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A replaceable reflective film for solar concentrators

Description: The 3M Company manufactures a silvered acrylic film called ECP-305 that is regarded as the preferred reflective film for use on stretched-membrane heliostats. However, ECP-305 will degrade in time, due to both corrosion of the silver layer and delamination at the film's silver-to-acrylic interface, and will eventually need to be replaced. 3M uses a very aggressive adhesive on this film, and once it is laminated, replacement is very difficult. The purpose of this investigation was the developmen… more
Date: September 1, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cross Section Evaluation Working Group benchmark specifications. Volume 2. Supplement

Description: Neutron and photon flux spectra have been measured and calculated for the case of neutrons produced by D-T reactions streaming through a cylindrical iron duct surrounded by concrete. Measurements and calculations have also been obtained when the iron duct is partially filled by a laminated stainless steel and borated polyethylene shadow bar. Schematic diagrams of the experimental apparatus is included.
Date: September 1, 1986
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ZPPR-20 Phase D : A Cylindrical Assembly of Polyethylene Moderated U Metal Reflected by Beryllium Oxide and Polyethylene.

Description: The Zero Power Physics Reactor (ZPPR) fast critical facility was built at the Argonne National Laboratory-West (ANL-W) site in Idaho in 1969 to obtain neutron physics information necessary for the design of fast breeder reactors. The ZPPR-20D Benchmark Assembly was part of a series of cores built in Assembly 20 (References 1 through 3) of the ZPPR facility to provide data for developing a nuclear power source for space applications (SP-100). The assemblies were beryllium oxide reflected and had… more
Date: September 30, 2006
Creator: Lell, R.; Grimm, K.; McKnight, R.; Shaefer, R.; Division, Nuclear Engineering & INL
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The effect of visible light on Harshaw Model 8801 thermoluminescent dosimeters

Description: It has been known for some time that illumination of lithium fluoride (LiF) thermoluminescent dosimeters, particularly with ultraviolet wavelengths, causes these dosimeters to emit thermoluminescence (TL), similar to that caused by exposure to radiation. However the effect of incandescent light on dosimeters is not well documented. In this study the growth, saturation and spectral dependence of this luminescence is studied for open dosimeter cards illuminated with room incandescent light, and f… more
Date: September 1, 1990
Creator: Sonder, E.; Ahmed, A. B.; McMahan, K. L.; Colwell, D. S. & Smith, P. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Waste Form Evaluation Program. Final report

Description: This report presents data that can be used to assess the acceptability of polyethylene and modified sulfur cement waste forms to meet the requirements of 10 CFR 61. The waste streams selected for this study include dry evaporator concentrate salts and incinerator ash as representative wastes which result from advanced volume reduction technologies and ion exchange resins which remain problematic for solidification using commercially available matrix materials. Property evaluation tests such as … more
Date: September 1, 1985
Creator: Franz, E.M. & Colombo, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Assessment of existing and prospective piping technology for district-heating applications

Description: Data on design features and operational experience of 40 hot water and steam district-heating networks with an overall heat capacity of 18,000 MWt have been collected, systematized, and analyzed. Piping networks located in Canada, Denmark, Finland, France, Italy, Japan, Netherlands, Sweden, USA, USSR, and West Germany have been analyzed and the data assembled. The data bank and analysis of the operational experience design features of hot water and steam district-heating networks are provided i… more
Date: September 1, 1979
Creator: Oliker, I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spectroscopic study of coal structure and reactivity

Description: Work done during this period (December 15, 1989 to March 14, 1990) covered two of the three primary areas of study of this project. The first involved the continuing development a of step-scanning interferometer for the photoacoustic depth-profiling of materials whose composition varies in the spatial region between 5 and 50 {mu}m from its surface. The second covered the initial construction of an on-line interface between a supercritical fluid chromatograph (SFC) and a Fourier transform infrar… more
Date: September 7, 1990
Creator: Rabenstein, D.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Waste form development program. Annual report, October 1982-September 1983

