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850/sup 0/C VHTR plant technical description

Description: This report describes the conceptual design of an 842-MW(t) process heat very high temperature reactor (VHTR) plant having a core outlet temperature of 850/sup 0/C (1562/sup 0/F). The reactor is a variation of the high-temperature gas-cooled reactor (HTGR) power plant concept. The report includes a description of the nuclear heat source (NHS) and of the balance of reactor plant (BORP) requirements. The design of the associated chemical process plant is not covered in this report. The reactor de… more
Date: June 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NRC plan for cleanup operations at Three Mile Island Unit 2

Description: This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup … more
Date: February 1, 1982
Creator: Lo, R. & Snyder, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the results of the Midland PRA

Description: This paper presents the results of a limited review of the Midland PRA (MPRA), aimed at facilitating regulatory analyses and at providing insights into safety related plant failures. In particular, stress was laid on the root causes of accident sequences, particularly their failure modes, viz., hardware, human, maintenance, test, and repair. Because this information was difficult to extract in this detailed and sophisticated PRA (and in certain others) a special algorithm was developed to displ… more
Date: January 1, 1986
Creator: Bozoki, G. & Teichmann, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization of solids in the Three Mile Island Unit 2 Reactor defueling water: Addendum

Description: Shortly after ORNL/TM-10362 was issued, it was discovered that a series of 31 figures had been inadvertently omitted. These figures, which consist of scanning electron microscope (SEM) photographs and energy-dispersive X-ray fluorescence scans, provide significant information about the results obtained in the tests performed with water sample W3. This Addendum includes these figures. Details of and comments on the SEM photographs may be found in ORNL/TM-10362.
Date: March 1, 1988
Creator: Campbell, D.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Evaluation of liquid metal leak detection methods for the Clinch River Breeder Reactor Plant

Description: This report documents an independent review and evaluation of sodium leak detection methods described in the Clinch River Breeder Reactor Preliminary Safety Analysis Report. Only information in publicly available documents was used in making the assessments.
Date: December 1, 1977
Creator: Morris, C. J. & Doctor, S. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Computer program SCAP-BR for gamma-ray streaming through multi-legged ducts

Description: A computer program, SCAP-BR, has been developed at Burns and Roe for the gamma-ray streaming analysis through multi-legged ducts. SCAP-BR is a modified version of the single scattering code, SCAP, incorporating capabilities of handling multiple scattering and volumetric source geometries. It utilizes the point kernel integration method to calculate both the line-of-sight and scattered gamma dose rates by employing the ray tracing technique through complex shield geometries. The multiple scatter… more
Date: December 8, 1977
Creator: Byoun, T. Y.; Babel, P. J. & Dajani, A. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Field radiography using 100 Ci of Co-60 without interrupting adjacent manufacturing operations

Description: Radiography is the primary method of Nondestructive Examination recognized by the ASME B and PV Code as providing objective evidence of volumetric examination of the pressure boundary welds that are present in the Clinch River Breeder Reactor Program (CRBRP) Steam Generator. In order to support the steam generator production schedule, the radiographic examinations must be performed without interrupting any other manufacturing or inspection operations taking place within a 20-ft radius from the … more
Date: January 1, 1979
Creator: Donnelly, C.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Environmental monitoring at major U. S. Energy Research and Development Administration contractor sites: calendar year 1976. Volume 2

Description: The purpose of this compilation is to present, in a central reference document, all of the individual annual reports summarizing the results of the environmental monitoring programs conducted at each of the Energy Research and Development Administration (ERDA) sites having a potential for environmental impact or which release a significant quantity of radioactivity or nonradioactive pollutants. Data on the levels of radioactivity and nonradioactive pollutants in effluents and the environs at ea… more
Date: August 1, 1977
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Insights from an overview of four PRAs

Description: This paper summarizes the findings of an investigation of four probabilistic risk assessments (PRAs), those for Millstone 3, Seabrook, Shoreham, and Oconee 3, performed by Brookhaven National Laboratory (BNL) for the Reliability and Risk Assessment Branch of the US Nuclear Regulatory Commission (NRC). This group of four PRAs was subjected to an overview process with the basic goal of ascertaining what insights might be gained (beyond those already documented within the individual PRAs) by an in… more
Date: January 1, 1986
Creator: Fitzpatrick, R.; Arrieta, L.; Teichmann, T. & Davis, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Shielding considerations for advanced space nuclear reactor systems

Description: To meet the anticipated future space power needs, the Los Alamos National Laboratory is developing components for a compact, 100 kW/sub e/-class heat pipe nuclear reactor. The reactor uses uranium dioxide (UO/sub 2/) as its fuel, and is designed to operate around 1500 k. Heat pipes are used to remove thermal energy from the core without the use of pumps or compressors. The reactor heat pipes transfer mal energy to thermoelectric conversion elements that are advanced versions of the converters u… more
Date: January 1, 1982
Creator: Angelo, J.P. Jr. & Buden, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Exploding the myths about the fast breeder reactor

Description: This paper discusses the facts and figures about the effects of conservation policies, the benefits of the Clinch River Breeder Reactor demonstration plant, the feasibility of nuclear weapons manufacture from reactor-grade plutonium, diversion of plutonium from nuclear plants, radioactive waste disposal, and the toxicity of plutonium. The paper concludes that the U.S. is not proceeding with a high confidence strategy for breeder development because of a variety of false assumptions.
Date: January 1, 1979
Creator: Burns, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear alkali metal Rankine power systems for space applications

Description: Nucler power systems utilizing alkali metal Rankine power conversion cycles offer the potential for high efficiency, lightweight space power plants. Conceptual design studies are being carried out for both direct and indirect cycle systems for steady state space power applications. A computational model has been developed for calculating the performance, size, and weight of these systems over a wide range of design parameters. The model is described briefly and results from parametric design st… more
Date: August 1, 1986
Creator: Moyers, J. C. & Holcomb, R. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Transient thermal analysis of three fast-charging latent heat storage configurations for a space-based power system

Description: A space-based thermal storage application must accept large quantities of heat in a short period of time at an elevated temperature. A model of a lithium hydride phase change energy storage system was used to estimate reasonable physical dimensions for this application which included the use of a liquid metal heat transfer fluid. A finite difference computer code was developed and used to evaluate three methods of enhancing heat transfer in the PCM energy storage system. None of these three met… more
Date: January 1, 1988
Creator: Stovall, T. K. & Arimilli, R. V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Hot cell studies of tritium removal from and dissolution of an irradiated thoria fuel

Description: Tritium removal and dissolution studies on an irradiated thoria-based fuel were conducted in the High Level Caves at the Savannah River Laboratory (SRL). The objectives of these studies were to define the effects of key process-related parameters on tritium evolution and subsequent dissolution. The test program at SRL determined the effects on tritium removal of particle size, heating temperature, oxidation, and agitation. ThO/sub 2//UO/sub 2/ (95%/5%) fuel from the Elk River Reactor, irradiate… more
Date: January 1, 1980
Creator: Pickett, J.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization of radioactive ion exchange media waste generated at Three Mile Island

Description: The March 1979 accident at General Public Utilities Nuclear Corporation (GPUNC) Three Mile Island Nuclear Power Station Unit 2 (TMI-2), resulted in the transfer of more than 1100 m/sup 3/ of contaminated water to the auxiliary and fuel handling building. The principal sources of the water were the makeup and letdown purification system and the containment building sump. The contaminated water was processed through an ion exchange system designated as EPICOR II. The EPICOR-II System is a three-s… more
Date: October 1, 1981
Creator: Runion, T. C.; Holzworth, R. E.; Ogle, R. E.; Burton, H. M. & Bixby, W. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radiochemical analysis of the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor

Description: This report presents the analysis of radioactive elements on the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor. The plateout probe is a device which samples the primary coolant for condensible fission products. Circuit inventories of individual radionuclides are estimated from the probe analysis. The analysis shows that the radioactive contamination in the primary circuit is remarkable low, with activation product concentrations much greater than that of fissi… more
Date: June 1, 1982
Creator: Burnette, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CRBRP sodium circulating pump design evaluation

Description: The following topics are discussed: (1) primary sodium pump design concept; (2) pump level control system; (3) resolution of design problems in stress analysis, dynamics analysis, and mechanical design; (4) model testing; (5) planned performance tests; and (6) fabrication status. (DG)
Date: December 1, 1977
Creator: Marrujo, F.; Cook, M.; Manners, L. & Cothran, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Surface footprint from initial Chernobyl release as indicated by the meso-alpha MLAM (Multi-Layer Air Mass) model

Description: This document reports the results of dose calculations from the Chernobyl reactor accident in April 1986. The calculations were completed in 1987. The results are now being published to disseminate the information to an audience of potential users. This study's objective was to model the transport path of materials released during April 26 and 27, the first 48 hours of the accident. 5 refs., 15 figs.
Date: December 1, 1989
Creator: Davis, W. E.; Olsen, A. R.; Didier, B. T.; Tucker, P. E. & Damschen, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Some Scoping Experiments for a Space Reactor

Description: Some scoping experiments were performed to evaluate fuel performance in a lithium heat pipe reactor operating at a nominal 1500K heat pipe temperature. Fuel-coolant and fuel-coolant-clad relationships showed that once a failed heat pipe occurs temperatures can rise high enough so that large concentrations of uranium can be transported by the vapor phase. Upon condensation this uranium would be capable of penetrating heat pipes adjacent to the failed pipe. The potential for propagation of failur… more
Date: July 7, 1983
Creator: Alexander, C. A. & Ogden, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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