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K Basins isolation barriers summary report

Description: The 105-K East and 105-K West fuel storage basins (105-K Basins) were designed and constructed in the early 1950`s for interim storage of irradiated fuel following its discharge from the reactors. The 105-K- East and 105-K West reactor buildings were constructed first, and the associated storage basins were added about a year later. The construction joint between each reactor building structure and the basin structure included a flexible membrane waterstop to prevent leakage. Water in the storage basins provided both radiation shielding and cooling to remove decay heat from stored fuel until its transfer to the Plutonium Uranium Extraction (PUREX) Facility for chemical processing. The 105-K West Reactor was permanently shut down in February 1970; the 105-K East Reactor was permanently shut down in February 1971. Except for a few loose pieces, fuel stored in the basins at that time was shipped to the PUREX Facility for processing. The basins were then left idle but were kept filled with water. The PUREX Facility was shut down and placed on wet standby in 1972 while N Reactor continued to operate. When the N Reactor fuel storage basin began to approach storage capacity, the decision was made to modify the fuel storage basins at 105-K East and 105-K West to provide additional storage capacity. Both basins were subsequently modified (105-K East in 1975 and 105-K West in 1981) to provide for the interim handling and storage of irradiated N Reactor fuel. The PUREX Facility was restarted in November 1983 to provide 1698 additional weapons-grade plutonium for the United States defense mission. The facility was shut down and deactivated in December 1992 when the U.S. Department of Energy (DOE) determined that the plant was no longer needed to support weapons-grade plutonium production. When the PUREX Facility was shut down, approximately 2.1 x 1 ...
Date: July 31, 1996
Creator: Strickland, G.C., Westinghouse Hanford
Partner: UNT Libraries Government Documents Department

Pen Branch delta expansion

Description: Since 1954, cooling water discharges from K Reactor ({anti X} = 370 cfs {at} 59 C) to Pen Branch have altered vegetation and deposited sediment in the Savannah River Swamp forming the Pen Branch delta. Currently, the delta covers over 300 acres and continues to expand at a rate of about 16 acres/yr. Examination of delta expansion can provide important information on environmental impacts to wetlands exposed to elevated temperature and flow conditions. To assess the current status and predict future expansion of the Pen Branch delta, historic aerial photographs were analyzed using both basic photo interpretation and computer techniques to provide the following information: (1) past and current expansion rates; (2) location and changes of impacted areas; (3) total acreage presently affected. Delta acreage changes were then compared to historic reactor discharge temperature and flow data to see if expansion rate variations could be related to reactor operations.
Date: February 1, 1984
Creator: Nelson, E.A.; Christensen, E.J.; Mackey, H.E.; Sharitz, R.R.; Jensen, J.R. & Hodgson, M.E.
Partner: UNT Libraries Government Documents Department

Final Remediation Report for the K-Area Bingham Pump Outage Pit (643-1G)

Description: The K-Area Bingham Pump Outage Pit (K BPOP) Building Number 643-1G, is situated immediately south and outside the K-Reactor fence line and is approximately 400 feet in length and 60 feet in width. For the K BPOP operable unit, the Land Use Control (LUC) objectives are to prevent contact, removal, or excavation of buried waste in the area and to preclude residential use of the area.
Date: June 18, 2002
Creator: Morganstern, M.
Partner: UNT Libraries Government Documents Department

Feasibility study 100 K East Area water purification pools fish-rearing program

Description: As part of the feasibility study, a design analysis was conducted to determine the usefulness of the existing sand filters and associated media for reuse. The sand filters which were studied for potential reuse are located on the northern end of the 100-K East Area water filtration plant on the Hanford Site. This plant is located about one- half mile from the Columbia River. The sand filters were originally part of a system which was used to provide cooling water to the nearby plutonium production K Reactors. This Cold War operation took place until 1971, at which time the K Reactors were closed for eventual decontamination and decommissioning. Recently, it was decided to study the concept of putting the sand filter structures back into use for fish-rearing purposes. Because the water that circulated through the water purification pools (K Pools) and associated sand filters was clean river water, there is little chance of the structures being radioactively contaminated. To date, separate K Pools have been used for raising a variety of cold water fish species, including white sturgeon and fall chinook salmon, as well as for providing potable water to the 100 K Area of the Hanford Site for fire and service water purposes.
Date: July 3, 1996
Creator: Betsch, M.D., Westinghouse Hanford
Partner: UNT Libraries Government Documents Department

Hanford`s spent nuclear fuel retrieval: an agressive agenda

Description: Starting December 1997, spent nuclear fuel that has been stored in the K Reactor Fuel Storage Basins will be retrieved over a two year period and repackaged for long term dry storage. The aging and sometimes corroding fuel elements will be recovered and processed using log handled tools and teleoperated manipulator technology. The U.S. Department of Energy (DOE) is committed to this urgent schedule because of the environmental threats to the groundwater and nearby the Columbia River.
Date: December 6, 1996
Creator: Shen, E.J., Westinghouse Hanford
Partner: UNT Libraries Government Documents Department

