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Measurement of Xenon Poisoning in the HRT

Description: Measurements obtained during three periods of HRT operations indicated that the xenon poison fraction was approximately 0.010. The technique used was based on mass spectrographic analyses of the stable xenon isotopes in the reactor off-gas stream. Models proposed to explain the measurements show that xenon, which is formed primarily by decay of iodine adsorbed on the pipe walls, is held up on the walls, out of the circulating stream, for an average period of about eight hours. (auth)
Date: April 19, 1962
Creator: Burch, W.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mirror hybrid reactor studies

Description: The hybrid reactor studies are reviewed. The optimization of the point design and work on a reference design are described. The status of the nuclear analysis of fast spectrum blankets, systems studies for fissile fuel producing hybrid reactor, and the mechanical design of the machine are reviewed. (MHR)
Date: January 19, 1978
Creator: Bender, D.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part II. Economic Potential and Development Program. Heavy Water-Moderated Power Reactor

Description: The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel de… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part III. Status Report on Large (100 and 300 MWe) Heavy Water-Moderated Power Reactors--as of 1960

Description: An evaluation of 300- and 100-Mwe power plants was conducted using ground rules prescribed by the USAEC for this study. Costs corresponding to two average discharged fuel burnups are: 8.6 mills/kwh (8500 Mwd/ metric ton) and 8.8 mills/kwh (7500 Mwd/metric ton) for the 300-Mw plant. Costs for the 100 Mw plant are 14.7 mills/kwh for an average discharged fuel burnup of 6010 Mwd/metric ton. Estimates of future potential indicate that the 300 Mw/sub 3/ (8500 Mwd/metric ton) plant could produce powe… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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INFLUENCE OF RADIATION FROM AN UNSHIELDED REACTOR ON A NATURAL MICROFLORA

Description: The soil microflora and its respiratory activity were measured in soil cores collected at different distances from an unshielded reactor. No direct correlation was found between dose received and microbial counts or respiration. Indication of a correlation between dose and microbial respiration was obtained after eliminating the overriding influence of moisture. Radiation probably affected the soil microflora through damage to the phanerogam vegetation rather than directly. This preliminary stu… more
Date: October 19, 1961
Creator: Witkamp, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gcr-Orr Loop No. 2 Filter Tests. Part Ii

Description: Tests of Cambridge absolute filters, Model Sl-071, specified for use in the GCR-ORR Loop No. 2 as full-flow, primary coolant fiiters were completed. kD.O.P/ (dioctylphthalate) efficiency tests were performed on three filters in the as-received condition, on two filters following canning and thermal cycling, and on one of the canned fiIters following bsking out. None of the three units met the design criteria of 99.97% efficiency for removal of 0.3 micron particles in the as-received condition. … more
Date: February 19, 1962
Creator: Flint, F. A. & Smith, A. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High temperature ceramic membrane reactors for coal liquid upgrading

Description: In this project we well evaluate the performance of Sel-Gel alumina membranes in coal liquid upgrading processes under realistic temperature and pressure conditions and investigate the feasibility of using such membranes in a membrane reactor based coal liquid upgrading process. In addition, the development of novel ceramic membranes with enhanced catalytic activity for coal-liquid upgrading applications, such as carbon-coated alumina membranes, will be also investigated. (VC)
Date: June 19, 1992
Creator: Tsotsis, T.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tokamak Fusion Test Reactor neutral beam injection system vacuum chamber

Description: Most of the components of the Neutral Beam Lines of the Tokamak Fusion Test Reactor (TFTR) will be enclosed in a 50 cubic meter box-shaped vacuum chamber. The chamber will have a number of unorthodox features to accomodate both neutral beam and TFTR requirements. The design constraints, and the resulting chamber design, are presented.
Date: October 19, 1977
Creator: Pedrotti, L.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Uranium Contamination on the Surfaces of Alclad Uranium-Aluminum Alloy Research Reactor Fuel Plates

