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Physics Design of the National High-Power Advanced Torus eXperiment

Description: Moving beyond ITER toward a demonstration power reactor (Demo) will require the integration of stable high fusion gain in steady-state, advanced methods for dissipating very high divertor heat-fluxes, and adherence to strict limits on in-vessel tritium retention. While ITER will clearly address the issue of high fusion gain, and new and planned long-pulse experiments (EAST, JT60-SA, KSTAR, SST-1) will collectively address stable steady-state high-performance operation, none of these devices wil… more
Date: July 2, 2007
Creator: Menard, J; Goldston, R; Fu, G; Gorelenkov, N; Kaye, S; Kramer, G et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Investigation into continuous acoustic emission monitoring of BWR components. Semi-annual report

Description: This report covers the work accomplished during the eight month period from October 1, 1977 through June 1, 1978. During this period, Peach Bottom Unit 3 was operational for the first six months and was shutdown for a refueling outage for the last two months. During the refueling outage, removal, recalibration, refurbishment, and reinstallation of all the AE instrumentation was performed. The coupling efficiency and the sensitivity of the sensors did not vary significantly with time. 5600 AE ev… more
Date: June 2, 1980
Creator: McElroy, J W
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Computer simulations of a 1/5-scale experiment of a Mark I boiler water reactor pressure-suppression system under hypothetical LOCA conditions

Description: The CHAMP computer code was employed to simulate a plane-geometry cross section of a Mark I boiling water reactor toroidal pressure suppression system air discharge experiment under hypothetical loss-of-coolant accident conditions. The experiments were performed at the Lawrence Livermore Laboratory on a /sup 1///sub 5/-scale model of the Peach Bottom Nuclear Power Plant.
Date: May 2, 1978
Creator: Edwards, L.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An alternative strategy for low specific power reactors to power interplanetary spacecraft, based on exploiting lasers and lunar resources

Description: A key requirement setting the minimum electric propulsion performance (specific power ..cap alpha../sub e/ = kW/sub e//kg) for manned missions to Mars is the maximum allowable radiation dose to the crew during the long transits between Earth and Mars. Penetrating galactic cosmic rays and secondary neutron showers give about 0.1-rem/day dose, which only massive shielding (e.g., a meter of concrete) can reduce significantly. With a humane allowance for cabin space, the shielding mass becomes so l… more
Date: February 2, 1989
Creator: Logan, B. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operating limits, Hanford Production Reactors. Revision 3

Description: These operating limits are applicable to eight operating production reactors, B, C, D, DR, F, H, KE, and KW. Subjects covered are: operating parameter limitations; reactivity limitations; control and safety systems; reactor fuel loadings; coolant requirements with irradiated fuel in reactor; reactor confinement; test facilities; code compliance; safety instrumentation and set points; and control criteria. Also discussed are the administrative procedures for process control, operator certificati… more
Date: August 2, 1963
Creator: Owsley, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mixer Spool Effectiveness and Pressure Loss Evaluations for Low Pressure Reactors

Description: Process tube and fuel jacket failures due to corrosion are recurring problems in the operation of nuclear reactors and are generally accentuated by coolant temperature increases. Water mixer fuel pieces which mix the subchannel flow streams are used in the production reactor fuel columns to reduce peripheral and hole-to-annulus coolant temperature disparities and, thus, to reduce corrosion problems. The mixer in current use is approximately two inches long and is attached to a six inch fuel pie… more
Date: February 2, 1968
Creator: Sutey, A. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Survey of supression of sodium fires in liquid metal fast breeder reactors

Description: A survey was made of protection and suppression technologies relative to liquid sodium fires at selected sites. These technologies will find application in the Liquid Metal Fast Breeder Reactor (LMFBR) program. Based on this survey, a series of conclusions and recommendations are given. Dry type powder agents will only be of use of relatively small sodium fires. Large fires will be extinguished by inerting the chamber or collecting pans where the sodium leak occurs. Liquid sodium fire suppressi… more
Date: June 2, 1976
Creator: Hemstreet, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Annotated bibliography of safety-related occurrences in boiling-water nuclear power plants as reported in 1976

