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Qualification of a Tritium-Producing Target for the light water reactor application

Description: The Pacific Northwest Laboratory (PNL) currently manages the Light Water Reactor (LWR) Tritium Target Development Project (TTDP) for the Office of New Production Reactors (NP), US Department of Energy. The project`s objective is to demonstrate and qualify a high-temperature LWR tritium target system with fabrication and extraction processes sufficiently confirmed to ensure a deployable system consistent with variable tritium production demands. The project has also examined and reported on tech… more
Date: June 1, 1992
Creator: Apley, W. J.; Beeman, G. H. & Ethridge, J. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Continuous tritium effluent water monitor at the Savannah River Site

Description: A continuous monitor for tritium in water has been installed in the secondary cooling water effluent from the K-Reactor at the Savannah River Site (SRS). The monitor is designed to provide early detection of a small leak of the tritiated heavy water moderator and facilitate rapid isolation procedures. The tritium detector consists of an analysis cell containing 0.1--0.25 mm diameter beads of plastic scintillator interposed between two photomultiplier tubes and standard fast-slow coincidence ele… more
Date: November 1, 1992
Creator: Hofstetter, K. J. & Wilson, H. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of K-Area core samples for K-Area formation stabilization work

Description: Foundation stabilization work in K-Area has been recently completed by Bechtel Inc. This effort involved pumping cement and cement-sand grout into unconsolidated sediments under K-Area. Subsequent to stabilization, core samples were collected to document the extent of grout flow in the area. Samples of this core were examined by SRTC personnel in support of the grouting program at the request of Bechtel personnel. This report summarizes the results of the SRTC study.
Date: May 27, 1992
Creator: Langton, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of effluent disposal practices in N Reactor Department

Description: A survey has been conducted of current methods of disposal of radioactive, chemical, and sanitary wastes used both at the 100 Area and 300 Area sites of N Reactor Department Operations. In addition, liquid storage facilities have been surveyed for situations which might result in river water pollution. The survey and this report have been prepared in response to the request of the Manager, Richland Operations Office of the Atomic Energy Commission in accordance with Executive Order 11258. An au… more
Date: February 28, 1966
Creator: Stepnewski, D. D. & Hendrickson, M. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Restart Division trend analysis report, second quarter 1991

Description: This document provides a trend analysis for the Savannah River Reactor Restart Program. The data contained in this report is comprised of Nonconformance Report (NCR), Surveillance Reports, and Corrective Action Reports (CAR). The data trended now includes six quarters and provides the capability of looking at changing patterns in the various performance categories over time.
Date: October 7, 1991
Creator: Castles, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An exploratory analysis of thermal-hydraulic conditions leading to severe accidents for the New Production Heavy-Water Reactor

Description: This study, sponsored by the New Production Reactor (NPR) Program through the Los Alamos NPR Safety Project Office, is part of the body of severe-accident review information being developed to support the safety review of the New Production Heavy-Water Reactor (NP-HWR). The NP-HWR safety study of severe beyond-design-basis events concerns two issues related to in-vessel, sudden-energy sources: wet-core recriticality and molten-fuel-and-coolant interaction (MFCI). The configuration that will lea… more
Date: December 1, 1992
Creator: Cheng, Teh-Chin
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design optimization analysis of the new SPR III-M reactor

Description: This report discusses the finite element method analysis which was used to refine the SPR III-M reactor fuel assembly mechanical design to withstand the stresses and strains of pulse-mode operation, which induces thermal shock loading in the fuel assembly components. The original reactor design was analyzed for its structural response to separate pulses at increasingly severe levels. Subsequent calculations at one consistent pulse level examined several design modifications, which will result i… more
Date: December 31, 1993
Creator: Miller, J. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, September 1963

Description: This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: October 14, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The RERTR Program. A status report

Description: The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. The major events, findings, and activities of 1991 are reviewed after a brief summary of the results which the RERTR Program had achieved by the end of 1991 in collaboration with its many international partners.
Date: December 31, 1992
Creator: Travelli, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Best-estimate Mark 22 power and temperature limits during the flow instability phase of K Reactor LBLOCAs

Description: Los Alamos National Laboratory (LANL) has been providing independent analyses to the Department of Energy in its endeavor to enhance the safe operation of the K Reactor located at the Savannah River Laboratory (SRL). LANL has performed neutronic and thermal-hydraulic system simulations to assess the impact of hypothesized accidents in the K Reactor. In particular, the large-break loss-of-coolant accident (LBLOCA) was one of the major transients that was analyzed. The LBLOCA consists of two dist… more
Date: March 1, 1992
Creator: Rodriguez, S.; Steiner, J.; Motley, F. & Morgan, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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C-Reactor I and E loading instability limits

Description: The pilot charging of I & E fuel elements has been implemented at C-Reactor under Production Test IP-19-A. It was necessary to provide adequate tube protection against flow interruption by establishing proper trip setting on the Panellit pressure gauges. the administration of these Panellit trip settings is done by trip-before- boiling tube outlet temperature limits, which are similar in principle to the current instability limits. Trip-before-boiling limits for C-Reactor I & E fuel elements lo… more
Date: January 24, 1957
Creator: Hess, K. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report on Production Test 105-528-A -- Alteration of two C-Pile horizontal safety rods for temperature distribution control

Description: Pile temperature control is normally maintained by using four horizontal rods, two ``long`` rods extending to the far side of the pile and two ``short`` rods whose tips are on the near side. (1) This procedure prevents cycling of ``hot spots`` about the pile, but does not achieve symmetrical horizontal temperature distribution. Prior to pile operation the cadmium-containing cans were removed from the near ends of the two ``long`` control rods, numbers 5 and 11, at C pile, so that when these rod… more
Date: June 11, 1953
Creator: Halliday, A. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Flow regime mapping of vertical two-phase downflow in a ribbed annulus

Description: Two-phase flow regimes have been mapped for vertical, cocurrent downflow in a narrow annulus which is partially segmented by the presence of longitudinal ribs. This geometry and flow condition has application to the analysis of a Large-Break Loss of Coolant Accident (LB-LOCA) in the production K-Reactor at the Savannah River Site (SRS). The ribbed annular geometry, particularly the presence of non-sealing ribs, gives rise to some unique phenomenological features. The flow behavior is influenced… more
Date: December 1, 1992
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radioisotope concentrations in the PRTR primary coolant and helium system during operation with a failed fuel element(s)

Description: Fission product measurements in the PRTR primary D{sub 2}O and helium systems during the startup tests in May 1961, showed the presence of a defective fuel elements(s). Reactor operation was discontinued during the latter part of May and during June for reactor maintenance and fuel element inspection. On resumption of operation on July 1, a sampling and analytical program was initiated to study the radioisotope concentrations resulting from this defective element(s) which were present in the pr… more
Date: September 7, 1961
Creator: Perkins, R. W. & Thomas, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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