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in creator/contributor: "Trauger, D.B."  
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Nuclear power options viability: Oak Ridge National Laboratory's study

Description: Seven criteria, augmented by desired characteristics, were established to assess the viability of nuclear reactors for the timeframe beginning at 2005 for the United States. Earlier nuclear power needs will be filled by LWRs. Several advanced concepts were selected, based on three ground rules, and assessed. It was concluded that there are several acceptable and viable concepts.
Date: January 1, 1986
Creator: Gat, U.; Trauger, D.B. & White, J.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Helium-cooled high temperature reactors

Description: Experience with several helium cooled reactors has been favorable, and two commercial plants are now operating. Both of these units are of the High Temperature Graphite Gas Cooled concept, one in the United States and the other in the Federal Republic of Germany. The initial helium charge for a reactor of the 1000 MW(e) size is modest, approx.15,000 kg.
Date: January 1, 1985
Creator: Trauger, D.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Statement on the Consolidated Fuel Reprocessing Program

Description: Oak Ridge National Laboratory has chosen the following objectives for future reprocessing plant design: reduced radiation exposure to workers; minimal environmental impact; improved plant operation and maintenance; improved accountability; no plutonium diversion; and reduced overall capital and operating cost. These objectives lead to a plant with totally remote operation. The Breeder Reactor Engineering Test (BRET) has been designed to perform a key role in demonstrating advanced reprocessing … more
Date: January 1, 1984
Creator: Trauger, D.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safety and licensing for small and medium power reactors

Description: Proposed new concepts for small and medium power reactors differ substantially from traditional Light Water Reactors (LWRs). Although designers have a large base of experience in safety and licensing, much of it is not relevant to new concepts. It can be a disadvantage if regulators apply LWR rules directly. A fresh start is appropriate. The extensive interactions between industry, regulators, and the public complicates but may enhance safety. It is basic to recognize the features that distingu… more
Date: January 1, 1987
Creator: Trauger, D.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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ORNL grouting technologies for immobilizing hazardous wastes

Description: The Cement and Concrete Applications Group at the Oak Ridge National Laboratory (ORNL) has developed versatile and inexpensive processes to solidify large quantities of hazardous liquids, sludges, and solids. By using standard off the shelf processing equipment, these batch or continuous processes are compatible with a wide range of disposal methods, such as above-ground storage, shallow-land burial, deep geological disposal, sea-bed dumping, and bulk in-situ solidification. Because of their ec… more
Date: January 1, 1983
Creator: Dole, L.R. & Trauger, D.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Three Mile Island in perspective

Description: The events of March 28 are described briefly. Some of the causes, for example, failures due to men, to machines, and to man-machine interfaces are discussed. Some plans and actions now being taken to improve things for the future are outlined.
Date: January 1, 1979
Creator: Trauger, D.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Status of HTGR technology development and demonstration

Description: Several HGTR items which require thorough testing include the core support and pads, vessel insulation and liner, and graphite fuel blocks. Tests which are to be conducted in the Component Flow Test Loop are discussed. The neutron streaming experiment at the Tower Shielding Facility is described. Materials and fuels development studies are also discussed. (DLC)
Date: January 1, 1983
Creator: Trauger, D.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nuclear power options viability study

Description: The Oak Ridge National Laboratory has chosen to assess the present nuclear energy situation and to evaluate new directions which may offer opportunity for improvement. Options for industry, regulation, and research are considered in these assessments. Smaller reactors (500 MW or less) were chosen for emphasis because they have received less recent attention than larger units and because they fit the current lower power demand projections. They also offer potential for increased shop fabrication… more
Date: January 1, 1984
Creator: Trauger, D.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

DESIGN REPORT FOR NMSR PRESSURIZED WATER LOOP AT ORR

Description: A pressurized water loop constructed in the Oak Ridge Research Reactor for use in the Maritime Reactor Program is described. irradiation testing of pressure vessel materinl specimens and several sets of fuel pins for the NS Savannah'' Nuclear Merchant Ship Reactor, NMSR, was completed. Operating conditions for the fuel tests nominally were 500 deg F and 1750 psig. The loop has capability for operation at 650 deg F, 2500 psig, with a maximum water flow rate of 80 gpm, and heat removal in excess … more
Date: January 1, 1962
Creator: Dudley, I.T.; Tidwell, D.E. & Trauger, D.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SOME MAJOR FUEL-IRRADIATION TEST FACILITIES OF THE OAK RIDGE NATIONAL LABORATORY

Description: Irradiations of test fuel specimens and experimental fue elements are conducted both in capsules and in forcedconvection-cooled loops. The design of equipment suitable for irradiation tests pertinent to the development of boiling and pressurized-water, gas-cooled, sodium-cooled, and molten-salt reactors is described briefly, with particular emphasis on test capability. The capsules utilize thermal conduction through sodium or NaK, gas-filled annuli, and graphite for heat removal from the fuel e… more
Date: April 1, 1964
Creator: Trauger, D.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Design Report for the NMSR Pressurized Water Loop at ORR

Description: The design criteria, description, flow diagrams, and some drawings of a pressurized water loop in which reactor operation conditions can be simulated are presented. The prirnary purpose of this test facility is irradiation testing of various versions of fuel elements for use in the Merchant Ship Reactor Program. The loop proper is designed for operation at 625 deg F and 2250 psi with a water flow rate of 90 gpm. Heat exchanger capacity is 150 kw at 300-F system water temperature. Loop construct… more
Date: October 23, 1958
Creator: Dudley, I.T.; Trauger, D.B. & Savage, H.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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