Description: This bibliography contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at boiling-water reactor nuclear power plants in 1976. The report includes 1,253 abstracts that describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. They are arranged alphabetically by reactor name and then chronologically for each reactor. Key-word and permuted-title indexes are provided to facil… more
Date: August 2, 1977
Creator: Scott, R. L. & Gallaher, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison and Validation of HEU and LEU Modeling Results to HEU Experimental Benchmark Data for the Massachusetts Institute of Technology MITR Reactor.

Description: The Massachusetts Institute of Technology Reactor (MITR-II) is a research reactor in Cambridge, Massachusetts designed primarily for experiments using neutron beam and in-core irradiation facilities. It delivers a neutron flux comparable to current LWR power reactors in a compact 6 MW core using Highly Enriched Uranium (HEU) fuel. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used… more
Date: March 2, 2011
Creator: Newton, T. H.; Wilson, E. H; Bergeron, A.; Horelik, N.; Stevens, J. (Nuclear Engineering Division) & Lab.), (MIT Nuclear Reactor
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutronic Analyses for HEU to LEU fuel conversion of the Massachusetts Institute of Technology.

Description: The Massachusetts Institute of Technology (MIT) reactor (MITR-II), based in Cambridge, Massachusetts, is a research reactor designed primarily for experiments using neutron beam and in-core irradiation facilities. It delivers a neutron flux comparable to current LWR power reactors in a compact 6 MW core using Highly Enriched Uranium (HEU) fuel. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that… more
Date: March 2, 2011
Creator: Wilson, E. H.; Newton, T. H.; Bergeron, A.; Horelik, N.; Stevens, J. G (Nuclear Engineering Division) & NS), (
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

Description: We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advan… more
Date: October 2, 2006
Creator: Chadwick, M. B.; Oblozinsky, P.; Herman, M.; Greene, N. M.; McKnight, R. D.; Smith, D. L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Hydrodynamic phenomena of gas-filled chamber due to target implosion in fusion reactors.

Description: Use of an intermediate gas in the reaction chamber of an inertial fusion power reactor is under consideration to decrease the thermal shock to the walls resulting from target implosions. A model was developed and implemented in HEIGHTS package to simulate hydrodynamic and radiation shock waves in the chamber and used to determine the effect of xenon gas at various densities ranging from mtorr up to tens of torr. Numerical calculations for the dense-gas case indicated that two pressure peaks res… more
Date: July 2, 2003
Creator: Sizyuk, V. & Hassanein, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Structural aspects of the Chernobyl accident

Description: On April 26, 1986 the world's worst nuclear power plant accident occurred at the Unit 4 of the Chernobyl Nuclear Power Station in the USSR. This paper presents a discussion of the design of the Chernobyl Power Plant, the sequence of events that led to the accident and the damage caused by the resulting explosion. The structural design features that contributed to the accident and resulting damage will be highlighted. Photographs and sketches obtained from various worldwide news agencies will be… more
Date: September 2, 1988
Creator: Murray, R. C. & Cummings, G. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Helios pulsed nuclear propulsion concept

Description: A Helios-propelled vehicle would make use of a containment vessel--perhaps 30 feet in diameter--in which small nuclear explosive charges would be placed, together with a few hundred pounds of hydrogen. Firing of a charge would result in bringing the mixture of charge residue and hydrogen to a high temperature--say 5000 or 6000/sup 0/K--and subsequent release through a nozzle would provide propulsive thrust. This process would be repeated several thousand times, at intervals likely to be 10 seco… more
Date: June 2, 1965
Creator: Hadley, J. W.; Stubbs, T. F.; Janssen, M. A. & Simons, L. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RDA-DC-3 and Program X, process tube assembly -- Design criteria (preliminary)