Description: This report provides a summary of the work conducted for the Waste Form Development/Test Program at Brookhaven National Laboratory in FY 1983 under the sponsorship of the US Department of Energy's Low-Level Waste Management Program. The primary focus of this work is the investigation of new solidification agents which will provide improved immobilization of low-level radioactive wastes in an efficient, cost-effective manner. A working set of preliminary waste form evaluation criteria which coul… more
Date: September 1, 1983
Creator: Colombo, P.; Kalb, P. D. & Fuhrmann, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Macroscopic cross section sensitivity study for fusion reactor shielding experiments

Description: Sensitivities of the calculated neutron and gamma-ray responses of an NE-213 detector to the macroscopic cross sections for neutron interactions in materials used in an integral experiment for fusion reactor shielding studies are presented. Sensitivities for the interactions in the 14-MeV and 1- to 2-MeV energy ranges are found to be large enough to ensure the derivation of a significant amount of information from the experiment.
Date: September 1, 1978
Creator: Seki, Y.; Santoro, R. T.; Oblow, E. M. & Lucius, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Shielding Calculations for the BDMS UF6 Mass Flow Meter

Description: We performed Monte Carlo calculations of the neutron and gamma ray spectra and neutron and gamma dose rates outside the shielding of the UF{sub 6} mass flowmeter. The UF{sub 6} mass flowmeter and the UF{sub 6} mass flowmeter are the two main components of the Blend Down Monitoring System (BDMS) equipment. The BDMS equipment is designed to continuously monitor the UF{sub 6} enrichment and mass flow rates in processing pipes at uranium facilities. The UF{sub 6} mass flowmeter incorporates four {s… more
Date: September 13, 2001
Creator: Radev, R & Hall, J
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FINAL CLOSURE PLAN SURFACE IMPOUNDMENTS CLOSURE, SITE 300

Description: Lawrence Livermore National Laboratory of the University of California (LLNL) operates two Class II surface impoundments that store wastewater that is discharged from a number of buildings located on the Site 300 Facility (Site 300). The wastewater is the by-product of explosives processing. Reduction in the volume of water discharged from these buildings over the past several years has significantly reduced the wastewater storage needs. In addition, the impoundments were constructed in 1984, a… more
Date: September 29, 2004
Creator: Lane, J E; Scott, J E & Mathews, S E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Polyethylene-Reflected Arrays of HEU(93.2) Metal Units Separated by Vermiculite

Description: This benchmark details the results of an experiment performed in the early 1970s as part of a series testing critical configurations in three dimensional arrays. For this experiment, cylinders of 93.2% enriched uranium metal were arranged in a 2x2x2 array inside of a polyethylene reflector. Layers of vermiculite of varying heights were surrounding each cylinder to achieve criticality variations. A total of four experimental configurations were tested by D.W. Magnuson, and detailed in his experi… more
Date: September 1, 2010
Creator: Gorham, Mackenzie; Briggs, J. Blair; Bess, John D.; Dean, Virginia & Reed, Davis
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ORALLOY (93.2 235U) METAL CYLINDER WITH BERYLLIUM TOP REFLECTOR

Description: A variety of critical experiments were constructed of enriched uranium metal during the 1960s and 1970s at the Oak Ridge Critical Experiments Facility (ORCEF) in support of criticality safety operations at the Y-12 Plant. The purposes of these experiments included the evaluation of storage, casting, and handling limits for the Y-12 Plant and providing data for verification of calculation methods and cross-sections for nuclear criticality safety applications. These included solid cylinders of va… more
Date: September 1, 2010
Creator: Bess, John D.; Montierth, Leland M.; Reed, Raymond & Mihalczo, John T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EFFECTS OF GAMMA IRRADIATION ON EPDM ELASTOMERS