Axial power monitor rod issues and resolution for K-14.1

Description: A recent concern arose over the treatment of uncertainty associated with the K-Reactor axial power monitors (APMs). There are nine axial power monitor rods located at various positions in the K-Reactor core. By comparing the output of one sensor near the top of the rod to the output of another sensor near the bottom of the rod, the relative ratio of the neutron flux from the top to the bottom of the core can be determined. This ratio is called the roof-top-ratio (RTR) and is the output of a top sensor (Sensor 2) divided by the output of a bottom sensor (Sensor 6). The RTR is important to the safety analyses because when the RTR is maintained within certain ranges, the severity of reactivity transients is limited. There are uncertainties associated with the equipment`s ability to measure the true roof top ratio. It was determined recently that sufficient uncertainty was not accounted for either in reactor operation or in the safety analyses. The concern about uncertainty was addressed for three separate issues. One issue dear with the linear response of the sensors for power ranges planned for K-Reactor operation. The second issue dear with overall uncertainty in the RTR channel. The third issue dear with apparent large ranges in confidence bands for the RTR at low reactor powers as represented by original vendor data. Plots of sparse vendor data indicated unacceptably large uncertainties in RTR would have to be accounted for at the power ranges planned for K-Reactor operation. These concerns were brought to management`s attention through the existing procedures for notification, irrespective of their potential impact on the restart schedule. Analyses have been completed to resolve the APM issues described above, and work is progressing to take the needed steps to change operational procedures.
Date: May 1, 1992
Creator: Easterling, T.C.; Fields, C.C.; Hightower, N.T. III; Wooten, L.A.; Andre, S.K.; Apperson, C.E. et al.
Partner: UNT Libraries Government Documents Department

Demonstration of plasma in-situ vitrification at the K-Reactor seepage basin (904-65G)

Description: The Savannah River Technology Center at SRS had begun investigating the possibility of utilizing a plasma torch for ``bottoms up`` in-situ vitrification and had funded pilot plant scale testing at the Georgia Institute of Technology (GIT) and at Clemson University. By the spring of 1996, the GIT trials had indicated that the process was potentially viable for vitrification of SRS soils but that the process needed to be validated on a clean site at a near production scale, before deployment into a radioactive environment could be contemplated. Environmental Restoration Division organized this demonstration at a clean location adjacent to the 904-65G, K-Reactor Seepage basin with the objectives of: developing realistic cost/effectiveness data for evaluation of the process against other competing remediation technologies such as soil grouting; developing the engineering data necessary for possible subsequent full scale deployment at an SRS radiologically contaminated waste unit; and evaluating commercially available non-intrusive subsurface monitoring techniques as potential methods for regulatory compliance verification. This Interim Technical Report provides a preliminary description of the demonstration with conclusions and recommendations based on observations made during the period of the demonstration. A detailed engineering report will be compiled in the near future providing all the data pertaining to the demonstration, together with the cost comparisons, product quality determinations and engineering recommendations for future actions.
Date: December 4, 1996
Creator: Blundy, R.F.; Zionkowski, P.; Schumacher, R.F. & Herman, D.T.
Partner: UNT Libraries Government Documents Department

Pen Branch stream corridor and Delta Wetlands change assessment

Description: Airborne multispectral scanner data from 1987 to 1991 covering the Pen Branch corridor and delta at SRS were utilized to provide a detailed change detection analysis. The multispectral data were geo-referenced to a Universal Transverse Mercator projection using finite element registration. Each year was then classified into eleven different landcover categories, and the yearly changes in each landcover category were analyzed. The decrease in operations of K Reactor in 1988 has resulted in drying of the corridor and delta. This has led to the decline of nonpersistent vegetation and the increase of persistent vegetation. Cattails, willow, and bottomland hardwoods, in particular, have grown to dominate the corridor and most of the delta.
Date: June 1, 1995
Creator: Blohm, J.D.
Partner: UNT Libraries Government Documents Department

RELIABILITY of FUEL ASSEMBLY EFFLUENT TEMPERATURES UNDER L0CA/LOPA CONDITIONS

Description: The purpose of this study was to ascertain whether or not the K-Reactor safety computers could calculate primarily false positive, but also false negative, and ''on-scale'' misleading fuel assembly average effluent temperatures (AETs) due to relatively large temperature changes in or flooding of the -36 foot elevation isothermal box during a LOCA/LOPA.
Date: June 21, 1999
Creator: Sachs, A.D.
Partner: UNT Libraries Government Documents Department

