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MCNP photon transport benchmarking calculations performed at SRP. Revision 1

Description: Monte Carlo methods have long been used at the Savannah River Laboratory (SRL) to perform criticality calculations for many different processes. To perform transport analyses (both neutron and photon) a two-dimensional infinite lattice integral transport code (GLASS) has been used. The neutron transport portion of the code has been benchmarked against other codes and experimental data. The photon transport portion of the code, which is used to calculate gamma redistribution in the event of a loss of moderator and/or coolant, had not been benchmarked against either. For this reason, the Monte Carlo code MCNP was used to benchmark the photon transport portion of the GLASS code. Preceding this, a brief description of the geometry of the Savannah River Plant`s (SRP) reactor cores and how they were modeled using MCNP will be given.
Date: 1989-06~
Creator: White, A. M.
Partner: UNT Libraries Government Documents Department

Hydrogeological and Groundwater Flow Model for C, K, L, and P Reactor Areas, Savannah River Site, Aiken, South Carolina

Description: A regional groundwater flow model encompassing approximately 100 mi{sup 2} surrounding the C, K. L. and P reactor areas has been developed. The Reactor flow model is designed to meet the planning objectives outlined in the General Groundwater Strategy for Reactor Area Projects by providing a common framework for analyzing groundwater flow, contaminant migration and remedial alternatives within the Reactor Projects team of the Environmental Restoration Department.
Date: February 24, 1999
Creator: Flach, G.P.
Partner: UNT Libraries Government Documents Department

Buoyancy-driven flow excursions in fuel assemblies

Description: A power limit criterion was developed for a postulated Loss of Pumping Accident (LOPA) in one of the recently shut down heavy water production reactors at the Savannah River Site. These reactors were cooled by recirculating moderator downward through channels in cylindrical fuel tubes. Powers were limited to prevent a flow excursion from occurring in one or more of these parallel channels. During full-power operation, limits prevented a boiling flow excursion from taking place. At low flow rates, during the addition of emergency cooling water, buoyant forces reverse the flow in one of the coolant channels before boiling occurs. As power increases beyond the point of flow reversal, the maximum wall temperature approaches the fluid saturation temperature, and a thermal excursion occurs. The power limit criterion for low flow rates was the onset of flow reversal. To determine conditions for flow reversal, tests were performed in a mock-up of a fuel assembly that contained two electrically heated concentric tubes surrounded by three flow channels. These tests were modeled using a finite difference thermal-hydraulic code. According to code calculations, flow reversed in the outer flow channel before the maximum wall temperature reached the local fluid saturation temperature. Thermal excursions occurred when the maximum wall temperature approximately equaled the saturation temperature. For a postulated LOPA, the flow reversal criterion for emergency cooling water addition was more limiting than the boiling excursion criterion for full power operation. This criterion limited powers to 37% of historical levels.
Date: December 31, 1995
Creator: Laurinat, J.E.; Paul, P.K. & Menna, J.D.
Partner: UNT Libraries Government Documents Department

Natural Convection and Boiling for Cooling SRP Reactors During Loss of Circulation Conditions

Description: This study investigated natural convection and boiling as a means of cooling SRP reactors in the event of a loss of circulation accident. These studies show that single phase natural convection cooling of SRP reactors in shutdown conditions with the present piping geometry is probably not feasible.
Date: June 26, 2001
Creator: Buckner, M.R.
Partner: UNT Libraries Government Documents Department

Ion Chamber Compensation Tests

Description: The purpose of this report is to present the results of a series of tests performed to determine the need for gamma compensation of the ion chambers used to monitor the neutron flux in the 100 Area reactors.
Date: February 14, 2003
Creator: Mallard, R.L. Jr.
Partner: UNT Libraries Government Documents Department

Sensitivity of SRP LOCA power limit to break size and location

Description: SRP reactors are low pressure, heavy water reactors with six external process water loops that drive the coolant into an upper plenum and then downward through the assemblies. Assembly LOCA power limits are currently set in these reactors to prevent Ledinegg flow instability (FI) in any assembly flow channel. These limits are based on a postulated break area and location. This study determined the sensitivity of the power limit to the break area and location.
Date: 1989-06~
Creator: White, A. M.; Pevey, R. E. & Smith, F. G.
Partner: UNT Libraries Government Documents Department

