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Sensitivity and uncertainty analysis for functionals of the time-dependent nuclide density field. [ORIGEN-A]

Description: An approach to extend the present ORNL sensitivity program to include functionals of the time-dependent nuclide density field is developed. An adjoint equation for the nuclide field was derived previously by using generalized perturbation theory; the present derivation makes use of a variational principle and results in the same equation. The physical significance of this equation is discussed and compared to that of the time-dependent neutron adjoint equation. Computational requirements for de… more
Date: April 1, 1978
Creator: Williams, M.L. & Weisbin, C.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of fuel relocation for the NRC/PNL Halden assemblies IFA-431, IFA-432, and IFA-513

Description: The effects of the thermally-induced cracking and subsequent relocation of UO/sub 2/ fuel pellets on the thermal and mechanical behavior of light-water reactor fuel rods during irradiation are quantified in this report. Data from the Nuclear Regulatory Commission/Pacific Northwest Laboratory Halden experiments on instrumented fuel assemblies (IFA) IFA-431, IFA-432, and IFA-513 are analyzed. Beginning-of-life in-reactor measurements of fuel center temperatures, linear heat ratings, and cladding … more
Date: April 1, 1980
Creator: Williford, R. E.; Mohr, C. L.; Lanning, D. D.; Cunningham, M. E.; Rausch, W. N. & Bradley, E. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Final report

Description: The present study was designed to identify the impact of maintenance and testing (M and T) upon the safety of LWR power plants. The study involved data extraction from various sources reporting safety-related and operation-related nuclear power plant experience. Primary sources reviewed, including Licensee Event Reports (LER's) submitted to the NRC, revealed that only ten percent of events reported could be identified as M and T problems. The collected data were collated in a manner that w… more
Date: April 1, 1980
Creator: Husseiny, A. A.; Sabri, Z. A. & Turnage, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stress analysis of ultrasonic density detector for LOFT core inlet steady-state and LOCE conditions. Supplement 1

Description: The UDD sensor bar with modified cross-section (0.0938-in. thick by 0.25-in. high overall) was analyzed to determine its resonant frequencies. Thermal and fluid-induced stresses due to steady-state and LOCE loads were also calculated. The sensor bar was shown not to be subject to vortex-shedding lock-in and was shown to meet applicable criteria of the ASME Boiler and Pressure Vessel Code. Seismic loads are insignificant compared to fluid loads.
Date: April 25, 1979
Creator: Mosby, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Part II. Final report

Description: Information is presented concerning overview of literature relating to radiation exposure and operating experience; details of LWR-MTC3 classification system; histograms for individual BWR facilities depicting frequency of M and T mode and frequency of systems and components involved with M and T problems; histograms for individual PWR facilities depicting frequency of M and T mode and frequency of systems and components involved with M and T problems; and Fortran program for M and T data clust… more
Date: April 1, 1980
Creator: Husseiny, A. A.; Sabri, Z. A. & Turnage, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of compliance with PL 92-500 Section 316(b) for the Donald C. Cook Nuclear Power Plant of the Indiana and Michigan Power Company

Description: Region III of the US Fish and Wildlife Service contracted with the Division of Environmental Impact Studies, Argonne National Laboratory, to make the 316(b) determination for the Donald C. Cook Nuclear Power Plant of the Indiana and Michigan Power Company and to make recommendations for improvement in intake design to facilitate compliance. To conduct this assessment, appropriate literature on screening systems and reports furnished by the applicant on intake design and operation and on ecologi… more
Date: April 1, 1980
Creator: Sharma, R K & Freeman, III, R F
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Seismic structural fragility investigation for the San Onofre Nuclear Generating Station, Unit 1 (Project I); SONGS-1 AFWS Project

Description: An evaluation of the seismic capacities of several of the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1) structures was conducted to determine input to the overall probabilistic methodology developed by Lawrence Livermore National Laboratory. Seismic structural fragilities to be used as input consist of median seismic capacities and their variabilities due to randomness and uncertainty. Potential failure modes were identified for each of the SONGS-1 structures included in this study by… more
Date: April 1, 1982
Creator: Wesley, D.A. & Hashimoto, P.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nondestructive verification and assay systems for spent fuels

