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Bench-Scale Studies With Mercury Contaminated SRS Soil

Description: The Savannah River Technology Center (SRTC) has been charactered by the Department of Enregy (DOE) - Office of Technology Development (OTD) to investigate vitrification technology for the treatment of Low Level Mixed Wastes (LLMW). In fiscal year 1995, LLW streams containing mercury and organics were targeted. This report will present the results of studies with mercury contaminated waste. In order to successfully apply vitrification technology to LLMW, the types and quantities of glass forming… more
Date: May 8, 1996
Creator: Cicero, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Utilization of Folk Song Elements in Selected Works by Ralph Vaughan Williams and Percy Grainger with Subsequent Treatment Exemplified in the Wind Band music of David Stanhope

Description: An examination of the utilization of folk song elements in the wind band music of Australian composer David Stanhope, represented in two movements ("Lovely Joan" and "Rufford Park Poachers") from his Folk Songs for Band. Sets 1 and 2. Included is an historical overview of English folk music, emphasizing the theoretical properties of the English folk song and the events surrounding the modern renaissance of British folk music. Background information related to the musical development of Vaughan … more
Date: May 1996
Creator: Birdwell, John Cody
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries
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Irradiation behavior of uranium oxide-aluminum dispersion fuel

Description: An oxide version of the DART code has been generated in order to assess the irradiation behavior of UO{sub 2}-Al dispersion fuel. The aluminum-fuel interaction models were developed based on U{sub 3}O{sub 8}-Al irradiation data. Deformation of the fuel element occurs due to fuel particle swelling driven by both solid and gaseous fission products, as well as a consequence of the interaction between the fuel particles and the aluminum matrix. The calculations show, that with the assumption that t… more
Date: December 1, 1996
Creator: Hofman, G.L.; Rest, J. & Snelgrove, J.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Acceptance test report for high pressure water jet system feed pump

Description: This document summarizes results of WHC-SD-SNF-ATP-016, Rev. 0 ``Acceptance Test Procedure High Pressure Water Jet System``, conducted on December 20, 1995 and December 22, 1995. This jet supplies water at 15,000 psi @ 15 gpm to nozzles to clean surfaces of empty fuel storage canisters.
Date: March 12, 1996
Creator: Crystal, J.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation data for the MFA-1 and MFA-2 tests during FFTF cycles 10A and 10B

Description: This report provides key information on the irradiation environment of the MONJU fuel test MFA-1 and MFA-2 in the Fast Flux Test Facility (FFTF) during operating cycles 10A and 10B.This information includes the fission powers, neutron fluxes, sodium temperatures and sodium flow rates in MFA-1, MFA-2, and adjacent assemblies. It also includes MFA-1 and MFA-2 compositions as a function of exposure during cycles 10A and 10B. The work was performed at the request of Power Reactor and Nuclear Fuels … more
Date: October 30, 1996
Creator: Nelson, J.V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Leu conversion status of U.S. research reactors: September 1996

Description: At the request of the Department of Energy, the RERTR Program has summarized the conversion status of research and test reactors in the United States and has made estimates of the uranium densities that would be needed to convert the reactors with power levels greater than or equal to 1 MW from Highly Enriched Uranium (HEU) (greater than or equal to 20% U-235) to Lightly Enriched Uranium (LEU) (less than 20% U-235) fuels. Detailed conversion studies for each of the reactors need to be completed… more
Date: September 1, 1996
Creator: Matos, J. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Neutronic performance of high-density LEU fuels in water-moderated and water-reflected research reactors

Description: At the Reduced Enrichment for Research and Test Reactors (RERTR) meeting in September 1994, Durand reported that the maximum uranium loading attainable with U{sub 3}Si{sub 2} fuel is about 6.0 g U/cm{sup 3}. The French Commissariat a l`Energie Atomique (CEA) plan to perform irradiation tests with 5 plates at this loading. Compagnie pour L`Etude et La Realisation de Combustibles Atomiques (CERCA) has also fabricated a few uranium nitride (UN) plates with a uranium density in the fuel meat of 7.0… more
Date: September 1, 1996
Creator: Bretscher, M.M. & Matos, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of burnable poison in Ford Nuclear Reactor fuel to extend fuel lifetime. Final report, August 1, 1994--September 29, 1996

