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Reactor Operations Management Plan

Description: The K-Reactor last operated in April 1988. At that time, K-Reactor was one of three operating reactors at the Savannah River Site (SRS). Following an incident in P-Reactor in August 1988, it was decided to discontinue SRS reactor operation and conduct an extensive program to upgrade operating practices and plant hardware prior to restart of any of the reactors. The K-reactor was the first of three reactors scheduled to resume production. At the present time, it is the only reactor with planned … more
Date: December 5, 1991
Creator: Rice, P.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Power Systems Development Facility Gasification Test Run TC07

Description: This report discusses Test Campaign TC07 of the Kellogg Brown & Root, Inc. (KBR) Transport Reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). The Transport Reactor was operated as a pressurized… more
Date: April 5, 2002
Creator: Southern Company Services
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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P Division monthly report, July 1949

Description: The progress report discusses activities of the P Division for the month of July, 1949. The B and F piles operated at 275 megawatts and the D pile at 305 megawatts throughout the month except for outages listed under Area Activities. A total of 57.5 tons of metal, at an average concentration of 363 megawatt days/ton (MWD/ton) was discharged from the piles during the month. This included 41.9 tons of Class V (alpha-rolled, triple-dipped, completely transformed) metal at an average concentration … more
Date: August 5, 1949
Creator: Lee, Edward P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Core-power and decay-time limits for disabled automatic-actuation of LOFT ECCS

Description: The Emergency Core Cooling System (ECCS) for the LOFT reactor may need to be disabled for modifications or repairs of hardware or instrumentation or for component testing during periods when the reactor system is hot and pressurized, or it may be desirable to enable the ECCS to be disabled without the necessity of cooling down and depressurizing the reactor. LTR 113-47 has shown that the LOFT ECCS can be safely bypassed or disabled when the total core power does not exceed 25 kW. A modified pol… more
Date: June 5, 1978
Creator: Hanson, G.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Xenon and Samarium reactivity effects associated with coolant loss

Description: In Hanford reactors the reactivity gain upon loss of coolant water is an important factor in the speed of control requirements. The reactivity gain in the cold, clean reactor is determined from experiments, but additional effects must be taken into account if the gain in the operating reactors is to be obtained. One of these effects is the change in Xenon and Samarium poisoning with neutron temperature, which is discussed here. Earlier work on the relationship of operating limits to the reactiv… more
Date: April 5, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Total Control vs Reactivity Parameters

Description: Changes in pile operating parameters, such as fuel exposure, paver, and reactivity gain upon water loss affect the potential reactivity of the operating, pile and, therefore, the amount of enrichment required to operate under the desired conditions. Similarly a change in ECT (through enrichment location) changes the amount of enrichment.needed to maintain a constant reactivity. Many of the factors which influence the operating reactivity have quite different effects upon the reactivity of the d… more
Date: February 5, 1959
Creator: Simpson, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Events of importance for week ending August 3, 1949

Description: The redox and pile operations are reported on. Construction in 100 (Pile), 200 (Separation), and 300 (Metal Fabrication) areas is described. General work in the Richland commercial areas and on the Southern Railroad connection is also described. Personnel information is disclosed.
Date: August 5, 1949
Creator: Schlemmer, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiochemistry for the rupture of a Zircaloy-2 clad, natural uranium thermocouple fuel element in KER-1

Description: During the 0000--0800 shift on August 21, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 2, 3 and 4 monitors indicating a possible fuel element failure in Loop 1. The KER Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant and coupon samples taken from Loop 1.
Date: June 5, 1961
Creator: Demmitt, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operating history

Description: This document provides the Hanford Production Reactors operating histories from January 1, 1961 through November 30, 1969. The raw log sheets are provided.
Date: March 5, 1964
Creator: Newell, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Monthly record report -- March 1965 research and engineering operation irradiation processing department

Description: This report covers progress in the following areas: process and reactor development; process technology; operational physics; and testing. Process and reactor developments covers reactor fuels, reactor engineering and radiological engineering. Process technology includes process standards, process change authorizations, and process standard relaxation. Operational physics includes updates on the B, C, D, F, H, KE, and KW reactors along with summaries of studies on reactivity and control and pro… more
Date: April 5, 1965
Creator: Greager, O. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aquifer Testing and Rebound Study in Support of the 100-H Deep Chromium Investigation

