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Seismic review of the R. E. Ginna Nuclear Power Plant as part of the Systematic Evaluation Program for the Nuclear Regulatory Commission

Description: This paper is a progress report on work at the Lawrence Livermore National Laboratory (LLNL) to perform a limited seismic reassessment of the Robert E. Ginna Nuclear Power Plant. The reassessment is being done for the Nuclear Regulatory Commission (NRC) as part of the Systematic Evaluation Program. The reassessment focuses generally on the reactor coolant pressure boundary and on those systems and components necessary to shut down the reactor safely and to maintain it in a safe shutdown conditi… more
Date: May 27, 1980
Creator: Murray, R. C.; Nelson, T. A.; Ng, D. S.; Liaw, C. Y.; Levin, H. A. & Cheng, T. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Impedance calculations for power cables to primary coolant pump motors

Description: The LOFT primary system motor generator sets are located in Room B-239 and are connected to the primary coolant pumps by means of a power cable. The calculated average impedance of this cable is 0.005323 ohms per unit resistance and 0.006025 ohms per unit reactance based on 369.6 kVA and 480 volts. The report was written to show the development of power cable parameters that are to be used in the SICLOPS (Simulation of LOFT Reactor Coolant Loop Pumping System) digital computer program as writte… more
Date: October 27, 1977
Creator: Hegerhorst, K.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization of Nuclear Fuel using Multivariate Statistical Analysis

Description: Various combinations of reactor type and fuel composition have been characterized using principle components analysis (PCA) of the concentrations of 9 U and Pu isotopes in the 10 fuel as a function of burnup. The use of PCA allows the reduction of the 9-dimensional data (isotopic concentrations) into a 3-dimensional approximation, giving a visual representation of the changes in nuclear fuel composition with burnup. Real-world variation in the concentrations of {sup 234}U and {sup 236}U in the … more
Date: November 27, 2007
Creator: Robel, M; Robel, M; Robel, M; Kristo, M J & Kristo, M J
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SHIELDING ANALYSIS FOR X-RAY SOURCES GENERATED IN TARGET CHAMBER OF THE NATIONAL IGNITION FACILITY

Description: Prompt doses from x-rays generated as result of laser beam interaction with target material are calculated at different locations inside the National Ignition Facility (NIF). The maximum dose outside a Target Chamber diagnostic port is {approx} 1 rem for a shot utilizing the 192 laser beams and 1.8 MJ of laser energy. The dose during a single bundle shot (8 laser beams) drops to {approx} 40 mrem. Doses calculated outside the Target Bay doors and inside the Switchyards (except for the 17 ft.-6 i… more
Date: March 27, 2008
Creator: Khater, H Y; Brereton, S J & Singh, M S
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Space Nuclear Power Plant Pre-Conceptual Design Report, For Information

Description: This letter transmits, for information, the Project Prometheus Space Nuclear Power Plant (SNPP) Pre-Conceptual Design Report completed by the Naval Reactors Prime Contractor Team (NRPCT). This report documents the work pertaining to the Reactor Module, which includes integration of the space nuclear reactor with the reactor radiation shield, energy conversion, and instrumentation and control segments. This document also describes integration of the Reactor Module with the Heat Rejection segment… more
Date: January 27, 2006
Creator: Levine, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium technology activities at HEDL in support of fast reactor development and the FFTF

Description: Activities of the Hanford Engineering Development Laboratory are presented. A brief description of FFTF and some highlights of reactor operations are reviewed. The sodium technology work at HEDL is summarized by discussing several facets of the program and their tie-ins to breeder reactor development.
Date: February 27, 1984
Creator: Atwood, J.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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PMS: What are you getting for your money

Description: The development and effectiveness of a Performance Measurement System (PMS) for contractors at Hanford Engineering Development Laboratory are discussed. The system was developed in particular for the FFTF project but has been extended to other areas.
Date: September 27, 1978
Creator: Rigney, R. A. & Campbell, R. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Category I structures program. [PWR; BWR]

Description: The objective of the Category I Structure Program is to supply experimental and analytical information needed to assess the structural capacity of Category I structures (excluding the reactor cntainment building). Because the shear wall is a principal element of a Category I structure, and because relatively little experimental information is available on the shear walls, it was selected as the test element for the experimental program. The large load capacities of shear walls in Category I str… more
Date: October 27, 1981
Creator: Endebrock, E.G. & Dove, R.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

LOFT fuel prototypes, models, and mockups

Description: The report provides a list of and information concerning the prototypes, models, and mockups that were constructed for LOFT Fuel design verification tests, proof-of-fabrication demonstrations, and operator training qualifications.
Date: July 27, 1978
Creator: Russell, M.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FFTF operator training

Description: The qualifications required and the training received by FFTF operators are described. The training includes sodium fill training and cold plant qualification. Requirements for supervisors are also outlined. Arrangement of personnel at FFTF is described. Requalification training and recertification are considered. (DLC)
Date: September 27, 1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT core inlet and outlet flow arrangement diagrams

Description: The purpose of the report is to show the flow path and flow measurement device arrangements in the LOFT core inlet and outlet regions. The assembly composites are diagrammed in detail and are useful in understanding the flow distributions upstream and downstream of the core region.
Date: July 27, 1978
Creator: Russell, M.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Survey of neutrons inside the containment of a pressurized water reactor

Description: A neutron survey was made inside the containment of the Farley Nuclear Plant, Alabama Power and Light Company, Dothan, Alabama, in November 1977. The survey was made to determine the spectra of leakage neutrons and to evaluate the accuracy of albedo neutron dosimeters and a 9-in.-diameter sphere rem meter. The survey also covered variations in the neutron spectra, the ratio of gamma-to-neutron dose rates, and the thermal neutron component of the neutron dose.
Date: September 27, 1978
Creator: Hankins, D.E & Griffith, R.V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Alternative oxide fuel pellet fabrication for irradiation testing. [LMFBR]

Description: Fabrication of experimental breeder reactor fuel pellets by the common cold-press-and-sinter technique for irradiation testing in EBR-II is discussed. Fuel types include mixed thoria-plutonia, UO/sub 2/ enriched with 22 weight percent /sup 233/U in U, UO/sub 2/ enriched with thirty-four weight percent /sup 235/U in U, and mixed urania-plutonia.
Date: October 27, 1978
Creator: Rasmussen, D. E.; Jentzen, W. R. & McCord, R. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

LOFT drag-disc turbine tansducer shroud and cover weld analysis and evaluation

Description: The results are presented of stress analysis and evaluation of the drag-disc turbine transducer (DTT) shroud and cover welds used in the Loss-of-Fluid Test (LOFT) facility. The analysis concerns LOFT DTTs currently installed and/or planned for use in future experiments by LOFT Experimental Measurements Branch personnel. Thermal/hydraulic conditions for Experiments L1-5 and L2-4 (for all nuclear tests) were used to predict the loads experienced by the various shroud and cover welds. The results … more
Date: November 27, 1978
Creator: Martinell, J.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Functional Analysis and Thermal-Hydraulics Program Plan

Description: The purpose of this document is to set forth the Program Plan for the Functional Analysis and Thermal-Hydraulics (FA TH) Program (herein after referred to as the [open quotes]Program[close quotes]) for the 5 year period covering fiscal years 1992 thru 1996. Specifically, the actions planned by the Safety Analysis Group (SAG) of the Reactor Safety Research Section within SRTC will be identified, defined, and a schedule and resource projection presented. This document will be used by the Reactor … more
Date: March 27, 1992
Creator: Paik, I.K.; Lord, R. & Parks, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LPWR fuel assembly characteristics

Description: The purpose of the report is to document the LPWR fuel assembly characteristics from which the LOFT fuel bundle material and dimension design choices were derived.
Date: July 27, 1978
Creator: Russell, M.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HAZARDS SUMMARY REPORT FOR THE ARMY PACKAGE POWER REACTOR

Description: The APPR-I is described and the various hazards are reviewed. Because of the reactor's location near the nation's Capitol, containment is of the utmost importance. The maximum energy release in any possible accident is 7.4 million Btu's which is completely contained within a 7/8 inch thick steel cylindrical shell with hemispherical ends. The vapor container is 60 ft high and 32 ft in diameter and is lined on the inside with 2 ft of reinforced concrete which provides missile prote… more
Date: July 27, 1955
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE FINAL DEMISE OF EAST TENNESSEE TECHNOLOGY PARK BUILDING K-33 Health Physics Society Annual Meeting West Palm Beach, Florida June 27, 2011

Description: Building K-33 was constructed in 1954 as the final section of the five-stage uranium enrichment cascade at the Oak Ridge Gaseous Diffusion Plant (ORGDP). The two original building (K-25 and K-27) were used to produce weapons grade highly enriched uranium (HEU). Building K-29, K-31, and K-33 were added to produce low enriched uranium (LEU) for nuclear power plant fuel. During ORGDP operations K-33 produced a peak enrichment of 2.5%. Thousands of tons of reactor tails fed into gaseous diffusion p… more
Date: June 27, 2011
Creator: King, David A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

9975 SHIPPING PACKAGE LIFE EXTENSION SURVEILLANCE PROGRAM RESULTS SUMMARY

Description: Results from the 9975 shipping package Storage and Surveillance Program at the Savannah River Site (SRS) are summarized for justification to extend the life of the 9975 packages currently stored in the K-Area Complex (KAC). This justification is established with the stipulation that surveillance activities will continue throughout the extended time to ensure the continued integrity of the 9975 materials of construction and to further understand the currently identified degradation mechanisms. T… more
Date: May 27, 2011
Creator: Dunn, K.; Daugherty, W.; Hackney, B.; Hoffman, E. & Skidmore, E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1976. [Graphite and fuel irradiations; fission product release]

Description: The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and the data are presented in tables, graphs, and photographs.
Date: December 27, 1976
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design criteria -- Modification of fuel element test facilities. 1706-KER Project CGI-839

Description: The following criteria outlines the basis, objectives, and fundamental methods that shall govern the preparation of final design for ``Project CGI-839, Modification to Fuel Element Test Facilities -- 1706 KER.`` These modifications will provide the equipment to test NPR size fuel elements in the KER recirculating loops. The 1706-KER Recirculation Test Facility of KE Reactor is operated to obtain experimental data regarding high temperature reactor coolant technology and high temperature fuel el… more
Date: August 27, 1959
Creator: Rudock, E. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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