Thermal Analysis of the SAFKEG Package for Long Term Storage

Description: Interim plutonium storage for up to 10 years in the K-reactor building is currently being planned at Savannah River Site (SRS). SAFKEG package could be used to store Pu metal and oxide (PuO2) in the K-reactor complex with other packagings like 9975. The SAFKEG is designed for carrying Type-B materials across the DOE complex and meets the 10CFR71 requirements. Thermal analyses were performed to ensure that the temperatures of the SAFKEG components will not exceed their temperature limits under the K-reactor storage conditions. Thermal analyses of the SAFKEG packaging with three content configurations using BNFL 3013 outer container (Rocky Flats, SRS bagless transfer cans, and BNFL inner containers) were performed for storage of PuO2 and plutonium metal
Date: January 10, 2005
Creator: NARENDRA, GUPTA
Partner: UNT Libraries Government Documents Department

EVALUATION OF ACTIVATION PRODUCTS IN REMAINING IN REMAINING K-, L- AND C-REACTOR STRUCTURES

Description: An analytic model and calculational methodology was previously developed for P-reactor and R-reactor to quantify the radioisotopes present in Savannah River Site (SRS) reactor tanks and the surrounding structural materials as a result of neutron activation of the materials during reactor operation. That methodology has been extended to K-reactor, L-reactor, and C-reactor. The analysis was performed to provide a best-estimate source term input to the Performance Assessment for an in-situ disposition strategy by Site Decommissioning and Demolition (SDD). The reactor structure model developed earlier for the P-reactor and R-reactor analyses was also used for the K-reactor and L-reactor. The model was suitably modified to handle the larger Creactor tank and associated structures. For all reactors, the structure model consisted of 3 annular zones, homogenized by the amount of structural materials in the zone, and 5 horizontal layers. The curie content on an individual radioisotope basis and total basis for each of the regions was determined. A summary of these results are provided herein. The efficacy of this methodology to accurately predict the radioisotopic content of the reactor systems in question has been demonstrated and is documented in Reference 1. As noted in that report, results for one reactor facility cannot be directly extrapolated to other SRS reactors.
Date: September 30, 2010
Creator: Vinson, D. & Webb, R.
Partner: UNT Libraries Government Documents Department

Revised STREAM code benchmarking with 1991 K-reactor tritiated aqueous release incident

Description: The transport and diffusion module of the WIND System aqueous emergency response program (STREAM code) was replaced with the EPA WASP5 code. A set of input data was developed to model the transport of pollutants from a release point in K-Area to Savannah, Georgia through Indian Grave Branch, Pen Branch, the SRS swamp, Steel Creek, and the Savannah River. To evaluate the modifications to the STREAM code, data from an accidental release of tritiated water from K-Reactor in 1991 were used for benchmarking. A leak in a heat exchanger allowed a small amount of reactor coolant water to be released to cooling streams onsite, eventually reaching the Savannah River. Measurements of tritium concentration were taken at several downstream locations during the release. The results show that the revised STREAM code overpredicts the peak concentrations by 3 to 15%, which is comparable to the measurement uncertainty (one standard deviation). The revised STREAM code underpredicts the transport times of the concentration peak by 18 to 37%. The discrepancies in the travel time could result from uncertainties in the start of the release. The revised STREAM code performed well in simulating both the timing and the magnitude of the maximum observed tritium concentration. This gives confidence that the code can perform well both for emergency response and other engineering or safety analyses
Date: April 25, 1996
Creator: Chen, K.F.
Partner: UNT Libraries Government Documents Department

Assessment of Pen Branch delta and corridor vegetation changes using multispectral scanner data 1992--1994

Description: Airborne multispectral scanner data were used to monitor natural succession of wetland vegetation species over a three-year period from 1992 through 1994 for Pen Branch on the Savannah River Site in South Carolina. Image processing techniques were used to identify and measure wetland vegetation communities in the lower portion of the Pen Branch corridor and delta. The study provided a reliable means for monitoring medium- and large-scale changes in a diverse environment. Findings from the study will be used to support decisions regarding remediation efforts following the cessation of cooling water discharge from K reactor at the Department of Energy`s Savannah River Site in South Carolina.
Date: January 1, 1996
Partner: UNT Libraries Government Documents Department

Savannah River Site production reactor technical specifications. K Production Reactor

Description: These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This report describes requirements on thermal-hydraulic limits; limiting conditions for operation and surveillance for the reactor, power distribution control, instrumentation, process water system, emergency cooling and emergency shutdown systems, confinement systems, plant systems, electrical systems, components handling, and special test exceptions; design features; and administrative controls.
Date: February 1, 1996
Partner: UNT Libraries Government Documents Department

