1,439 Matching Results

Search Results

Advanced search parameters have been applied.

in subjects: "220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors"

open access

Some recent observations on the radiation behavior of uranium silicide dispersion fuel

Addition of B{sub 4}C burnable poison results in higher plate swelling in both U{sub 3}Si{sub 2} and U{sub 3}Si-Al dispersion fuel plates and also decreases the blister threshold temperature of these plates. Prolonged annealing of U{sub 3}Si{sub 2}-Al fuel plates produced no blister after 696 hours at 400{degrees}C. Blister formation started between 257 hours and 327 hours at 425{degrees}C and between 115 hours and 210 hours at 450{degrees}C. Operation with breached cladding resulted in pillowi… more

Date: January 1, 1988

Creator: Hofman, G.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Savannah River Laboratory monthly report, February 1992

This report is a progress report for the Savannah River Laboratory for the month of February 1992. The progress and activities in six categories were described in the report. The categories are reactor, tritium, separations, environmental, waste management, and general. Each category described numerous and varied activities. Some examples of these activities described are such things as radiation monitoring, maintenance, modifications, and remedial action.

Date: February 1, 1992

Creator: Ferrell, J.M. (comp.) & Ice, L.W. (ed.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

TFE verification program

The program objective is to demonstrate the technology readiness of a thermionic fuel element (TFE) suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. This report states progress made in the following tasks: concept design, converter performance, insulator seal, sheath insulator, fueled emitter, cesium reservoir and interconnective TFE components, and thermionic fuel element testing. 20 refs.,… more

Date: April 1, 1991

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Tiger Team Assessment of the Los Alamos National Laboratory

The purpose of the safety and health assessment was to determine the effectiveness of representative safety and health programs at the Los Alamos National Laboratory (LANL). Within the safety and health programs at LANL, performance was assessed in the following technical areas: Organization and Administration, Quality Verification, Operations, Maintenance, Training and Certification, Auxiliary Systems, Emergency Preparedness, Technical Support, Packaging and Transportation, Nuclear Criticality… more

Date: November 1, 1991

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Fuels for research and test reactors, status review: July 1982

A thorough review is provided on nuclear fuels for steady-state thermal research and test reactors. The review was conducted to provide a documented data base in support of recent advances in research and test reactor fuel development, manufacture, and demonstration in response to current US policy on availability of enriched uranium. The review covers current fabrication practice, fabrication development efforts, irradiation performance, and properties affecting fuel utilization, including the… more

Date: December 1, 1982

Creator: Stahl, D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Neodymium, Samarium and Europium Capture Cross-Section Adjustments Based on EBR-II Integral Measurements

Integral capture measurements were made for highly enriched isotopes of neodymium, samarium, and europium irradiated in a row 8 position of EBR-II with samples located both at mid-plane and in the axial reflector. Broad response, resonance, and threshold dosimeters were included to characterize the neutron spectra at the sample locations. The saturation reaction rates for the rare-earth samples were determined by post-irradiation mass-spectrometric analyses and for the dosimeter materials by th… more

Date: January 1, 1979

Creator: Anderl, R. A.; Harker, Y. D. & Schmittroth, F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Energy Production Using Fission Fragment Rockets

Fission fragment rockets are nuclear reactors with a core consisting of thin fibers in a vacuum, and which use magnetic fields to extract the fission fragments from the reactor core. As an alternative to ordinary nuclear reactors, fission fragment rockets would have the following advantages: Approximately twice as efficient if one can directly convert the fission fragment energy into electricity; by reducing the buildup of a fission fragment inventory in the reactor one could avoid a Chernobyl … more

Date: August 1, 1991

Creator: Chapline, George & Matsuda, Yoshiyuki

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Tensile testing and scanning electron microscope examination of Charpy impact specimens from the HFBR

The Materials Technology Group of the Department of Nuclear Energy (DNE) at Brookhaven National Laboratory (BNL) has performed a fractographic examination of neutron irradiated and unirradiated Charpy V'' notch specimens which have been deformed to failure in a tensile testing apparatus. The evaluation was carried out using a scanning electron microscope (SEM) to evaluate the fracture mode. Photomicrographs were then evaluated to determine if ductile areas were present on the fracture surfaces … more

Date: January 1, 1990

Creator: Czajkowski, C. J.; Schuster, M. H. & Roberts, T. C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Instrumentation and Controls Division biennial progress report, September 1, 1974--September 1, 1976. Non-LMFBR programs

