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Mixer pump long term operations plan for Tank 241-SY-101 mitigation

Description: This document provides the general Operations Plan for performance of the mixer pump long term operations for Tank 241-SY-101 mitigation of gas retention and periodic release in Tank 101-SY. This operations plan will utilize a 112 kW (150 hp) mixing pump to agitate/suspend the particulates in the tank.
Date: September 7, 1994
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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105-KE Basin isolation barrier leak rate test analytical development. Revision 1

Description: This document provides an analytical development in support of the proposed leak rate test of the 105-KE Basin. The analytical basis upon which the K-basin leak test results will be used to determine the basin leakage rates is developed in this report. The leakage of the K-Basin isolation barriers under postulated accident conditions will be determined from the test results. There are two fundamental flow regimes that may exist in the postulated K-Basin leakage: viscous laminar and turbulent fl… more
Date: May 9, 1995
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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105-KE Basin isolation barrier leak rate test analytical development

Description: This report provides analytical developments in support of the proposed leak rate test of the 105-KE Basin. The analytical basis upon which the K-basin leak test results will be used ti determine the basin leakage rates is developed in this report. The leakage of the K-Basin isolation barriers under accident conditions will be determined from the test results. There are two fundamental flow regimes that may exist in the postulated K-Basin leakage, viscous laminar and turbulent flow. An analytic… more
Date: December 1, 1994
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FFTF vertical sodium storage tank preliminary thermal analysis

Description: In the FFTF Shutdown Program, sodium from the primary and secondary heat transport loops, Interim Decay Storage (IDS), and Fuel Storage Facility (FSF) will be transferred to four large storage tanks for temporary storage. Three of the storage tanks will be cylindrical vertical tanks having a diameter of 28 feet, height of 22 feet and fabricated from carbon steel. The fourth tank is a horizontal cylindrical tank but is not the subject of this report. The storage tanks will be located near the FF… more
Date: February 21, 1995
Creator: Irwin, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FFTF horizontal sodium storage tank preliminary thermal analysis

Description: In the FFTF Shutdown Program, sodium from the primary and secondary heat transport loops, Interim Decay Storage (IDS), and Fuel Storage Facility (FSF) will be transferred to four large storage tanks for temporary storage. Three of the drain tanks will be cylindrical vertical tanks having a diameter of 28 feet, height of 22 feet and fabricated from carbon steel. The vertical tanks were the subject of a previous report and are not the subject of this report. The fourth tank is a horizontal cylind… more
Date: February 21, 1995
Creator: Irwin, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

Description: The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces… more
Date: November 18, 2000
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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105K West Isolation Barrier Acceptance Test results

Description: The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KW/100K. The tests were performed in accordance with the test plan and acceptance test procedure. The test report contains the test data. This document compares the test data against the criteria. A discussion of the leak rate analytical characterization describes how the flow characteristics flow rate will be determined using the test data from the test report. Two m… more
Date: May 18, 1995
Creator: McCracken, K. J. & Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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105 K East isolation barrier acceptance analysis report

Description: The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KE/100K. The tests were performed in accordance with the test plan (McCracken 1995c) and acceptance test procedure (McCracken 1995a). The test report (McCracken 1995b) contains the test data. This document compares the test data (McCracken 1995b) against the criteria (McCracken 1995a, c). A discussion of the leak rate analytical characterization (Irwin 1995) describes… more
Date: May 31, 1995
Creator: McCracken, K. J. & Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cold Vacuum Drying (CVD) Facility Vacuum Purge System Chilled Water System Design Description (SYS 47-4)

Description: This system design description (SDD) addresses the Vacuum Purge System Chilled Water (VPSCHW) system. The discussion that follows is limited to the VPSCHW system and its interfaces with associated systems. The reader's attention is directed to Drawings H-1-82162, Cold Vacuum Drying Facility Process Equipment Skid P&ID Vacuum System, and H-1-82224, Cold Vacuum Drying Facility Mechanical Utilities Process Chilled Water P&ID. Figure 1-1 shows the location and equipment arrangement for the … more
Date: June 13, 2000
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent nuclear fuel project cold vacuum drying facility process water conditioning system design description

Description: This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Process Water Conditioning (PWC) System. The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), the HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the PWC … more
Date: November 30, 1998
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

Description: This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a gene… more
Date: February 3, 2000
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Master Equipment List