Description: The objective of the project was to establish the feasibility of extending the lifetime of fuel elements for the Ford Nuclear Reactor (FNR) by replacing current aluminide fuel with silicide fuel comprising a heavier uranium loading but with the same fissile enrichment of 19.5 wt% {sup 235}U. The project has focused on fuel designs where burnable absorbers, in the form of B{sub 4}C, are admixed with uranium silicide in fuel plates so that increases in the control reactivity requirements and peak… more
Date: December 1, 1996
Creator: Burn, R. R. & Lee, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Numerical modeling of giant magnetoresistance effect for application to magnetic data storage. CRADA final report for CRADA number Y-1293-0175

Description: The giant magnetoresistance (GMR) effect is a change in the electrical resistance of a magnetically inhomogeneous material that occurs when an applied magnetic field aligns the magnetic moments in different regions of the material. GMR allows the development of very small and sensitive devices for detecting and measuring magnetic fields. Such devices have many applications including the sensing of data on magnetic disk drives and in magnetic random access memory cells. This Cooperative Research… more
Date: September 16, 1996
Creator: Butler, W. H. & Gurney, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The design and performance of the research reactor fuel counter

Description: This paper describes the design features, hardware specifications, and performance characteristics of the Research Reactor Fuel Counter (RRFC) System. The system is an active mode neutron coincidence counter intended to assay material test reactor fuel assemblies under water. The RRFC contains 12 {sup 3}He tubes, each with its own preamplifier, and a single ion chamber. The neutron counting electronics are based on the Los Alamos Portable Shift Register (PSR) and the gamma readout is a manual-r… more
Date: September 1, 1996
Creator: Abhold, M. E.; Hsue, S. T.; Menlove, H. O.; Walton, G. & Holt, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dry spent fuel cask monitoring by {sup 252}Cf-source-driven frequency analysis measurements

Description: If developed, a nondestructive method would be useful for verifying canister contents without requiring the canister to be opened. This paper addresses the application of the {sup 252}Cf-source-driven frequency analysis measurements for verification of the fissile material content of sealed spent fuel canisters. The cross-power spectral density (CPSD) between the {sup 252}Cf source in an ionization chamber and external neutron detectors depends only on the induced fission rate in the fissile sy… more
Date: October 1, 1996
Creator: Valentine, T.E.; Mattingly, J.K. & Mihalczo, J.T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Delayed neutron emission measurements from fast fission of U-235 and Np-237

Description: Experiments have been designed and conducted to measure the periods and yields of delayed neutrons from fast fission of {sup 235}U and {sup 237}Np. These measurements were performed in a pool type reactor using a fast flux in-core irradiation device. The energy dependent neutron flux spectrum within the irradiation device was characterized using a foil activation technique and the SAND-II unfolding code. Five delayed neutron groups were measured. The total yield (sum of the five group yields) f… more
Date: September 1, 1996
Creator: Charlton, W. S.; Parish, T. A.; Raman, S.; Shinohara, Nubuo & Andoh, Masaki
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Advanced neutron source reactor conceptual safety analysis report, three-element-core design: Chapter 15, accident analysis

Description: In order to utilize reduced enrichment fuel, the three-element-core design for the Advanced Neutron Source has been proposed. The proposed core configuration consists of inner, middle, and outer elements, with the middle element offset axially beneath the inner and outer elements, which are axially aligned. The three-element-core RELAP5 model assumes that the reactor hardware is changed only within the core region, so that the loop piping, heat exchangers, and pumps remain as assumed for the tw… more
Date: February 1, 1996
Creator: Chen, N. C. J.; Wendel, M. W.; Yoder, G. L. & Harrington, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Use of WIMS-E lattice code for prediction of the transuranic source term for spent fuel dose estimation

Description: A recent source term analysis has shown a discrepancy between ORIGEN2 transuranic isotopic production estimates and those produced with the WIMS-E lattice physics code. Excellent agreement between relevant experimental measurements and WIMS-E was shown, thus exposing an error in the cross section library used by ORIGEN2.
Date: April 15, 1996
Creator: Schwinkendorf, K.N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

An alternative to the SAS2H/ORIGEN-S sequence to account for water-density effects in BWR systems

Description: A scheme to generate one-group problem-dependent cross-section libraries for point-depletion calculations with the ORIGEN-S code was developed as an alternative to the SAS2H sequence of the SCALE code system. The methodology, named Automatic Rapid Processing (ARP), generates libraries by interpolating in SAS2H precomputed cross section libraries. The method has been used to generate ORIGEN-S cross section libraries on a personal computer resulting in a great reduction of computer time without a… more
Date: September 1, 1996
Creator: Leal, L. C.; Hermann, O. W.; Ryman, J. C. & Broadhead, B. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Hanford`s spent nuclear fuel retrieval: an agressive agenda

