11 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Hot Cells"  
Results: 1 - 11
open access

WASTE PACKAGE REMEDIATION SYSTEM DESCRIPTION DOCUMENT

Description: The Waste Package Remediation System remediates waste packages (WPs) and disposal containers (DCs) in one of two ways: preparation of rejected DC closure welds for repair or opening of the DC/WP. DCs are brought to the Waste Package Remediation System for preparation of rejected closure welds if testing of the closure weld by the Disposal Container Handling System indicates an unacceptable, but repairable, welding flaw. DC preparation of rejected closure welds will require removal of the weld i… more
Date: June 22, 2000
Creator: Sudan, N.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Robot Work Platform for Large Hot Cell Deactivation

Description: The 324 Building, located at the Hanford Site near Richland, Washington, is being deactivated to meet state and federal cleanup commitments. The facility is currently in its third year of a nine-year project to complete deactivation and closure for long-term surveillance and maintenance. The 324 building contains large hot cells that were used for high-radiation, high-contamination chemical process development and demonstrations. A major obstacle for the 324 deactivation project is the inabilit… more
Date: May 1, 2000
Creator: Bitten, E. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

Description: The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from t… more
Date: June 30, 2000
Creator: Loros, E. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Prototype Tests for the Recovery and Conversion of UF<sub>6</sub>Chemisorbed in NaF Traps for the Molten Salt Reactor Remediation Project

Description: The remediation of the Molten Salt Reactor Experiment (MSRE) site includes the removal of about 37 kg of uranium. Of that inventory, about 23 kg have already been removed from the piping system and chemisorbed in 25 NaF traps. This material is being stored in Building 3019. The planned recovery of {approx}11 kg of uranium from the fuel salt will generate another 15 to 19 NaF traps. The remaining 2 to 3 kg of uranium are present in activated charcoal beds, which are also scheduled to be removed … more
Date: June 7, 2000
Creator: Del Cul, G.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spent Nuclear Fuel (SNF) Project Acceptance Criteria for Light Water Reactor Spent Fuel Storage System [OCRWM PER REV2]

Description: As part of the decommissioning of the 324 Building Radiochemical Engineering Cells there is a need to remove commercial Light Water Reactor (LWR) spent nuclear fuel (SNF) presently stored in these hot cells. To enable fuel removal from the hot cells, the commercial LWR SNF will be packaged and shipped to the 200 Area Interim Storage Area (ISA) in a manner that satisfies site requirements for SNF interim storage. This document identifies the criteria that the 324 Building Radiochemical Engineeri… more
Date: December 20, 2000
Creator: Johnson, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Drying Results of K-Basin Damaged/Corroded SNF Internal Sludge and Surface Coating

Description: Experiments were performed using a thermogravimetric analysis (TGA) system by Pacific Northwest National Laboratory (PNNL)to study the drying behavior of the K-Basin spent nuclear fuel (SNF) internal sludge and two different surface coatings of SNF elements. These measurements were conducted in support of the safety and process analyses of the proposed Integrated Process Strategy (IPS) to move the N-Reactor fuel stored at K-Basin to an interim storage facility. These limited experiments on the … more
Date: September 21, 2000
Creator: Abrefah, J.; Alexander, D. L. & Marschman, S. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Prototype Tests for the Recovery and Conversion of UF6 Chemisorbed in NaF Traps for the Molten Salt Reactor Remediation Project

Description: The remediation of the Molten Salt Reactor Experiment (MSRE) site includes the removal of about 37 kg of uranium. Of that inventory, about 23 kg have already been removed from the piping system and chemisorbed in 25 NaF traps. This material is being stored in Building 3019. The planned recovery of -11 kg of uranium from the fuel salt will generate another 15 to 19 NaF traps. The remaining 2 to 3 kg of uranium are present in activated charcoal beds, which are also scheduled to be removed from th… more
Date: April 1, 2000
Creator: Del Cul, G.D.; Icenhour, A.S. & Simmons, D.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reliable Wireless Data Acquisition and Control Techniques within Nuclear Hot Cell Facilities

Description: On this NEER project the University of Florida has investigated and applied advanced communications techniques to address data acquisition and control problems within the Fuel Conditioning Facility (FCF) of Argonne National Laboratory-West (ANL-W) in Idaho Falls. The goals of this project have been to investigate and apply wireless communications techniques to solve the problem of communicating with and controlling equipment and systems within a nuclear hot cell facility with its attendant high… more
Date: September 20, 2000
Creator: Kurtz, J.L. & Tulenko, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hot Cell Facility (HCF) Safety Analysis Report

Description: This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF an… more
Date: November 1, 2000
Creator: Mitchell, Gerry W.; Longley, Susan W.; Philbin, Jeffrey S.; Mahn, Jeffrey A.; Berry, Donald T.; Schwers, Norman F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Verification survey of the hot cell facility site, General Atomics, San Diego, California

Description: From 1958, General Atomics maintain a hot cell facility in support of government-funded research into reactor fuels. As the use of the facility declined, General Atomics entered into an agreement with DOE to dismantle the facility and decontaminate and decommission (D&amp;D) the site so that it could made available for unrestricted use. The Environmental Survey and Site Assessment Program (ESSAP) was requested to verify the final radiological status of the D&amp;D effort. This is the report of … more
Date: June 30, 2000
Creator: Adams, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen