Examination of H8 and B8 leadscrews from Three Mile Island Unit 2 (TMI-2) Metadata

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  • Main Title Examination of H8 and B8 leadscrews from Three Mile Island Unit 2 (TMI-2)


  • Author: Vinjamuri, K.
    Creator Type: Personal
  • Author: Akers, D.W.
    Creator Type: Personal
  • Author: Hobbins, R.R.
    Creator Type: Personal


  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE


  • Name: EG & G Idaho
    Place of Publication: Idaho Falls, Idaho
    Additional Info: EG and G Idaho, Inc., Idaho Falls (USA)


  • Creation: 1985-09-01


  • English


  • Content Description: Visual examinations, preliminary temperature estimates, and chemical and radiological analyses were conducted on samples removed from the control rod drive leadscrews. Hardness measurements and microstructure analysis suggest that significant temperature differences existed between the portions of the leadscrews closest to the bottom and top of the plenum assembly. Preliminary analysis indicates that the temperatures ranged from 666 to 1255/sup 0/K (740 to 1800/sup 0/F) for H8 and 723 to 1033/sup 0/K (842 to 1400/sup 0/F) for B8. The uncertainty in the temperature estimates is about +-28 to 56/sup 0/K (+-50 to 100/sup 0/F). Chemical analyses indicate that UO/sub 2/ and zirconium were deposited to a greater extent on surfaces closer to the core. Radiological analyses suggest that a number of the H8 radionuclides are insoluble in strong acid solutions. In contrast, more of the B8 radionuclides are soluble in strong acidic solutions. Also, an axial gradient in surface radionuclide concentrations was observed, with the highest concentration near the top of the plenum assembly. The data indicate changes in chemical composition and gradients in the surface radionuclide concentrations in the plenum assembly. As extrapolated from leadscrew data, the fractions of total core inventory of radionuclides retained on the plenum assembly surfaces are small (<2%).


  • Keyword: Radioactive Materials
  • STI Subject Categories: 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
  • Keyword: Reactor Components
  • STI Subject Categories: 22 General Studies Of Nuclear Reactors
  • Keyword: Reactor Accidents
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: Isotopes
  • Keyword: Crystal Structure
  • Keyword: Water Cooled Reactors
  • Keyword: Materials
  • Keyword: Fission Products
  • Keyword: Accidents
  • Keyword: Thermal Reactors
  • Keyword: Reactors
  • Keyword: Inspection
  • Keyword: Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
  • Keyword: Pwr Type Reactors
  • Keyword: Metallography
  • Keyword: Microstructure
  • Keyword: Enriched Uranium Reactors
  • Keyword: Chemical Analysis
  • Keyword: Radiochemical Analysis
  • Keyword: Control Rod Drives
  • Keyword: Three Mile Island-2 Reactor
  • Keyword: Power Reactors
  • Keyword: Radioisotopes
  • Keyword: Quantitative Chemical Analysis


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


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report


  • Text


  • Other: DE86002327
  • Report No.: GEND-INF-052
  • Grant Number: AC07-76ID01570
  • DOI: 10.2172/5048524
  • Office of Scientific & Technical Information Report Number: 5048524
  • Archival Resource Key: ark:/67531/metadc1061513