Description: Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium contamination on the surfaces of the alclad uranium-- aluminum plate-tyne fuel element led to an investigation to determine the sources of uranium contamination on the fuel plate surfaces. Two possible contributors to surface contamination are external sources such as rolling-mill equipment, the most obvious, and diffusion of uranium from the uranium-aluminum alloy fuel into the aluminum cladding.… more
Date: March 19, 1962
Creator: Beaver, R. J.; Erwin, J. H. & Mateer, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance of Argus as a laser fusion facility

Description: During the fifteen months that the Argus laser facility has been operating we have had two primary goals. These are: (1) to provide focusable, well characterized, high power beams for laser fusion experiments and (2) to further understand the propagation of high power and energy pulses. The propagation experiments have already led to increases in the laser output power and system reliability. Pulses appropriate for advanced targets are shaped to optimize the compression and heating of the targe… more
Date: September 19, 1977
Creator: Speck, D. R.; Simmons, W. W.; Hunt, J. T.; Boyle, M. J.; Rainer, F.; Storm, E. K. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tandem mirror reactor with thermal barriers

Description: This report gives detailed information in the form of the following chapters: (1) overview, (2) plasma physics, (3) magnets, (4) end-plug neutral beams, (5) barrier pump neutral beams, (6) ecr heating, (7) plasma direct converter, and (8) central cell. (MOW)
Date: September 19, 1979
Creator: Carlson, G. A.; Arfin, B.; Barr, W. L.; Boghosian, B. M.; Erickson, J. L.; Fink, J. H. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Inertial fusion power for space applications

Description: More than thirty-seven design concepts have been proposed for terrestrial ICF power plants. The design space is large because of the many allowable driver and reaction chamber combinations. These design studies have illustrated advantages of ICF power plants over other sources in lower impact on the environment, high safety, and almost no dependence on consumables like fuel. The fact that, once built, a 1000 MW/sub e/ ICF power plant would require only 240 kg of deuterium and from 770 to 9260 k… more
Date: May 19, 1986
Creator: Meier, W. R.; Hogan, W. J.; Hoffman, N. J.; Murray, K. A. & Olson, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reports distributed under the NRC Light-Water Reactor Safety Research Foreign Technical Exchange Program. Volume III, January--June 1977

Description: Lists of documents exchanged during the first half of 1977 under agreements between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, and Japan are presented. During this period, the NRC received 41 reports from France, 29 from F. R. Germany, and 24 from Japan, and in return sent 107 U.S. reports to each of these three countries.
Date: September 19, 1977
Creator: Sharp, D. S. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutral beam injection system for the Tokamak Fusion Test Reactor

Description: The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facility. This is a major step to reach the goal of fusion power using toroidal magnetic fields for plasma confinement. A major part of this test reactor will be four neutral beam injection systems. These systems will inject 20 MW of 120 kV neutral deuterium atoms into the plasma for 0.5 seconds. In order to achieve the required power input to the plasma, several systems are required within the neutral … more
Date: October 19, 1977
Creator: Pittenger, L.C.; Stone, R.R.; Valby, L.E. & Pedrotti, L.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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System design for the new TMX machine

Description: The Tandem Mirror Experiment (TMX) is designed to test the physics of a new approach to Q-enhancement in open confinement systems. In the tandem mirror concept, the ends of a long solenoid are plugged electrostatically by means of ambipolar potential barriers created in two mirror machines or plugs, one at each end of the solenoid. The ambipolar potential in mirror machines develops as a consequence of the higher scattering rate of electrons and the balancing of electron and ion loss rates. The… more
Date: October 19, 1977
Creator: Chargin, A. K.; Calderon, M. O.; Mooney, L. J. & Vogtlin, G. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fabrication of Pillar-Structured Thermal Neutron Detectors

Description: Pillar detector is an innovative solid state device structure that leverages advanced semiconductor fabrication technology to produce a device for thermal neutron detection. State-of-the-art thermal neutron detectors have shortcomings in achieving simultaneously high efficiency, low operating voltage while maintaining adequate fieldability performance. By using a 3-dimensional silicon PIN diode pillar array filled with isotopic boron 10, ({sup 10}B) a high efficiency device is theoretically pos… more
Date: November 19, 2007
Creator: Nikolic, R. J.; Conway, A. M.; Reinhardt, C. E.; Graff, R. T.; Wang, T. F.; Deo, N. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Over Batch Analysis for the LLNL Plutonium Packaging System (PuPS)