Description: Two formulations of EPDM elastomer, one substituting a UV stabilizer for the normal antioxidant in this polymer, and the other the normal formulation, were synthesized and samples of each were exposed to gamma irradiation in initially pure deuterium gas to compare their radiation stability. Stainless steel containers having rupture disks were designed for this task. After 130 MRad dose of cobalt-60 radiation in the SRNL Gamma Irradiation Facility, a significant amount of gas was created by radi… more
Date: September 22, 2011
Creator: Clark, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

2 x 2 Polyethylene Reflected and Moderated Highly Enriched Uranium System with Rhenium

Description: The 2 × 2 array HEU-Re experiment was performed on the Planet universal critical assembly machine on November 4th, 2003 at the Los Alamos Critical Experiments Facility (LACEF) at Los Alamos National Laboratory (LANL). For this experiment, there were 10 ½ units, each full unit containing four HEU foils and two rhenium foils. The top unit contained only two HEU foils and two rhenium foils. A total of 42 HEU foils were used for this experiment. Rhenium is a desirable cladding material for space nu… more
Date: September 1, 2010
Creator: Ellis, A. Nichole; Hutchinson, Jesson; Bess, John D.; Polyakov, Dmitry N.; Glushkov, Evgeny S. & Glushkov, Alexey E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculated and measured efficiency of a man-portable /sup 3/He neutron detector

Description: A small man-portable neutron detector was constructed using 18 /sup 3/He proportional counters arranged in three layers within a polyethylene moderator. Each counter is 25 mm in diameter by 340 mm long (sensitive length) and is filled with highly-purified /sup 3/He to a pressure of 400 kPa (4 atm). Efficiency measurements were made using a /sup 252/Cf neutron source. Detailed calculations of the detector efficiency were done using the TART Monte Carlo transport code. Calculations and measuremen… more
Date: September 29, 1976
Creator: O'Dell, A. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Benchmark Evaluation of Plutonium Nitrate Solution Arrays

Description: In October and November of 1981 thirteen approach-to-critical experiments were performed on a remote split table machine (RSTM) in the Critical Mass Laboratory of Pacific Northwest Laboratory (PNL) in Richland, Washington, using planar arrays of polyethylene bottles filled with plutonium (Pu) nitrate solution. Arrays of up to sixteen bottles were used to measure the critical number of bottles and critical array spacing with a tight fitting Plexiglas{reg_sign} reflector on all sides of the array… more
Date: September 1, 2011
Creator: Marshall, M. A. & Bess, J. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Coated Gallium Arsenide Neutron Detectors : Results of Characterization Measurements.

Description: Effective detection of special nuclear materials (SNM) is essential for reducing the threat associated with stolen or improvised nuclear devices. Passive radiation detection technologies are primarily based on gamma-ray detection and subsequent isotope identification or neutron detection (specific to neutron sources and SNM). One major effort supported by the Department of Homeland Security in the area of advanced passive detection is handheld or portable neutron detectors for search and locali… more
Date: September 29, 2006
Creator: Klann, R. T.; Perret, G. & Sanders, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Conformance Improvement Using Gels

Description: This report describes work performed during the third and final year of the project, ''Conformance Improvement Using Gels.'' Corefloods revealed throughput dependencies of permeability reduction by polymers and gels that were much more prolonged during oil flow than water flow. This behavior was explained using simple mobility ratio arguments. A model was developed that quantitatively fits the results and predicts ''clean up'' times for oil productivity when production wells are returned to ser… more
Date: September 30, 2004
Creator: Seright, Randall S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal testing of solid neutron shielding materials

Description: Two legal-weight truck casks the GA-4 and GA-9, will carry four PWR and nine BWR spent fuel assemblies, respectively. Each cask has a solid neutron shielding material separating the steel body and the outer steel skin. In the thermal accident specified by NRC regulations in 10CFR Part 71, the cask is subjected to an 800[degree]C environment for 30 minutes. The neutron shield need not perform any shielding function during or after the thermal accident, but its behavior must not compromise the ab… more
Date: September 1, 1992
Creator: Boonstra, R.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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