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Concrete nondestructive tests conducted in 225-B building

Description: In 1982, Construction Technology Laboratories (CTL), Portland Cement Association conducted additional sonic concrete nondestructive testing (NDT) in the Service Gallery on the south process (hot) cell walls and adjacent floor slab, including the locations where significant concrete degradation had been found by the 1981 sonic NDT. In the ceiling slabs, the anchor areas For the monorail hangers, and some visible cracks were sonic NDT inspected. CTL concluded that the hot cell walls have no signi… more
Date: September 19, 1996
Creator: Vollert, F.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Epoxy injection repairs to concrete in 225-B Building

Description: In 1982, the damaged anchor areas (67 total) in the Operating Gallery and cold manipulator shop ceiling reinforced concrete slabs were epoxy injection repaired by Construction Technology Laboratories (CTL), Portland Cement Association. The through depth vertical cracks (10 total) in the ceiling slabs in the galleries and manipulator shops were sealed and structurally repaired using epoxy injection procedures. The details of the epoxy reRair are reported. Sonic nondestructive (NDT) testing befor… more
Date: September 19, 1996
Creator: Vollert, F.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PUREX/UO3 Facilities deactivation lessons learned history

Description: Disconnecting the criticality alarm permanently in June 1996 signified that the hazards in the PUREX (plutonium-uranium extraction) plant had been so removed and reduced that criticality was no longer a credible event. Turning off the PUREX criticality alarm also marked a salient point in a historic deactivation project, 1 year before its anticipated conclusion. The PUREX/UO3 Deactivation Project began in October 1993 as a 5-year, $222.5- million project. As a result of innovations implemented … more
Date: September 19, 1996
Creator: Gerber, M.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ID-69 Sodium drain experiments

Description: This paper describes experiments to determine the sodium retention and drainage from the two key areas of an ID-69. This information is then used as the initiation point for guidelines of how to proceed with washing an ID-69 in the IEM Cell Sodium Removal System.
Date: September 19, 1996
Creator: Johnston, D.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Releases from failed HEPA filters due to an overpressurization event

Description: This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: HEPA Filter Failure - Exposure to High Temperature or Pressure. The calculations needed to quantify the risk associated with this accident scenario are included within.
Date: September 19, 1996
Creator: Ryan, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Criticality safety assessment of tank 241-C-106 remediation

Description: A criticality safety assessment was performed in support of Project 320 for the retrieval of waste from tank 241-C-106 to tank 241-AY-102. The assessment was performed by a multi-disciplined team consisting of expertise covering the range of nuclear engineering, plutonium and nuclear waste chemistry,and physical mixing hydraulics. Technical analysis was performed to evaluate the physical and chemical behavior of fissile material in neutralized Hanford waste as well as modeling of the fluid dyna… more
Date: July 19, 1996
Creator: Waltar, A. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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