Description: This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria (Reference 1, Section 6.a.3) about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Live… more
Date: November 19, 2007
Creator: Riley, D & Dodson, K
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Report for "Implimentation and Evaluation of Multigrid Linear Solvers into Extended Magnetohydrodynamic Codes for Petascale Computing"

Description: Extended magnetohydrodynamic (MHD) codes are used to model the large, slow-growing instabilities that are projected to limit the performance of International Thermonuclear Experimental Reactor (ITER). The multiscale nature of the extended MHD equations requires an implicit approach. The current linear solvers needed for the implicit algorithm scale poorly because the resultant matrices are so ill-conditioned. A new solver is needed, especially one that scales to the petascale. The most successf… more
Date: June 19, 2008
Creator: Vadlamani, Srinath; Kruger, Scott & Austin, Travis
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TRANSPARENCY: Tracking Uranium under the U.S. / Russian HEU Purchase Agreement

Description: By the end of August, 2005, the Russia Federation delivered to the United States (U.S.) more than 7,000 metric tons (MT) of low enriched uranium (LEU) containing approximately 46 million SWU and 75,000 MT of natural uranium. This uranium was blended down from weapons-grade (nominally enriched to 90% {sup 235}U) highly enriched uranium (HEU) under the 1993 HEU Purchase Agreement that provides for the blend down of 500 MT HEU into LEU for use as fuel in commercial nuclear reactors. The HEU Transp… more
Date: October 19, 2005
Creator: Benton, J B; Decman, D J & Leich, D A
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Sphere-Pac Evaluation for Transmutation

Description: The U.S. Department of Energy Advanced Fuel Cycle Initiative (AFCI) is sponsoring a project at Oak Ridge National Laboratory with the objective of conducting the research and development necessary to evaluate the use of sphere-pac transmutation fuel. Sphere-pac fuels were studied extensively in the 1960s and 1970s. More recently, this fuel form is being studied internationally as a potential plutonium-burning fuel. For transmutation fuel, sphere-pac fuels have potential advantages over traditio… more
Date: May 19, 2005
Creator: Icenhour, A.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Description: Ni-base alloys were considered for the Prometheus space reactor pressure vessel with operational parameters of {approx}900 K for 15 years and fluences up to 160 x 10{sup 20} n/cm{sup 2} (E > 0.1 MeV). This paper reviews the effects of irradiation on the behavior of Ni-base alloys and shows that radiation-induced swelling and creep are minor considerations compared to significant embrittlement with neutron ,exposure. While the mechanism responsible for radiation-induced embrittlement is not f… more
Date: January 19, 2006
Creator: Angeliu, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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On-Line Coolant Chemistry Analysis

Description: Impurities in the gas coolant of the space nuclear power plant (SNPP) can provide valuable indications of problems in the reactor and an overall view of system health. By monitoring the types and amounts of these impurities, much can be implied regarding the status of the reactor plant. However, a preliminary understanding of the expected impurities is important before evaluating prospective detection and monitoring systems. Currently, a spectroscopy system is judged to hold the greatest promis… more
Date: July 19, 2006
Creator: Bachman, LM
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium pool fire model for CONACS code. [LMFBR]

Description: The modeling of sodium pool fires constitutes an important ingredient in conducting LMFBR accident analysis. Such modeling capability has recently come under scrutiny at Westinghouse Hanford Company (WHC) within the context of developing CONACS, the Containment Analysis Code System. One of the efforts in the CONACS program is to model various combustion processes anticipated to occur during postulated accident paths. This effort includes the selection or modification of an existing model and de… more
Date: October 19, 1982
Creator: Yung, S.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, January 1, 1979-March 31, 1979

Description: This report presents the results of work performed from January 1, 1979 through March 31, 1979 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high tempera… more
Date: July 19, 1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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