Description: This is an interim report of a study concerning the potential application of nondestructive measurements on irradiated light-water-reactor (LWR) fuels at spent-fuel storage facilities. It describes nondestructive measurement techniques and instruments that can provide useful data for more effective in-plant nuclear materials management, better safeguards and criticality safety, and more efficient storage of spent LWR fuel. In particular, several nondestructive measurement devices are already av… more
Date: April 1, 1982
Creator: Cobb, D. D.; Phillips, J. R.; Bosler, G. E.; Eccleston, G. W.; Halbig, J. K.; Hatcher, C. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design concept and testing of an in-bundle gamma densitometer for subchannel void fraction measurements in the THTF electrically heated rod bundle. [PWR]

Description: A design concept is presented for an in-bundle gamma densitometer system for measurement of subchannel average fluid density and void fraction in rod or tube bundles. This report describes (1) the application of the design concept to the Thermal-Hydraulic Test Facility (THTF) electrically heated rod bundle; and (2) results from tests conducted in the THTF.
Date: April 1, 1982
Creator: Felde, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data report for the nondestructive examination of Turkey Point spent fuel assemblies B02, B03, B17, B41, and B43

Description: The fuel assembly sip test on all rods from assembly B17 were of sound intergrity. Visual examination showed three general regions of rod surface appearance: a dark adherent crud layer at the bottom of the rod, black spalling crud layers in the middle, and a spotty gray loose powdery coating with dark crud or oxide underneath towards the top. Rod lengths varied from 152.395 inches to 152.707 inches. Maximum rod bow measurements for rods G9, I9, and G7 were 0.038 to 040 inch and 0.022 inch for r… more
Date: April 1, 1980
Creator: Davis, R.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Licensee Event Report (LER) compilation for month of March 1988

Description: This monthly report contains Licensee Event Report (LER) operational information that was processed into the LER data file of the Nuclear Safety Information Center (NSIC) during the one-month period identified on the cover of the document. The LERS, from which this information is derived, are submitted to the Nuclear Regulatory Commission (NRC) by nuclear power plant licensees in accordance with federal regulations. Procedures for LER reporting for revisions to those events occurring prior to 1… more
Date: April 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Creepdown of Zircaloy fuel cladding: initial tests. [BWR; PWR]

Description: The report describes the initial creepdown tests of Zircaloy fuel cladding in which the surface displacements of the specimens have been measured as a function of time. Such measurements were made with a high accuracy, high precision eddy-current device capable of operation at elevated temperatures and pressures. Tests were conducted at 371/sup 0/C (700/sup 0/F) and external pressures of 14.5 to 17.2 MPa (2100 to 2500 psig) on specimens of reactor grade Zircaloy-4 fuel cladding in the unirradia… more
Date: April 1, 1978
Creator: Hobson, D.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of optimal LWR containment design, excluding accidents more severe than Class 8

Description: Information is presented concerning the restrictive effect of existing NRC requirements; definition of possible targets for containment; possible containment systems for LWR; optimization of containment design for class 3 through class 8 accidents (PWR); estimated costs of some possible containment arrangements for PWR relative to the standard dry containment system; estimated costs of BWR containment.
Date: April 1, 1980
Creator: Cave, L. & Min, T.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Faster-than-real-time simulation of nuclear reactor accidents: the TRAC-NPA code

Description: A reactor safety code that provides faster-than-real-time capabilities greatly enhances the effectiveness of an analyst. We have developed a new version of the Transient Reactor Analysis Code, TRAC-NPA, which is capable of running many one- and three-dimensional transients faster than real time on current computers. TRAC is an Eulerian finite-difference code designed to model transient, two-phase, multidimensional, steam-water flow in nuclear reactors. TRAC-NPA is fast running both because it e… more
Date: April 1, 1985
Creator: Woodruff, S.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Technical evaluation report on the proposed amendment to the technical specifications on the reactor protection system and the engineered safety features actuation system for Ft. Calhoun, Unit No. 1

Description: This report documents the technical evaluation of the application to amend the Technical Specifications for the Ft. Calhoun Unit No. 1 Nuclear Generating Plant. The review criteria are based on the Technical Specifications of St. Lucie and Calvert Cliffs, IEEE Standards, Combustion Engineering Standard Technical Specifications, and the Code of Federal Regulations. The evaluation compares the submittal made by the licensee with the NRC staff position and the review criteria and presents the revi… more
Date: April 9, 1982
Creator: Selan, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Oxidation of spent fuel in air at 175 degree to 195 degree C