Description: Starting December 1997, spent nuclear fuel that has been stored in the K Reactor Fuel Storage Basins will be retrieved over a two year period and repackaged for long term dry storage. The aging and sometimes corroding fuel elements will be recovered and processed using log handled tools and teleoperated manipulator technology. The U.S. Department of Energy (DOE) is committed to this urgent schedule because of the environmental threats to the groundwater and nearby the Columbia River.
Date: December 6, 1996
Creator: Shen, E.J., Westinghouse Hanford
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The transuranium elements: From neptunium and plutonium to element 112

Description: Beginning in the 1930`s, both chemists and physicists became interested in synthesizing new artificial elements. The first transuranium element, Np, was synthesized in 1940. Over the past six decades, 20 transuranium elements have been produced. A review of the synthesis is given. The procedure of naming the heavy elements is also discussed. It appears feasible to produce elements 113 and 114. With the Berkeley Gas-filled Separator, it should be possible to reach the superheavy elements in the … more
Date: July 26, 1996
Creator: Hoffman, D.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Precombustion removal of hazardous air pollutant precursors. Third quarterly technical progress report, April 1, 1996--June 30, 1996

Description: This project involves the development of an optimized, bench-scale processing circuit capable of efficiently removing trace elements from run-of-mine coals. The optimized circuit will be developed using characterization data obtained from detailed washability studies and release analyses tests conducted with several eastern US coals. The optimized circuit will incorporate a variety of conventional and advanced coal cleaning processes which are believed to be the most cost-effective and commerci… more
Date: July 19, 1996
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Conversion of ion-exchange resins, catalysts and sludges to glass with optional noble metal recovery using the GMODS process

Description: Chemical processing and cleanup of waste streams (air and water) typically result in products, clean air, clean water, and concentrated hazardous residues (ion exchange resins, catalysts, sludges, etc.). Typically, these streams contain significant quantities of complex organics. For disposal, it is desirable to destroy the organics and immobilize any heavy metals or radioactive components into stable waste forms. If there are noble metals in the residues, it is desirable to recover these for r… more
Date: November 1996
Creator: Forsberg, C. W. & Beahm, E. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Cleaning optimization for reduced chemical usage

Description: The use of dilute SC-1 (NH40H:H202:H20) chemistry cleaning processes for particle removal from silicon surfaces has been investigated. Dilute chemistries can be highly effective, especially when high- frequency acoustic energy (megasonics) is applied. The high particle removal efficacy of the dilute chemistry processes presumably arises due to increased double layer effects caused by reduced ionic strength. Dilute chemistry SC- I solutions exhibit somewhat reduced efficacy for removal of certai… more
Date: November 1, 1996
Creator: Resnick, P.J.; Simonson, G.C.; Matlock, C.A. & Kelly, M.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Description of TASHA: Thermal Analysis of Steady-State-Heat Transfer for the Advanced Neutron Source Reactor

Description: This document describes the code used to perform Thermal Analysis of Steady-State-Heat-Transfer for the Advanced Neutron Source (ANS) Reactor (TASHA). More specifically, the code is designed for thermal analysis of the fuel elements. The new code reflects changes to the High Flux Isotope Reactor steady-state thermal-hydraulics code. These changes were aimed at both improving the code`s predictive ability and allowing statistical thermal-hydraulic uncertainty analysis to be performed. A signific… more
Date: October 1, 1996
Creator: Morris, D. G.; Chen, N. C.; Nelson, W. R. & Yoder, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Statistical analysis of radiochemical measurements of TRU radionuclides in REDC waste

Description: This report summarizes results of the study on the isotopic ratios of transuranium elements in waste from the Radiochemical Engineering Development Center actinide-processing streams. The knowledge of the isotopic ratios when combined with results of nondestructive assays, in particular with results of Active-Passive Neutron Examination Assay and Gamma Active Segmented Passive Assay, may lead to significant increase in precision of the determination of TRU elements contained in ORNL generated w… more
Date: October 1, 1996
Creator: Beauchamp, J.; Downing, D.; Chapman, J.; Fedorov, V.; Nguyen, L.; Parks, C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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