Description: This document provides the master equipment list (MEL) for the Cold Vacuum Drying Facility (CVDF). The MEL was prepared to comply with DOE Standard 3024-98, Content of System Design Descriptions. The MEL was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems and the CVDF System Design Descriptions (SDD). The MEL identifies the SSCs and their safety functions, the design criteria, co… more
Date: September 21, 1999
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent nuclear fuel project cold vacuum drying facility safety equipment list

Description: This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installatio… more
Date: February 24, 1999
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spent nuclear fuel project cold vacuum drying facility operations manual

Description: This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general … more
Date: May 12, 1999
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spent nuclear fuel project cold vacuum drying facility supporting data and calculation database

Description: This document provides a database of supporting calculations for the Cold Vacuum Drying Facility (CVDF). The database was developed in conjunction with HNF-SD-SNF-SAR-002, ''Safety Analysis Report for the Cold Vacuum Drying Facility'', Phase 2, ''Supporting Installation of Processing Systems'' (Garvin 1998). The HNF-SD-SNF-DRD-002, 1997, ''Cold Vacuum Drying Facility Design Requirements'', Rev. 2, and the CVDF Summary Design Report. The database contains calculation report entries for all proce… more
Date: February 26, 1999
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spent nuclear fuel project cold vacuum drying facility tempered water and tempered water cooling system design description

Description: This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Tempered Water (TW) and Tempered Water Cooling (TWC) System . The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general des… more
Date: November 30, 1998
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

Description: This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment… more
Date: November 30, 1998
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cold Vacuum Drying (CVD) Facility Sampling and Analysis Plan

Description: The Cold Vacuum Drying (CVD) Facility provides the required process systems, supporting equipment, and facilities needed for the conditioning of spent nuclear fuel (SNF) from the Hanford K-Basins prior to storage at the Canister Storage Building (CSB). The process water conditioning (PWC) system collects and treats the selected liquid effluent streams generated by the CVD process. The PWC system uses ion exchange modules (IXMs) and filtration to remove radioactive ions and particulate from CVD … more
Date: September 22, 2000
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual

Description: This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations seq… more
Date: July 2, 1999
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Hanford spent nuclear metal fuel multi-canister overpack and vacuum drying {ampersand} hot conditioning process

Description: Nuclear production reactors operated at the U.S. Department of Energy`s Hanford Site from 1944 until 1988 to produce plutonium. Most of the irradiated fuel from these reactors was processed onsite to separate and recover the plutonium. When the processing facilities were closed in 1992, about 1,900 metric tons of unprocessed irradiated fuel remained in storage. Additional fuel was irradiated for research purposes or was shipped to the Hanford Site from offsite reactor facilities for storage or … more
Date: May 15, 1996
Creator: Irwin, J.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Cold vacuum drying facility design requirements

Description: This release of the Design Requirements Document is a complete restructuring and rewrite to the document previously prepared and released for project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility.
Date: September 24, 1997
Creator: Irwin, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spent nuclear fuel vacuum drying thermal-hydraulic analysis and dynamic model development status report

Description: This report summarizes preliminary thermal hydraulic scoping analysis and model development associated with the K Basin spent fuel MCO draining and vacuum drying system. The purpose of the draining and drying system is to remove all free water from the interior of the MCO, baskets, and fuel prior to back filling with inert gas and transfer to the hot conditioning process. Dominant physical processes and parameters are delineated and related quantitatively. Minimum dynamic modeling capability re… more
Date: August 28, 1996
Creator: Irwin, J.J. & Ogden, D.M., Westinghouse Hanford
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Engineering study of tank leaks related to hydraulic retrieval of sludge from tank 241-C-106. Revision 1

Description: This study evaluates hydraulic retrieval (sluicing) of the waste in single-shell tank 241-C-106 with respect to the likelihood of tank leaks, gross volumes of potential leaks, and their consequences. A description of hydraulic retrieval is developed to establish a baseline for the study. Leak models are developed based on postulated leak mechanisms to estimate the amount of waste that could potentially leak while sluicing. Transport models describe the movement of the waste constituents in the … more
Date: June 9, 1993
Creator: Lowe, S. S.; Carlos, W. C.; Irwin, J. J.; Khaleel, R.; Kline, N. W.; Ludowise, J. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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