Research progress and developments are reported in the areas of basic electronics, instruments, radiation monitoring, pulse counting and analysis, electronic engineering support for research facilities, automatic control and data acquisition, reactor instrumentation and controls, fuel reprocessing and shipping, process systems and instrumentation development, thermometry, instrumentation for reactor division experiments and test loops, environmental science studies, miscellaneous engineering st… more

Date: November 1, 1976

Creator: Sadowski, G. S. (comp.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Analysis and evaluation of ZPPR (Zero Power Physics Reactor) critical experiments for a 100 kilowatt-electric space reactor

ZPPR critical experiments were used for physics testing the reactor design of the SP-100, a 100-kW thermoelectric LMR that is being developed to provide electrical power for space applications. These tests validated all key physics characteristics of the design, including the ultimate safety in the event of a launch or re-entry accident. Both the experiments and the analysis required the use of techniques not previously applied to fast reactor designs. A few significant discrepancies between th… more

Date: January 1, 1990

Creator: McFarlane, H. F.; Collins, P. J.; Carpenter, S. G.; Olsen, D. N.; Smith, D. M.; Schaefer, R. W. (Argonne National Lab., Idaho Falls, ID (USA)) et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Iodine-131 releases from the Hanford Site, 1944--1947

Detailed results of the Hanford Environmental Dose Reconstruction (HEDR) iodine-131 release reconstruction are presented in this volume. Included are daily data on B, D, and F Plant, reactor operations from the P-Department Daily Reports (General Electric Company 1947). Tables of B and T Plant material processed from the three principal sources on separations plant operations: The Jaech report (Jaech undated), the 200 Area Report (Acken and Bird 1945; Bird and Donihee 1945), and the Metal Histo… more

Date: October 1, 1992

Creator: Heeb, C.M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Mechanical properties of transient-tested irradiated fast-reactor cladding. [811/sup 0/ to 1644/sup 0/K; 5. 8 x 10/sup 22/ n/cm/sup 2/]

Results are presented for three high burnup PNL-11 fuel pins irradiated to goal FFTF exposure levels in testing cladding stress and strain on fast reactor fuel pins subjected to simulated power transient conditions. The mixed oxide fuel with Type 316 SS clad were tested at heating rates of 5.5 k/s and 200 k/s with internal gas pressures of 17.2 to 98.6 MPa. Mechanical property data were obtained. Under short-term transient heating, neutron volumetric swelling does not change. Cladding strength … more

Date: August 9, 1978

Creator: Johnson, G. D. & Hunter, C. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

A survey of techniques for corrosion monitoring

Corrosion monitoring techniques have improved with advances in instrumentation technology and corrosion research. Older techniques, such as coupon immersion, generally provide historical information. The new electrochemical techniques, which have not been used widely at SRS, allow on-line monitoring and correlation with process changes. These techniques could improve the corrosion assessment of the waste tanks to be used for In-Tank Precipitation and Extended Sludge Processing. A task was initi… more

Date: October 1, 1992

Creator: Mickalonis, J.I.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Interpretation of gamma-scanning data from the ORR demonstration elements

The HEU and LEU fuel elements used in the ORR whole-core demonstration were gamma-scanned to determine the axial distribution of the {sup 140}La and {sup 137}Cs activities. Analysis of this data is now complete. From the {sup 140}La activity distributions cycle-averaged powers were determined while the {sup 137}Cs data provided a measure of the final {sup 235}U burnup in the fuel elements. A method for calculating correction factors for activity gradients transverse to the fuel element axis is … more

Date: January 1, 1989

Creator: Bretscher, M.M.; Snelgrove, J.L.; Hobbs, R.W. (Argonne National Lab., IL (USA) & Oak Ridge National Lab., TN (USA))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Overview of the Savannah River reactor surveillance program

Preliminary radiation effects studies, now nearing completion, are based upon short-term irradiations in the High Flux Isotope Reactor (HFIR) and University of Buffalo Reactor (UBR). The purpose of these studies is to assess the impact of radiation effects on the performance and service life of Savannah River Site (SRS) reactor components. The SRS reactor surveillance program was simultaneously established in order to validate the results of these short-term irradiations under conditions more a… more

Date: January 1, 1991

Creator: Sindelar, R.L.; Thomas, J.K. & Baumann, N.P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Analysis of soil samples from OMRE decommissioning project

