Radiation effects on reactor pressure vessel supports Metadata

Metadata describes a digital item, providing (if known) such information as creator, publisher, contents, size, relationship to other resources, and more. Metadata may also contain "preservation" components that help us to maintain the integrity of digital files over time.

Title

  • Main Title Radiation effects on reactor pressure vessel supports

Creator

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

Contributor

  • Sponsor: U.S. Nuclear Regulatory Commission
    Contributor Type: Organization
    Contributor Info: Nuclear Regulatory Commission, Washington, DC (United States)

Publisher

  • Name: U.S. Nuclear Regulatory Commission
    Place of Publication: Washington D.C.
    Additional Info: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology
  • Name: EG & G Idaho
    Place of Publication: Idaho Falls, Idaho
    Additional Info: EG and G Idaho, Inc., Idaho Falls, ID (United States)

Date

  • Creation: 1996-05-01

Language

  • English

Description

  • Content 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.

Subject

  • Keyword: Trojan Reactor
  • STI Subject Categories: 21 Nuclear Power Reactors And Associated Plants
  • Keyword: Embrittlement
  • STI Subject Categories: 36 Materials Science
  • Keyword: Physical Radiation Effects
  • Keyword: Fracture Mechanics
  • Keyword: Cost Benefit Analysis
  • Keyword: Data
  • Keyword: Pwr Type Reactors
  • Keyword: Reliability
  • Keyword: Pressure Vessels
  • Keyword: Reactor Materials
  • Keyword: Shippingport Reactor
  • Keyword: Steels
  • Keyword: Supports

Source

  • Other Information: PBD: May 1996

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

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

Note

  • Display Note: INIS; OSTI as TI96010265
Back to Top of Screen