Results of submerged sediment core sampling and analysis on Par Pond, Pond C, and L Lake: July 1995

Description: Sediment cores from shallow and deep water locations in Par Pond, Pond C, and L Lake were collected and analyzed in 1995 for radioactive and nonradioactive constituents. This core analysis was conducted to develop a defensible characterization of contaminants found in the sediments of Par Pond, Pond C, and L Lake. Mercury was the only nonradiological constituent with a nonestimated quantity that was detected above the U.S Environmental Protection Agency Region IV potential contaminants of concern screening criteria. It was detected at a depth of 0.3--0.6 meters (1.0--2.0 feet) at one location in L Lake. Cesium-137, promethium-146, plutonium-238, and zirconium-95 had significantly higher concentrations in Par Pond sediments than in sediments from the reference sites. Cobalt-60, cesium-137, plutonium-238, plutonium-239/240, and strontium-90 had significantly higher concentrations in L-Lake sediments than sediments from the reference sites.
Date: June 1, 1996
Creator: Koch, J.W. II; Martin, F.D. & Friday, G.P.
Partner: UNT Libraries Government Documents Department

E.I. duPont de Nemours & Co., Technical Division monthly progress report, January 1953

Description: This document from Savannah River Plant reports progress in January 1953. Heavy water studies include corrosion inhibitors and sulfide deposition. Reactor materials studies include uranium fuel elements and aluminium sheaths and special materials to include thorium and bismuth. Reactor technology studies include control systems, tritium production, CMX, moderator purification, concrete shield heating. Separations technology studies include Purex process, 221 building equipment, and fuel element handling.
Date: February 10, 1953
Partner: UNT Libraries Government Documents Department

E.I. duPont de Nemours & Co., Process Section Manufacturing Division, August 1956

Description: This monthly report from Savannah River Plant presents information on current activities at the 100 Area (reactors), 200 Area (separations plants), 300 Area (reactor fuels fabrication) and the 400 Area (heavy water). Also, utilities and general services present administrative, technical, and general information. The power ascension program and productivity improvement program are emphasized in the 100 Area report. Tritium processing, 200-F increased capacity, waste disposal, and the `25` process are described in the separations plant report. The increased productivity program in reactor fuels fabrication is described. And progress at the Dana plant and Savannah river plant on heavy water production is described.
Date: September 15, 1956
Partner: UNT Libraries Government Documents Department

E.I. duPont de Nemours & Co., Process Section Manufacturing Division, June 1955

Description: This document from Savannah River Plant reports progress for June 1955 in the 100, 200, 300, and 400 Areas. Information is presented on the assembly area, reactor control, reactor complex, and disassembly for the 100 Area (reactors). From the 200 Area (separations plants), progress at the solvent extraction plants is reported. Uranium - Aluminium and thorium canning are reported for the 300 area (reactor fuels fabrication). And stainless steel corrosion studies are reported for the 400 area (heavy water).
Date: July 15, 1955
Partner: UNT Libraries Government Documents Department

E.I. duPont de Nemours & Co., Process Section Manufacturing Division, November 1956

Description: This document presents monthly progress at the Savannah River Plant in the 100, 200, 300, and 400 Areas. In the 100 Area (reactors), the power ascension program, the productivity improvement program and general progress is given. Tritium processing, 200-F increased capacity, and waste disposal are reported for the solvent extraction plants in the 200 Area. The increased productivity program is reported for the 300 Area. Dana plant activities and 400-D progress are reported in the 400 area report (heavy water).
Date: December 15, 1956
Partner: UNT Libraries Government Documents Department

Engineering evaluation cost analysis for the 100-B/C area ancillary facilities at the 108-F Building

