Radiation effects on reactor pressure vessel supports

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Description

The purpose of this report is to present the findings from the work done in accordance with the Task Action Plan developed to resolve the Nuclear Regulatory Commission (NRC) Generic Safety Issue No. 15, (GSI-15). GSI-15 was established to evaluate the potential for low-temperature, low-flux-level neutron irradiation to embrittle reactor pressure vessel (RPV) supports to the point of compromising plant safety. An evaluation of surveillance samples from the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) had suggested that some materials used for RPV supports in pressurized-water reactors could exhibit higher than expected embrittlement rates. However, ... continued below

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202 p.

Creation Information

Johnson, R.E. & Lipinski, R.E. May 1, 1996.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

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  • Johnson, R.E. Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology
  • Lipinski, R.E. Idaho National Engineering Lab., Rockville, MD (United States)

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Description

The purpose of this report is to present the findings from the work done in accordance with the Task Action Plan developed to resolve the Nuclear Regulatory Commission (NRC) Generic Safety Issue No. 15, (GSI-15). GSI-15 was established to evaluate the potential for low-temperature, low-flux-level neutron irradiation to embrittle reactor pressure vessel (RPV) supports to the point of compromising plant safety. An evaluation of surveillance samples from the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) had suggested that some materials used for RPV supports in pressurized-water reactors could exhibit higher than expected embrittlement rates. However, further tests designed to evaluate the applicability of the HFIR data to reactor RPV supports under operating conditions led to the conclusion that RPV supports could be evaluated using traditional method. It was found that the unique HFIR radiation environment allowed the gamma radiation to contribute significantly to the embrittlement. The shielding provided by the thick steel RPV shell ensures that degradation of RPV supports from gamma irradiation is improbable or minimal. The findings reported herein were used, in part, as the basis for technical resolution of the issue.

Physical Description

202 p.

Notes

INIS; OSTI as TI96010265

Source

  • Other Information: PBD: May 1996

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  • Other: TI96010265
  • Report No.: NUREG--1509
  • Grant Number: AC07-76ID01570
  • DOI: 10.2172/238567 | External Link
  • Office of Scientific & Technical Information Report Number: 238567
  • Archival Resource Key: ark:/67531/metadc672631

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • May 1, 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

Description Last Updated

  • April 8, 2016, 8:19 p.m.

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Johnson, R.E. & Lipinski, R.E. Radiation effects on reactor pressure vessel supports, report, May 1, 1996; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc672631/: accessed October 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.