Criticality safety evaluation for K Area Disassembly Basin cleanup

Description: Preparations are currently being made to remove sludge from the Disassembly Basin in all reactor areas. Because this sludge contains fissile isotopes, it is necessary to perform a criticality safety evaluation for the planned activities. A previous evaluation examined the criticality safety aspects of the sludge removal process for L Area. This document addresses the criticality safety aspects of the K Area Disassembly Basin cleanup work. The K Area Disassembly Basin cleanup will involve, as a first step, pumping the basin sludge into the Monitor Basin portion of the Disassembly Basin. From the Monitor Basin, the sludge will be pumped into tanks or containers for permanent disposition. The criticality safety evaluation discussed in this document covers the transfer of the sludge to the Monitor Basin.
Date: February 1, 1994
Creator: Rosser, M.A.
Partner: UNT Libraries Government Documents Department

Safety Evaluation Report Restart of K-Reactor Savannah River Site

Description: In April 1991, the Department of Energy (DOE) issued DOE/DP-0084T, Safety Evaluation Report Restart of K-Reactor Savannah River Site.'' The Safety Evaluation Report (SER) documents the results of DOE reviews and evaluations of the programmatic aspects of a large number of issues necessary to be satisfactorily addressed before restart. The issues were evaluated for compliance with the restart criteria included in the SER. The results of those evaluations determined that the restart criteria had been satisfied for some of the issues. However, for most of the issues at least part of the applicable restart criteria had not been found to be satisfied at the time the evaluations were prepared. For those issues, open or confirmatory items were identified that required resolution. In August 1991, DOE issued DOE/DP-0090T, Safety Evaluation Report Restart of K-Reactor Savannah River Site Supplement 1.'' That document was the first Supplement to the April 1991 SER, and documented the resolution of 62 of the open items identified in the SER. This document is the second Supplement to the April 1991 SER. This second SER Supplement documents the resolution of additional open times identified in the SER, and includes a complete list of all remaining SER open items. The resolution of those remaining open items will be documented in future SER Supplements. Resolution of all open items for an issue indicates that its associated restart criteria have been satisfied, and that DOE concludes that the programmatic aspects of the issue have been satisfactorily addressed.
Date: October 1, 1991
Partner: UNT Libraries Government Documents Department

Heat exchanger restart evaluation

Description: On December 24, 1991, the K-Reactor was in the shutdown mode with full AC process water flow and full cooling water flow. Safety rod testing was being performed as part of the power ascension testing program. The results of cooling water samples indicated tritium concentrations higher than allowable. Further sampling and testing confirmed a Process Water System to Cooling Water System leak in heat exchanger 4A (HX 4A). The heat exchanger was isolated and the plant shutdown. Heat exchanger 4kA was removed from the plant and moved to C-Area prior to performing examinations and diagnostic testing. This included locating and identifying the leaking tube or tubes, eddy current examination of the leaking tube and a number of adjacent tubes, visually inspecting the leaking tube from both the inside as well as the area surrounding the failure mechanism. In addition ten other tubes that either exhibited eddy current indications or would represent a baseline condition were removed from heat exchanger 4A for metallurgical examination. Additional analysis and review of heat exchanger leakage history was performed to determine if there are any patterns which can be used for predictive purposes. Compensatory actions have been taken to improve the sensitivity and response time to any future events of this type. The results of these actions are summarized herein.
Date: February 28, 1992
Creator: Morrison, J.M.; Hirst, C.W. & Lentz, T.F.
Partner: UNT Libraries Government Documents Department

Analysis of coolability of the control rods of a Savannah River Site production reactor with loss of normal forced convection cooling

Description: An analytical study of the coolability of the control rods in the Savannah River Site (SRS) K-Production Reactor under conditions of loss of normal forced convection cooling has been performed. The study was performed as part of the overall safety analysis of the reactor supporting its restart. The analysis addresses the buoyancy-driven flow over the control rods that occurs when forced cooling is lost, and the limit of critical heat flux that sets the acceptance criteria for the study. The objective of the study is to demonstrate that the control rods will remain cooled at powers representative of those anticipated for restart of the reactor. The study accomplishes this objective with a very tractable simplified analysis for the modest restart power. In addition, a best-estimate calculation is performed, and the results are compared to results from sub-scale scoping experiments. 5 refs.
Date: January 1, 1992
Creator: Easterling, T.C.; Hightower, N.T. (Westinghouse Savannah River Co., Aiken, SC (United States)); Smith, D.C. & Amos, C.N. (Science Applications International Corp., Albuquerque, NM (United States))
Partner: UNT Libraries Government Documents Department

Automatic diagnosis of alarms: a system to improve operator emergency response

Description: A system is being developed at the Savannah River Plant to help reactor operators respond to multiple alarms in a developing incident situation. The need for such systems has becme evident in recent years, particularly after the Three Mile Island incident.
Date: January 1, 1980
Creator: Olson, H P; Gimmy, K L; Nomm, E & Finley, R H
Partner: UNT Libraries Government Documents Department