Description: In 1995, the US Department of Energy (DOE), Richland Operations Office (RL) conducted a removal site evaluation of selected facilities in the 100 Area of the Hanford Site in accordance with CERCLA and 40 Code of Federal Regulations (CFR) 300.410. The scope of the evaluation included the aboveground portions of the 108-F Biology Laboratory in the 100-F Area and all inactive ancillary buildings and structures in the 100-B/C Area, excluding the reactor building and the river outfall. Based on the evaluation, RL determined that hazardous substances in the 108-F Biology Laboratory and five of the 100-B/C Area facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. This determination was documented in an engineering evaluation/cost analysis (EE/CA) approval memorandum. The EE/CA approval memorandum is the basis on which to proceed with the performance of an EE/CA to determine the appropriate removal action. This report presents the results of the EE/CA for removal alternatives for final disposition of these six facilities. The EE/CA was conducted pursuant to the requirements of CERCLA and 40 CFR 300.415 and is intended to aid RL and the EPA in selecting a preferred removal action.
Date: October 1, 1996
Partner: UNT Libraries Government Documents Department

In Situ Stress Measurements in the NPR Hole, Volume I - Results and Interpretations

Description: This report presents the results of an investigation of the magnitudes and orientations of the in situ stresses in basement rocks beneath the Savannah River Site (SRS). Stress magnitudes were measured using the hydraulic fracturing technique. Stress orientations were obtained from the orientation of stress-induced wellbore breakouts and hydraulically-induced fractures. The measurements reported here were carried out in the New Production Reactor (NPR) hole, drilled to a total depth of 4000 feet near the center of the Savannah River Site, at roughly the location of the proposed NPR. The results obtained in this study are compared to previous stress measurements made using the same techniques in a series of shallower holes on the SRS, and discussed in the context of the regional stress field and potential seismic hazard.
Date: October 15, 2001
Creator: Moos, D.
Partner: UNT Libraries Government Documents Department

E.I. duPont de Nemours & Co., Process Section Manufacturing Division monthly report, December 1956

Description: This document form Savannah River Plant reports progress in the month of December 1956 for the 100, 200, 300, and 400 Areas. The productivity moderator program is described in the 100 (reactor) Area. Tritium processing, 200-F increased capacity, waste disposal, and the `25` plant are reported on in the 200 (separations) Area. The increased productivity program to include extended surface enriched and uranium elements is described in the 300 (reactor fuel fabrication) Area. Dana Plant operations are described in the heavy water studies.
Date: January 15, 1957
Partner: UNT Libraries Government Documents Department

Confirmatory radiological survey for the 190-C Main Pumphouse Facility decommissioning at the Hanford Site, Richland, Washington

Description: An independent assessment of remedial action activities at the 190-C Main Pumphouse Facility at the Hanford Site, Richland, Washington has been accomplished by the Oak Ridge National Laboratory Environmental Assessments Group. The purpose of the assessment was to confirm the site`s compliance with DOE applicable guidelines and provide independent measurements of the activity levels in the 190-C trenches and 105-C process water tunnels. The assessment included reviews of the Decontamination and Decommissioning Plan and data provided in the pre- and post-remedial action surveys. An on-site independent verification survey of the facility was conducted during the period of November 19--21, 1996. The independent verification survey included beta and gamma scans, smears for removable contamination, and direct measurements for beta-gamma activity in the trenches and tunnels. The same measurements and scans, with the addition of alpha measurements, were performed on the floor in the filter repair confinement area. The facility was also spot-checked for direct alpha and beta-gamma activity.
Date: June 1, 1997
Creator: Coleman, R.L. & Forbes, G.H.
Partner: UNT Libraries Government Documents Department

E.I. duPont de Nemours & Co., Process Section Manufacturing Division, September 1956

Description: This monthly report from the manufacturing division presents progress on operations at Savannah River plant. Reports are given from the reactors, separations plants, reactor fuels fabrication, and heavy water production. Administrative details are also given from utilities and general services.
Date: October 15, 1956
Partner: UNT Libraries Government Documents Department

Measurements of iodine uptake in falling water droplets

Description: The removal of gaseous iodine from air by water sprays was measured, using both ordinary water and a solution buffered to a pH near 9.5 with a carbonate mixture. The results were compared to the theoretical predictions of the I2WASH computer code. In all experiments, using both large and small spray droplets, the solution at the higher pH was approximately three times as effective at absorbing iodine from the air. This agrees with the predictions of the computer model for the smaller droplets studied. The computer code predicts no pH effect for large drops, probably because it assumes a well-mixed drop, and mixing during the fall time is too slow.
Date: 1989
Creator: Hyder, M. L.
Partner: UNT Libraries Government Documents Department

