Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel

Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel PDF Author: PN. Randall
Publisher:
ISBN:
Category : Annealing
Languages : en
Pages : 12

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Book Description
This paper is in several parts: the first presents an overview of research activities sponsored by the U.S. Nuclear Regulatory Commission (NRC) on neutron irradiation embrittlement of pressure vessel steels. A series of irradiation experiments have evaluated effects of chemistry on the fracture toughness properties of submerged arc welds representing current nuclear vessel fabrication practices and provide data to validate ASME Code practices. A correlation between Charpy energy and fracture toughness is being studied as is a program on radiation sensitivity to define the role of dose rate and to study the effects of postirradiation heat treatment (annealing). The development of a comprehensive data base for radiation embrittlement data has been initiated and is being applied in a correlation of reactor surveillance data with test reactor data. A comprehensive dosimetry effort has produced validated standard methods for calculating and measuring neutron flux and fluence parameters and the correlation of these parameters to embrittlement of pressure vessel steels in light water reactors. Our knowledge of radiation damage to reactor vessels has also been greatly increased in recent years by the accumulation of power reactor surveillance data and by better models and better analysis techniques applied to that data. Unfortunately, the results show that radiation damage is often more than previously predicted, using Revision 1 of NRC Regulatory Guide 1.99, and will result in more restrictive pressure temperature limits. The second part of this paper describes some of the system and operational impacts produced, which in turn lead to challenges to long-established safety margins. Finally, a number of outstanding issues which require further research are discussed, many of which will require better understanding of radiation damage mechanisms.

Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel

Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel PDF Author: PN. Randall
Publisher:
ISBN:
Category : Annealing
Languages : en
Pages : 12

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Book Description
This paper is in several parts: the first presents an overview of research activities sponsored by the U.S. Nuclear Regulatory Commission (NRC) on neutron irradiation embrittlement of pressure vessel steels. A series of irradiation experiments have evaluated effects of chemistry on the fracture toughness properties of submerged arc welds representing current nuclear vessel fabrication practices and provide data to validate ASME Code practices. A correlation between Charpy energy and fracture toughness is being studied as is a program on radiation sensitivity to define the role of dose rate and to study the effects of postirradiation heat treatment (annealing). The development of a comprehensive data base for radiation embrittlement data has been initiated and is being applied in a correlation of reactor surveillance data with test reactor data. A comprehensive dosimetry effort has produced validated standard methods for calculating and measuring neutron flux and fluence parameters and the correlation of these parameters to embrittlement of pressure vessel steels in light water reactors. Our knowledge of radiation damage to reactor vessels has also been greatly increased in recent years by the accumulation of power reactor surveillance data and by better models and better analysis techniques applied to that data. Unfortunately, the results show that radiation damage is often more than previously predicted, using Revision 1 of NRC Regulatory Guide 1.99, and will result in more restrictive pressure temperature limits. The second part of this paper describes some of the system and operational impacts produced, which in turn lead to challenges to long-established safety margins. Finally, a number of outstanding issues which require further research are discussed, many of which will require better understanding of radiation damage mechanisms.

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels PDF Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803111878
Category : Fracture mechanics
Languages : en
Pages : 276

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Book Description


Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels PDF Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803104731
Category : Boiling water reactors
Languages : en
Pages : 303

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Book Description


Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels PDF Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803114788
Category : Embrittlement
Languages : en
Pages : 405

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Book Description


Development of a Mechanistic Understanding of Radiation Embrittlement in Reactor Pressure Vessel Steels

Development of a Mechanistic Understanding of Radiation Embrittlement in Reactor Pressure Vessel Steels PDF Author:
Publisher:
ISBN:
Category : Electron microscopy
Languages : en
Pages : 75

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Book Description


Usnrc Research on Reactor Pressure Vessel Steel Embrittlement

Usnrc Research on Reactor Pressure Vessel Steel Embrittlement PDF Author: M. Mayfield
Publisher:
ISBN:
Category : Data base
Languages : en
Pages : 11

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Book Description
Meutron radiation embrittlement of nuclear reactor vessels continues to be a major concern of the USNRC. Research is sponsored for improving understanding of radiation embrittlement effects to predict margins of safety and to improve regulations. Regulatory issues that are affected by neutron embrittlement are examined and related to NRC research. Factors that control radiation embrittlement are examined. A comprehensive collection of radiation embrittlement data from surveillance reports and other published reports has been compiled in a computerized data base (PR-EDB). Fracture toughness data for irradiated pressure vessel steel has provided the basis for crack initiation and crack arrest toughness curves. Work is in place to improve our ability to predict thermal annealing recovery and reembrittlement. Areas where additional data are needed are described.

Overview of Studies in the United Kingdom on Neutron Irradiation Embrittlement of Pressure Vessel Steels

Overview of Studies in the United Kingdom on Neutron Irradiation Embrittlement of Pressure Vessel Steels PDF Author: LM. Davies
Publisher:
ISBN:
Category : Charpy tests
Languages : en
Pages : 21

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Book Description
The paper describes work on irradiation embrittlement that has been undertaken in the United Kingdom since preparation of the Second Marshall Report on the Integrity of pressure water reactor (PWR) pressure vessels. Results from research programs concentrate specifically on work on steels for Magnox and PWR pressure vessel (PV) applications.

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels PDF Author: Lendell E. Steele
Publisher: ASTM International
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 320

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Book Description


Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels

Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 70

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Book Description
This publication sets out the findings of a co-ordinated research project to determine the influence of the mechanism of the deterioration effect in radiation embrittlement of reactor pressure vessel steels with a high nickel content in nuclear power plants, including procurement of materials, determination of mechanical properties, irradiation and testing of specimens, and microstructural characterisation.

New Information on Neutron Embrittlement and Embrittlement Relief of Reactor Pressure Vessel Steels

New Information on Neutron Embrittlement and Embrittlement Relief of Reactor Pressure Vessel Steels PDF Author: L. E. STEELE
Publisher:
ISBN:
Category :
Languages : en
Pages : 42

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Book Description
Neutron embrittlement of the carbon and low-alloy steels investigated has been defined in terms of increases in the nil ductility transition (NDT) temperature. Increases in the NDT of pressure vessel steels as great as 545F have been observed. The extent of embrittlement has been shown to depend upon the neutron exposure, the type of steel, and the irradiation temperature. Embrittlement relief through annealing heat treatment at temperatures above the pressure vessel operating temperature has been demonstrated. Significant embrittlement relief was observed even with multiple irradiation-annealing cycles, the extent of relief being primarily dependent upon the irradiation temperature and the subsequent annealing temperature. Experimental data are reviewed with consideration for application to operating nuclear pressure vessel conditions. Preliminary results of power reactor surveillance and of the evaluation of one pressure vessel after nuclear service are related to experimental results. The value of extending the evaluation of surveillance speciments and of pressure vessels after removal from nuclear service are reviewed with reference to current uncertainties as to possible nuclear environmental and stress effects. (Author).