In order to establish that the present Organic Moderated Reactor Experiment (OMRE) site does not exceed the criteria for radioactive contamination, samples obtained from the remainder of the facility that was not removed such as soil, concrete pads, various structural materials, and the leach pond area were analyzed to determine their radioactive content. The results of the analyses performed on soil samples are presented. Results of this study indicate that the activity at the OMRE decommissio… more

Date: January 1, 1979

Creator: Simpson, O.D.; Chapin, J.A.; Hine, R.E.; Mandler, J.W.; Orme, M.P. & Soli, G.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Characteristics of potential repository wastes

The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the spent fuels and other wastes that will be disposed of in a geologic repository. The two major sources of these materials are commercial light-water reactor (LWR) spent fuel and immobilized high-level waste (HLW). Other wastes that may require long-term isolation include non-LWR spent fuels and miscellaneous sources such as activated metals. Detailed characterizations are required for all of these potential reposi… more

Date: January 1, 1989

Creator: Notz, Karl J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Formulation and experimental evaluation of closed-form control laws for the rapid maneuvering of reactor neutronic power

This report describes both the theoretical development and the experimental evaluation of a novel, robust methodology for the time-optimal adjustment of a reactor's neutronic power under conditions of closed-loop digital control. Central to the approach are the MIT-SNL Period-Generated Minimum Time Control Laws' which determine the rate at which reactivity should be changed in order to cause a reactor's neutronic power to conform to a specified trajectory. Using these laws, reactor power can be… more

Date: September 1, 1989

Creator: Bernard, John A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Enriched vs non-enriched vs non-fissile targets for pulsed spallation neutron sources

Numerous options exist among alternatives for target material and design of the neutron producing target in pulsed spallation neutron sources. This report surveys the advantages, disadvantages and limitations of some of the alternatives, including discussions of neutron yields, delayed neutron backgrounds, source pulse widths, source-to-moderator coupling, materials performance, fabrication problems, safeguards and security and hazards questions. 5 refs., 5 figs., 2 tabs.

Date: January 1, 1990

Creator: Carpenter, J.M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Pilot study risk assessment for selected problems at the Savannah River Site (SRS)

An assessment of the health risks was made for releases of tritium and [sup 137]Cs from the Savannah River Site (SRS) at water-receptor locations downriver. Although reactor operations were shut down at the SRS in 1989, liquid wastes continue to be released to the Savannah River either by direct discharges into onsite surface waters or by groundwater transport into surface waters from waste facilities. Existing state mandates will cause the liquid waste streams from future operations to go dire… more

Date: March 1, 1993

Creator: Hamilton, L.D.; Holtzman, S.; Meinhold, A.; Morris, S.C.; Pardi, R.; Sun, C. (Brookhaven National Lab., Upton, NY (United States)) et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Integrated system for production of neutronics and photonics calculational constants. Volume 15, Part E. Data testing results for the LLL Evaluated Nuclear Data Library (ENDL-78)

The LLL Evaluated Nuclear Data Library (ENDL-78) was tested for validity by comparing calculated and experimental values of k/sub eff/ for 67 critical assemblies and emission neutron spectra for 22 spheres that were pulsed with 14-MeV neutrons. 22 figures, 5 tables.

Date: August 13, 1979

Creator: Howerton, Robert J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Production of tungsten-188 and osmium-194 in a nuclear reactor for new clinical generators

Rhenium-188 and iridium-194 are potential candidates for radioimmunotherapy with monoclonal antibodies directed against tumor-associated antigens. Both nuclei are short-lived and decay by high energy {Beta}{minus} emission. In addition, both nuclei emit {gamma}-rays with energy suitable for imaging. An important characteristics is availability of {sup 188}Re and {sup 194}Ir from decay of reactor-produced parents ({sup 188}W and {sup 194}Os, respectively) in convenient generator systems. The {su… more

Date: January 1, 1991

Creator: Mirzadeh, S.; Knapp, F. F. Jr. & Callahan, A. P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fission energy: The integral fast reactor

The Integral Fast Reactor (IFR) is an innovative reactor concept being developed at Argonne National Laboratory as a such next- generation reactor concept. The IFR concept has a number of specific technical advantages that collectively address the potential difficulties facing the expansion of nuclear power deployment. In particular, the IFR concept can meet all three fundamental requirements needed in a next-generation reactor as discussed below. This document discusses these requirements.

Date: January 1, 1989

Creator: Chang, Yoon I.

Item Type: Article

Partner: UNT Libraries Government Documents Department