Search Results

Advanced search parameters have been applied.
open access

Multi-Region Simulation of Xenon Poisoning in the PRTR

Description: A previous study has been completed on the buildup and decay of xenon poisoning in the PRTR by simulating the reactor as a single region. The results of this study indicated that a study using a more refined model of the reactor would be valuable.
Date: April 13, 1959
Creator: Cameron, W. D.
Partner: UNT Libraries Government Documents Department
open access

Experimental PRTR Moderator Flow Distribution Results

Description: The moderator fluid will be injected into the PRTR calandrin through injectors located between the shroud tubes and at the bottom of the calandrin. It is important that the size and arrangement of the injectors be such that complete mixing of the moderator will occur and prevent hot sports from forming in the moderator. Such hot spots could lead to undesired changes in the moderating characteristics due to boiling within the moderator. Also of importance is the requirement that the injector sho… more
Date: January 7, 1959
Creator: Kreiter, M. R.
Partner: UNT Libraries Government Documents Department
open access

Advanced Reactors Transition Program Resource Loaded Schedule

Description: The Advanced Reactors Transition (ART) Resource Loaded Schedule (RLS) provides a cost and schedule baseline for managing the project elements within the ART Program. The Fast Flux Test Facility (FFTF) activities are delineated through the end of FY 2000, assuming continued standby. The Nuclear Energy (NE) Legacies and Plutonium Recycle Test Reactor (PRTR) activities are delineated through the end of the deactivation process. This document reflects the 1 Oct 1999 baseline.
Date: November 8, 1999
Creator: Bowen, W. W.
Partner: UNT Libraries Government Documents Department
open access

Advanced Reactors Transition Program Resource Loaded Schedule

Description: The Advanced Reactors Transition (ART) Resource Loaded Schedule (RLS) provides a cost and schedule baseline for managing the project elements within the ART Program. The Fast Flux Test Facility (FETF) activities are delineated through the end of FY 2000, assuming continued standby. The Nuclear Energy (NE) Legacies and Plutonium Recycle Test Reactor (PRTR) activities are delineated through the end of the deactivation process. This revision reflects the 19 Oct 1999 baseline.
Date: January 12, 2000
Creator: Gantt, D. A.
Partner: UNT Libraries Government Documents Department
open access

Characterization of the 309 fuel examination facility

Description: This document identifies radiological, chemical and physical conditions inside the Fuel Examination Facility. It is located inside the Plutonium Recycle Test Reactor containment structure (309 Building.) The facility was a hot cell used for examination of PRTR fuel and equipment during the 1960`s. Located inside the cell is a PRTR shim rod assembly, reported are radiological conditions of the sample. The conditions were assessed as part of overall 309 Building transition.
Date: July 9, 1997
Creator: Greenhalgh, W.O. & Cornwell, B.C.
Partner: UNT Libraries Government Documents Department
open access

PRTR ion exchange vault water removal

Description: This report documents the removal of radiologically contaminated water from the Plutonium Recycle Test Reactor (PRTR) ion exchange vault. Approximately 57,000 liters (15,000 gallons) of water had accumulated in the vault due to the absence of a rain cover. The water was removed and the vault inspected for signs of leakage. No evidence of leakage was found. The removal and disposal of the radiologically contaminated water decreased the risk of environmental contamination.
Date: November 1, 1995
Creator: Ham, J.E.
Partner: UNT Libraries Government Documents Department
open access

Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask

Description: This safety evaluation for packaging (SEP) provides the evaluation necessary to demonstrate that the Plutonium Recycle Test Reactor (PRTR) Graphite Cask meets the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B, fissile, non-highway route controlled quantities of radioactive material within the 300 Area of the Hanford Site. The scope of this SEP includes risk, shieldling, criticality, and.tiedown analyses to demonstrate that onsite transportation s… more
Date: September 29, 1997
Creator: Romano, T.
Partner: UNT Libraries Government Documents Department
open access

Characterization of the 309 building fuel transfer pit and storage basin

Description: This document identifies radiological, chemical and physical conditions inside the Fuel Transfer Pit and Fuel Storage Basins. These spaces are located inside the Plutonium Recycle Test Reactor structure (309 Building.) The fuel handling and storage feature of the PRTR were primarily located in these spaces. The conditions were assessed as part of overall 309 Building transition.
Date: March 19, 1998
Creator: Hale, N.S.
Partner: UNT Libraries Government Documents Department
open access

309 Building deactivation mission analysis report

Description: This report presents the results of the 309 Building (Plutonium Fuels Utilization Program) Deactivation Project mission analysis. Hanford systems engineering (SE) procedures call for a mission analysis. The mission analysis is an important first step in the SE process. The functions and requirements to successfully accomplish this mission, the selected alternatives and products will later be defined using the SE process.
Date: May 24, 1995
Creator: Lund, D. P.
Partner: UNT Libraries Government Documents Department
open access

Safety Evaluation for Packaging for onsite Transfer of plutonium recycle test reactor ion exchange columns

Description: The purpose of this Safety Evaluation for Packaging (SEP) is to authorize the use of three U.S. Department of Transportation (DOT) 7A, Type A metal boxes (Capital Industries Part No. S 0600-0600-1080- 0104) to package 12 Plutonium Recycle Test Reactor (PRTR) ion exchange columns as low-level waste (LLW). The packages will be transferred from the 309 Building in the 300 Area to low level waste burial in the 200 West Area. Revision 1 of WHC-SD-TP-SEP-035 (per ECN No. 621467) documents that the bo… more
Date: September 11, 1995
Creator: Smith, R. J.
Partner: UNT Libraries Government Documents Department
open access

THE ZIRFLEX PROCESS INTERIM DEVELOPMENT SUMMARY

Description: The Zircaloy-clad fuels and the application of the Zirflex Process for dissolution are discussed. Zirflex chemical flowsheets are presented as developed by pilot plant operatlons. The Zirflex Process is applicable to the reprocessing of fuels from the Dresden Reactor and the PWR Reactor. Other applications of the process are the Plutonium Recycle Test Reactor fuels and the New Production Reactor fuels, possible fuels from the Experimental Breeder Reactor; NPD-2 fuels; and fuels from Carolina-Vi… more
Date: June 24, 1959
Creator: Platt, A.M. & Cooley, C.R.
Partner: UNT Libraries Government Documents Department
open access

FFTF and Advanced Reactors Transition Program Resource Loaded Schedule

Description: This Resource Load Schedule (RLS) addresses two missions. The Advanced Reactors Transition (ART) mission, funded by DOE-EM, is to transition assigned, surplus facilities to a safe and compliant, low-cost, stable, deactivated condition (requiring minimal surveillance and maintenance) pending eventual reuse or D&D. Facilities to be transitioned include the 309 Building Plutonium Recycle Test Reactor (PRTR) and Nuclear Energy Legacy facilities. This mission is funded through the Environmental … more
Date: October 31, 2000
Creator: GANTT, D.A.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen