Technical Report Perrin, J; Wullaert, R; Odette, G; ...

Physically based correlations for irradiation embrittlement, as manifested in shifts in Charpy V-Notch transition temperatures, were developed for plate and welds of light water reactor pressure vessel steels. The data was taken from power reactor surveillance programs contained in the Electric Power Research Institute Irradiated Pressure Vessel Steel Data Base. Alternate physical models, based on irradiation induced production of either small microvoids or copper precipitates acting as the primary source of embrittlement, were used to guide and interpret statistical least square regression analyses. Results demonstrated that the critical embrittlement variables are copper and nickel content and fluence; they suggested thatmore »« less

Similar Records