Description: Oxidation tests in dry air were conducted on four LWR spent fuels at 175{degrees} and 195{degrees}C to determine the effect of the fuel characteristics on the oxidation state likely to exist at the time leaching occurs in a potential repository. Weight changes were measured and samples were examined by XRD, ceramography, TEM, and TGA. Despite local variations in the grain boundary susceptibility to oxidation, all four fuels progressed toward an apparent endpoint at an oxygen-to-metal (O/M) rati… more
Date: April 1, 1992
Creator: Einziger, R. E.; Buchanan, H. C.; Thomas, L. E. (Pacific Northwest Lab., Richland, WA (United States)) & Stout, R. B. (Lawrence Livermore National Lab., CA (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Time and dose assessment of barge shipment and at-reactor handling of a CASTOR V/21 spent fuel storage cask

Description: This report contains the results of a time/motion analysis and a radiation dose assessment made during the receipt from barge transport and the loading of CAst iron cask for Storage and Transport Of Radioactive material (CASTOR) V/21 storage casks with spent nuclear fuel at the Surry Power Station in Virginia during 1987. The study was a cooperative effort between Pacific Northwest Laboratory (PNL) and Virginia Electric and Power Company (Virginia Power), and was funded by the US Department of … more
Date: April 1, 1992
Creator: Hostick, C.J. (Pacific Northwest Lab., Richland, WA (United States)); Lavender, J.C. (Westinghouse Hanford Co., Richland, WA (United States)) & Wakeman, B.H. (Virginia Electric and Power Co., Richmond, VA (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Commercial nuclear reactors and waste: the current status

Description: During the last five years, the declared size of the commercial light water reactor (LWR) nuclear power industry in the US has steadily decreased. As of January 1980, the total number of power plants had dropped to 191 from the 226 in December 31, 1974. At least another nine were cancelled in the last few months. This report was developed as the first of a series to track implications to waste management due to such changes in the declared size of the industry. For the presently declared size, … more
Date: April 1, 1980
Creator: Platt, A.M. & Robinson, J.V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Path to development of quantitative safety goals

Description: There is a growing interest in defining numerical safety goals for nuclear power plants as exemplified by an ACRS recommendation. This paper proposes a lower frequency limit of approximately 10/sup -4//reactor-year for design basis events. Below this frequency, down, to a small frequency such as 10/sup -5//reactor-year, safety margin can be provided by, say, site emergency plans. Accident sequences below 10/sup -5/ should not impact public safety, but it is prudent that safety research programs… more
Date: April 1, 1980
Creator: Joksimovic, V. & Houghton, W.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermal analysis of LOFT containment vessel penetrations S-5E and S-6A

Description: Thermal analysis of the LOFT containment vessel penetration S-6A was conducted for steady-state operation and blowdown transients. Penetration S-6A is a 20-inch pipe through which passes a 10-inch pipe from the steam generator containing 600/sup 0/F steam. Recommendations for penetration S-5E were based on the analysis of penetration S-6A. Penetration S-5E is an 18-inch pipe through which pass a 4-inch pipe containing the steam generator feedwater at 430/sup 0/F and a 0.5-inch pipe containing s… more
Date: April 21, 1970
Creator: Condie, K.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Time/motion observations and dose analysis of reactor loading, transportation, and dry unloading of an overweight truck spent fuel shipment

Description: This document presents observed activity durations and radiation dose analyses for an overweight truck shipment of pressurized water reactor (PWR) spent fuel from the Surry Power Station in Virginia to the Idaho National Engineering Laboratory. The shipment consisted of a TN-8L shipping cask carrying three 9-year-old PWR spent fuel assemblies. Handling times and dose analyses for at-reactor activities were completed by Virginia Electric and Power Company (Virginia Power) personnel. Observations… more
Date: April 1, 1992
Creator: Hostick, C.J. (Pacific Northwest Lab., Richland, WA (United States)); Lavender, J.C. (Westinghouse Hanford Co., Richland, WA (United States)) & Wakeman, B.H. (Virginia Electric and Power Co., Richmond, VA (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Air velocity profiles near sleeve blockages in an unheated 7 x 7 rod bundle. [PWR]

Description: Local air velocity measurements were obtained with a laser Doppler anemometer near flow blockages in an unheated 7 x 7 rod bundle. Sleeve blockages were positioned on the center nine rods to create an area reduction of 90% in the center four subchannels of the bundle. Experimental results indicated that severe flow disturbances occurred downstream from the blockage cluster but showed only minor flow disturbances upstream from the blockage. Flow reversals were detected downstream from the blocka… more
Date: April 1, 1979
Creator: Creer, J. M. & Bates, J. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Offsite dose calculation manual guidance: Standard radiological effluent controls for pressurized water reactors

Description: This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-01, which allows Radiological Effect Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological en… more
Date: April 1, 1991
Creator: Meinke, W.W. & Essig, T.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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