Treatment plan for protection of cultural resources for the 100-KR-4 pump-and-treat project

Description: The 100-K Reactor Area is located on the southern shore of the Columbia River at the northern edge of the Hanford Site. The K-East and K-West reactors operated from 1955 to 1971 as part of the US efforts to produce weapons grade nuclear materials. Reactor operations required the use of water from the Columbia River to cool the reactors. Occasionally, reactor equipment would malfunction causing radioactive contamination in the cooling water. On these occasions, rather than being discharged to the Columbia River, the water was discharged to a trench, approximately 1.61 km (1 mi) long, located to the east of the reactor area. This discharged cooling water, in addition to being radioactively contaminated, also contained significant quantities of chromium that had been used to prevent corrosion within the reactors, After the cooling water had been discharged into the trench, it percolated into the ground and traveled toward the Columbia River via the groundwater flow. Current interim remediation activities planned for this part of the 100-K Area are focused on protecting the Columbia River by pumping the chromium contaminated groundwater to a treatment system. The treated water will then be pumped back into the ground upstream of the trench. This document describes how the planned construction activities have been modified to protect the extremely sensitive cultural resources in the area.
Date: November 1, 1996
Partner: UNT Libraries Government Documents Department

Savannah River Technology Center monthly report, March 1995

Description: Short summaries are given on the status of projects within the Savannah River Technology Center covering the following broad topical areas: Tritium; Separations; Environmental studies; Waste management; and General. Studies listed under this last area include: Reactor support; Site robotics support; Robotics for D and D; Robotics for mixed waste operation; Integrated demonstration of an underground storage tank; and Alliance for the Advancement of Robotic Technology (AART).
Date: March 1, 1995
Partner: UNT Libraries Government Documents Department

Inadequate neutron flux monitoring

Description: Reactor shutdown operations were outside the requirements of Technical Specification DPST-TS-105-2.1, Scram Instrumentation, and Technical Standard DPSTS-105-4.02, Subcritical Operations, when data was not recorded per DPSOL 105-1223B, Neutron Flux Control Monitoring During Shutdown -- External Fission Counter Normal Mode. DPSOL 105- 1223B, Data Sheet 2, requires operations personnel to record External Fission Counter (EFC) data at 15 minute intervals. Reactor Technology Department surveillance on 6/7/89 identified that data were not recorded for three consecutive intervals on 6/6/89. Operations personnel failed to take data per the frequency required in DPSOL 105-1223B. The time period that this event occurred was during shift change; the three missed readings should have been recorded at 7:15 a.m., and 7:45 a.m. Operations personnel were seated at the external fission counter desk and maintained audio/visual monitoring of the flux while conducting the turnover. Root Cause -- Monitoring alertness of personnel was less than adequate. Monitoring requirements for the external fission counters are set per DPSOL 105- 1223B. Personnel inadvertently failed to take data per the frequency required in DPSOL 105-1223B.
Date: August 10, 1989
Creator: Rubio, G. A.
Partner: UNT Libraries Government Documents Department

Current status of H Reactor total control

Description: This document presents the total control aspects of the current blanket and central zone E-N loading at H Reactor based on the calculational parameters in Physics of E-N Load compared to Natural Uranium Load at H Reactor, D.I. Monnie, May 11, 1961. The original charge for the E-N core load at H Reactor, (19.37 in. E to 1 in. N) was found to be more reactive than desirable for maximum production efficiency. Therefore a less reactive E to N ratio (18.14 in. E to 1 in. N) has now replaced the original loading.
Date: October 15, 1961
Creator: Vaughn, A. D.
Partner: UNT Libraries Government Documents Department

New supply for canyon fire foam system

Description: The raw water supply for the B-Plant Canyon fire foam system is being replaced. The 4 inche water supply line to the foam system is being rerouted from the 6 inches raw water line in the Pipe Gallery to the 10 inches raw water main in the Operating Gallery. This document states the acceptance criteria for the flushing and testing to be performed by the contractor.
Date: January 1, 1995
Creator: Gainey, T.
Partner: UNT Libraries Government Documents Department