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Surveillance and prediction methods for the plutonium limit in the K-East Fuel Storage Basin Sandfilter Backwash Pit

Description: Methods to predict and measure the amount of plutonium added to the 105-K East fuel storage basin sandfilter backwash pit have been developed. The bases for the methods and an evaluation of available data used in the methods are described.
Date: June 1, 1995
Creator: Harris, R.A.
Partner: UNT Libraries Government Documents Department

USA/FBR program fast flux test facility startup physics and reactor characterization methods and results

Description: Final confirmation of much of the engineering mockup work has been achieved in FTR zero-power experiments in February, 1980, and in power demonstration performed in December, 1980, and March, 1981. Final in-core low-power and high-power irradiation of spatially distributed radioactivants will be completed late in 1981. This paper describes physics experiments and present summaries of the extensive results accumulated to date. 53 figures.
Date: September 1, 1981
Creator: Bennett, R.A.; Harris, R.A. & Daughtry, J.W.
Partner: UNT Libraries Government Documents Department

Sampling and Analysis Plan for canister liquid and gas sampling at 105-KW fuel storage basin

Description: This Sampling and Analysis Plan (SAP) details the sampling and analyses to be performed on fuel canisters transferred to the Weasel Pit of the 105-KW fuel storage basin. The radionuclide content of the liquid and gas in the canisters must be evaluated to support the shipment of fuel elements to the 300 Area in support of the fuel characterization studies (Abrefah, et al. 1994, Trimble 1995). The following sections provide background information and a description of the facility under investigation, discuss the existing site conditions, present the constituents of concern, outline the purpose and scope of the investigation, outline the data quality objectives (DQO), provide analytical detection limit, precision, and accuracy requirements, and address other quality assurance (QA) issues.
Date: March 1, 1995
Creator: Harris, R.A.; Green, M.A.; Makenas, B.J. & Trimble, D.J.
Partner: UNT Libraries Government Documents Department

Validation and configuration management plan for the KE basins KE-PU spreadsheet code

Description: This report provides documentation of the spreadsheet KE-PU software that is used to verify compliance with the Operational Safety Requirement and Process Standard limit on the amount of plutonium in the KE-Basin sandfilter backwash pit. Included are: A summary of the verification of the method and technique used in KE-PU that were documented elsewhere, the requirements, plans, and results of validation tests that confirm the proper functioning of the software, the procedures and approvals required to make changes to the software, and the method used to maintain configuration control over the software.
Date: March 11, 1996
Creator: Harris, R.A.
Partner: UNT Libraries Government Documents Department

Reactivity analysis of core distortion effects in the FFTF

Description: Three main conclusions can be drawn from this work. For the FFTF and similar liquid metal fast reactors: (1) A simple ring-wise worth gradient does not adequately describe distortion reactivity effects of heterogeneous hexagonal components. (2) The chopped cosine-squared model for the axial shape of the distortion reactivity is not completely correct; the axial shape depends on radial position. (3) The presence of control rods in the core increases (in the negative direction) distortion reactivity, however, this effect is not large. The CORDIS code represents a cost efficient reactivity model which accounts for the core heterogeneity and control rod effects and also contains an improved axial model. Because of heterogeneity and control rod effects, it is important to calculate distortion reactivity with a comprehensive model such as the CORDIS code.
Date: May 1, 1981
Creator: Knutson, B.J.; Lucoff, D.M.; Harris, R.A. & Hecht, S.L.
Partner: UNT Libraries Government Documents Department

Initial physics measurements on FFTF

Description: Initial criticality of the Fast Flux Test Facility (FFTF) was achieved on February 9, 1980 at 3:45 p.m. During the period November 27, 1979 to March 8, 1980, fuel was loaded into the FFTF core, initial criticality was achieved, and several subcritical physics measurements were performed. The data obtained from initial FFTF nuclear operation are presented. Specifically, the absolute and relative neutron count rates were predicted for the bulk of the seventy-three fuel loadings of FFTF. Agreement between predicted and observed values is illustrated. Severe variations of fission chamber detection efficiency in the reactor shield is contrasted with that near the core center. Control rod worths, measured by the rod drop inverse kinetics method, are compared with predictions based upon Engineering Mockup Critical (EMC) evaluations. Control rod reactivity worth curves measured by rod run-in inverse kinetics are given.
Date: January 1, 1980
Creator: Bennett, R.A.; Daughtry, J.W.; Harris, R.A.; Jones, D.H.; King, T.L.; Midgett, J.C. et al.
Partner: UNT Libraries Government Documents Department

Nuclear startup, testing and core management of the FTR

Description: The Fast Test Reactor (FTR) is a sodium-cooled, mixed-oxide-fueled, 400 MW(Th) fast reactor designed for irradiation testing of FB fuels and materials. The reactor is located near Richland, Washington, and is operated by the Westinghouse Hanford Company for the US Department of Energy. The FTR is presently undergoing nonnuclear startup tests, in preparation for the initial fuel loading. The reactor is provided with special irradiation facilities to enhance its experimental capabilities.
Date: August 1, 1979
Creator: Bennett, R. A.; Daughtry, J. V.; Harris, R. A.; Jones, D. H.; Nelson, J. W.; Rawlins, J. A. et al.
Partner: UNT Libraries Government Documents Department

Quality assurance/quality control summary report on phase 2 of the Clinch River remedial investigation at the Oak Ridge Reservation, Oak Ridge, Tennessee

Description: Quality assurance (QA) objectives for Phase 2 were that (1) scientific data generated would withstand scientific and legal scrutiny; (2) data would be gathered using appropriate procedures for sample collection, sample handling and security, chain of custody, laboratory analyses, and data reporting; (3) data would be of known precision and accuracy; and (4) data would meet data quality objectives defined in the Phase 2 Sampling and Analysis Plan. A review of the QA systems and quality control (QC) data associated with the Phase 2 investigation is presented to evaluate whether the data were of sufficient quality to satisfy Phase 2 objectives. The data quality indicators of precision, accuracy, representativeness, comparability, completeness, and sensitivity were evaluated to determine any limitations associated with the data. Data were flagged with qualifiers that were associated with appropriate reason codes and documentation relating the qualifiers to the reviewer of the data. These qualifiers were then consolidated into an overall final qualifier to represent the quality of the data to the end user. In summary, reproducible, precise, and accurate measurements consistent with CRRI objectives and the limitations of the sampling and analytical procedures used were obtained for the data collected in support of the Phase 2 Remedial Investigation.
Date: December 1, 1996
Creator: Holladay, S.K.; Anderson, H.M.; Benson, S.B.; Bevelhimer, M.S.; Brandt, C.C.; Chavannes, C.M. et al.
Partner: UNT Libraries Government Documents Department