Description: The process tube assembly functions to provide a water-cooled channel through the reactor into which uranium slugs are inserted for processing. The channel consists of a cylindrical tube with 2 ribs towards the bottom of the inside diameter which supports the slugs in a central location. Thus providing an annular space around the slugs for the cooling water used to remove the heat generated by fission of the uranium. Because of the relative movement between the graphite and the biological shiel… more
Date: April 2, 1952
Creator: Nesbitt, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Activation Cross Sections Improvements needed for IFE Power Reactors Designs

Description: Uncertainties in the prediction of the neutron induced long-lived activity in the natural elements from H to Bi due to activation cross section uncertainties are estimated assuming as neutron environment those of the HYLIFE-II and Sombrero vessel structures. The latest available activation cross section data are employed. The random variables used in the uncertainty analysis have been the concentration limits (CL's) corresponding to hands-on recycling, remote recycling and shallow land burial, … more
Date: October 2, 2003
Creator: Rodriguez, A; Cabellos, O; Sanz, J; FalQuina, R; Latkowski, J & Reyes, S
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Calculations of the surface heat flux and fuel temperatures for PRTR MK-I PuO{sub 2}-UO{sub 2} fuel element with segregated PuO{sub 2}

Description: The methods used to fabricate the present loading of PuO{sub 2}-UO{sub 2} fuel elements for the Plutonium Recycle Test Reactor have resulted in alternating bands of high and low PuO{sub 2} concentration along each rod of the 19-rod elements. These bands are repeated every 1/2 or 1 inch along the length of the rod, depending on whether the loading of the oxides was done in 160 or 80 increments. This non-uniform distribution of PuO{sub 2} results in alternate regions of high and low heat generati… more
Date: January 2, 1963
Creator: Zaloudek, F. R. & Hesson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mid-Year Summary Report October 1, 1960-March 31, 1961 Army Pwr Support and Development Program

Description: Abstract: A cyclic stress analysis of the SM-1 primary system was carried out. Problems encountered in the fabrication of PM-2A Core II and SM-lA Core II are described, and the results of an examination of damaged SM-lA Core I stationary fuel elements reported. A preliminary study of the radiation damage to SM-1 reactor vessel was made and the possibility of annealing the vessel discussed. Performance analyses are presented for five cores: SM-1 Core, SM-1 Core 1 rearranged and spiked, SM-1 Core… more
Date: June 2, 1961
Creator: Hoover, H. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Time behavior of a critical reactor pulsed with a large square wave source

Description: In a previous Naval Application memorandum, a discussion was given of what happens to the power level of a reactor when an instantaneous, very large neutron source is introduced. The motivation for the problem arises from the question of what happens when a nuclear bomb is detonated near a reactor powered missile. This present memorandum looks at the same problem as that which is discussed in the previous memorandum but in slightly more detail. The results obtained are essentially the same as t… more
Date: October 2, 1962
Creator: Barnett, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility of direct reactivity measurement in multi-canister overpacks at the Cold Vacuum Drying Facility

Description: A proposed method for measuring the chemical reaction rate (power) of breached N-Reactor fuel elements with water in a Multi-canister overpack (MCO) based on hydrogen release rate is evaluated. The reaction rate is measured at 50 C in an oxygen free water by applying a vacuum to boil the water and adding a low, measured flow of helium. The ratio of helium to hydrogen is used to infer the reaction rate. A test duration of less than 8 hours was found to provide sufficient accuracy for confidence … more
Date: October 2, 1997
Creator: Cowan, R.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Task completion report for update FXFILL

Description: The FILL component in TRAC-P defines a phasic-velocities boundary condition or total-mass-flow boundary condition. FILL option IFTY = 10 defines the total-mass flow and its composition for flow donoring from the FILL to its adjacent component by signal variables and/or control blocks. For flow from the adjacent component to the FILL component, the phasic densities of the adjacent-component cell need to be upstream donored by the IFTY = 10 option total-mass flow. Instead, the FILL-cell phasic de… more
Date: September 2, 1997
Creator: Steinke, R.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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