U.S. High Fluence Power Reactor Surveillance Data—Past and FutureSource: Journal of Pressure Vessel Technology:;2014:;volume( 136 ):;issue: 002::page 21603DOI: 10.1115/1.4026149Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Enhanced radiation embrittlement at high fluence, indicative of extended operating life beyond 60 years for current operating pressurized water reactor (PWR) vessels, has been identified as a potential limiting degradation mechanism. Currently, there are limited U.S. power reactor surveillance data available at fluences greater than 4 أ— 1019 n/cm2 (E > 1 MeV) for comparison with existing embrittlement prediction models. Additional data will be required to support extended operations to 80+ years, where some plants are projected to have peak vessel fluences approaching 1 أ— 1020 n/cm2. A number of programs are designed to contribute to the high fluence surveillance data to support extended operating life. The U.S programs include the Coordinated PWR Reactor Vessel Surveillance Program (CRVSP), the PWR Supplemental Surveillance Program (PSSP), and the Light Water Reactor Sustainability (LWRS) Program. The LWRS Program involves generation of high fluence test reactor data on many different reactor pressure vessel steels and model alloys, including some of the same PWR vessel materials irradiated to higher fluences in conventional power reactor surveillance programs. This paper surveys the existing high fluence data and the data projected to come from the above listed programs to show when such data will become available. The data will be used to validate or revise embrittlement trend correlations applicable for the high fluence regime. Mechanical property data are being developed, and finescale microstructure data are being produced using stateoftheart methods.
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contributor author | Server, William L. | |
contributor author | Hardin, Timothy C. | |
contributor author | Brian Hall, J. | |
contributor author | Nanstad, Randy K. | |
date accessioned | 2017-05-09T01:11:56Z | |
date available | 2017-05-09T01:11:56Z | |
date issued | 2014 | |
identifier issn | 0094-9930 | |
identifier other | pvt_136_02_021603.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/156127 | |
description abstract | Enhanced radiation embrittlement at high fluence, indicative of extended operating life beyond 60 years for current operating pressurized water reactor (PWR) vessels, has been identified as a potential limiting degradation mechanism. Currently, there are limited U.S. power reactor surveillance data available at fluences greater than 4 أ— 1019 n/cm2 (E > 1 MeV) for comparison with existing embrittlement prediction models. Additional data will be required to support extended operations to 80+ years, where some plants are projected to have peak vessel fluences approaching 1 أ— 1020 n/cm2. A number of programs are designed to contribute to the high fluence surveillance data to support extended operating life. The U.S programs include the Coordinated PWR Reactor Vessel Surveillance Program (CRVSP), the PWR Supplemental Surveillance Program (PSSP), and the Light Water Reactor Sustainability (LWRS) Program. The LWRS Program involves generation of high fluence test reactor data on many different reactor pressure vessel steels and model alloys, including some of the same PWR vessel materials irradiated to higher fluences in conventional power reactor surveillance programs. This paper surveys the existing high fluence data and the data projected to come from the above listed programs to show when such data will become available. The data will be used to validate or revise embrittlement trend correlations applicable for the high fluence regime. Mechanical property data are being developed, and finescale microstructure data are being produced using stateoftheart methods. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | U.S. High Fluence Power Reactor Surveillance Data—Past and Future | |
type | Journal Paper | |
journal volume | 136 | |
journal issue | 2 | |
journal title | Journal of Pressure Vessel Technology | |
identifier doi | 10.1115/1.4026149 | |
journal fristpage | 21603 | |
journal lastpage | 21603 | |
identifier eissn | 1528-8978 | |
tree | Journal of Pressure Vessel Technology:;2014:;volume( 136 ):;issue: 002 | |
contenttype | Fulltext |