Description: The 100-HR-3 Groundwater Operable Unit (OU) second Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) 5-year review (DOEIRL-2006-20, The Second CERCLA Five-Year Review Report for the Hanford Site) set a milestone to conduct an investigation of deep hexavalent chromium contamination in the sediments of the Ringold upper mud (RUM) unit, which underlies the unconfined aquifer in the 100-H Area. The 5-year review noted that groundwater samples from one deep well … more
Date: November 5, 2010
Creator: Smoot, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PT IP-183-A-98-FP: Evaluation of projection fuel elements for use in K Process tubes

Description: The objective of this test is to permit irradiation of projection fuel elements to evaluate jacket corrosion in areas of projection, to examine the effect of well-aligned fuel elements on hot-spot incidence, and to evaluate problems associated with projection slug usage in ribbed process tubes.
Date: November 5, 1958
Creator: Hall, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Engineer Works technical progress letter number 152: May 25 through May 31, 1947

Description: This report gives weekly progress in pile technology. An exposure of over 96 hours was made with the slug radiographing apparatus from May 22 to May 26. The three pieces subjected to the exposure included one of the special pieces designed for installation of a thermocouple. The thermocouple well in the special pieces showed up satisfactorily and for the first time it was possible to detect spots which could be due to small voids. Crushing and breaking strength measurements made on graphite pie… more
Date: June 5, 1947
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REGULATORY STRATEGIES TO MINIMIZE GENERATION OF REGULATED WASTES FROM CLEANUP, CONTINUED USE OR DECOMMISSIONING OF NUCLEAR FACILITIES CONTAMINATED WITH POLYCHLORINATED BIPHENYLS (PCBS) - 11198

Description: Disposal costs for liquid PCB radioactive waste are among the highest of any category of regulated waste. The high cost is driven by the fact that disposal options are extremely limited. Toxic Substances Control Act (TSCA) regulations require most liquids with PCBs at concentration of {ge} 50 parts-per-million to be disposed by incineration or equivalent destructive treatment. Disposal fees can be as high as $200 per gallon. This figure does not include packaging and the cost to transport the w… more
Date: November 5, 2010
Creator: Lowry, N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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FY2004 CORROSION SURVEILLANCE RESULTS FOR L-BASIN

Description: This report documents the results of the L-Basin Corrosion Surveillance Program for the fiscal year 2004. Test coupons were removed from the basin on February 12, 2004, shipped to Savannah River National Laboratory (SRNL), and visually examined in a contaminated laboratory hood. Selected coupons were metallurgically characterized to establish the extent of general corrosion and pitting. Pitting was observed on galvanically coupled and on intentionally creviced coupons, thus demonstrating that l… more
Date: September 5, 2005
Creator: VORMELKER, P
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MSET modeling of Crystal River-3 venturi flow meters.

Description: The analysis of archived Crystal River-3 feedwater flow data reveals a slow and steady degradation of the flow meter measurements during the 1992/1993 operating cycle. MSET can reliably estimate the true flow rate and quantify the degree of departure between the indicated signal and the true flow rate with high accuracy. The MSET computed flow rate could, in principle, be used to provide an improved estimate of the reactor power and hence avoid the revenue loss associated with derating the reac… more
Date: January 5, 1998
Creator: Bockhorst, F. K.; Gross, K. C.; Herzog, J. P. & Wegerich, S. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Status of irradiations performed by testing and irradiation services for BNW as of February 18, 1968

Description: This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period. Data are given table form. An explanation of the various columns in the report is given.
Date: March 5, 1968
Creator: Barker, L. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of irradiations performed by fuel and target irradiation technology for BNW as of August 31, 1969

Description: This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the materials being irradiated, awaiting disposition and material shipped during the report period. The data are given in table form. Information consists of: TISR No.; request number; target material; piece number; operating time; CMK absorbed; charge date; location; exposure to date-NVT; discharge, date and time; and shipping date.
Date: September 5, 1969
Creator: Barker, L. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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