Resource Type
Serial/Series Title
Chemical Processing Department Monthly Report
41
Winter Fuels Report
5
Irradiation Processing Department Monthly Record Report
3
Hanford Laboratories Operation Monthly Activities Report
2
Hanford Works Monthly Report
2
Irradiation Processing Department Monthly Report
2
A Real-Time Coal Content/Ore Grade (C2OG) Sensor, Technical Report
1
Fiscal Year 1977
1
Fiscal Year 1992
1
Fiscal Year 1993
1
17 More
Country
States
Decade
Month
Day
Language
1,857 Matching Results
Results open in a new window/tab.
prev
Results:
1,849 - 1,857 of
1,857
Potential radiation damage: Storage tanks for liquid radioactive waste
High level waste at SRS is stored in carbon steel tanks constructed during the period 1951 to 1981. This waste contains radionuclides that decay by alpha, beta, or gamma emission or are spontaneous neutronsources. Thus, a low intensity radiation field is generated that is capable of causing displacement damage to the carbon steel. The potential for degradation of mechanical properties was evaluated by comparing the estimated displacement damage with published data relating changes in Charpy V-notch (CVN) impact energy to neutron exposure. Experimental radiation data was available for three of the four grades of carbonsteel from which the tanks were constructed and is applicable to all four steels. Estimates of displacement damage arising from gamma and neutron radiation have been made based on the radionuclide contents for high level waste that are cited in the Safety Analysis Report (SAR) for the Liquid Waste Handling Facilities in the 200-Area. Alpha and beta emissions do not penetrate carbon steel to a sufficient depth to affect the bulk properties of the tank walls but may aggravate corrosion processes. The damage estimates take into account the source of the waste (F- or H-Area), the several types of tank service, and assume wateras an attenuating …
Date:
August 21, 1992
Creator:
Caskey, G. R., Jr.
System:
The UNT Digital Library
Predictions and acceptance criteria for K Reactor startup and power ascension
Calculations have been performed to determine the reactivity worth of various partial rod movements to be performed in the K-14 Startup and Power Ascension Test Program. Some tests have been revised since the issuance of the predictions and acceptance criteria for the startup/power ascension testing procedure, RSP 90-007. The tests were modified to account for changes in the Technical Specifications concerning control rod positioning. This addendum describes the changes to the test configurations and documents the revised expectation values for the partial rod insertion tests. Additional calculations were performed to cover the complete range of possible full rod positions at the zero power testing level.
Date:
October 21, 1991
Creator:
Bond, R. A., Jr.
System:
The UNT Digital Library
Recommended Method To Account For Daughter Ingrowth For The Portsmouth On-Site Waste Disposal Facility Performance Assessment Modeling
A 3-D STOMP model has been developed for the Portsmouth On-Site Waste Disposal Facility (OSWDF) at Site D as outlined in Appendix K of FBP 2013. This model projects the flow and transport of the following radionuclides to various points of assessments: Tc-99, U-234, U-235, U-236, U-238, Am-241, Np-237, Pu-238, Pu-239, Pu-240, Th-228, and Th-230. The model includes the radioactive decay of these parents, but does not include the associated daughter ingrowth because the STOMP model does not have the capability to model daughter ingrowth. The Savannah River National Laboratory (SRNL) provides herein a recommended method to account for daughter ingrowth in association with the Portsmouth OSWDF Performance Assessment (PA) modeling.
Date:
June 21, 2013
Creator:
Phifer, Mark A. & Smith, Frank G., III
System:
The UNT Digital Library
Urban Wood/Coal Co-Firing in the Bellefield Boilerplant
During the third quarter, important preparatory work was continued so that the experimental activities can begin early in the fourth quarter. Authorization was awaited in response to the letter that was submitted to the Allegheny County Health Department (ACHD) seeking an R&D variance for the air permit at the Bellefield Boiler Plant (BBP). Verbal authorizations were received from the Pennsylvania Department of Environmental Protection (PADEP) for R&D variances for solid waste permits at the J. A. Rutter Company (JARC), and Emery Tree Service (ETS). Construction wood was acquired from Thompson Properties and Seven D Corporation. Forty tons of pallet and construction wood were ground to produce BioGrind Wood Chips at JARC and delivered to Mon Valley Transportation Company (MVTC). Five tons of construction wood were milled at ETS and half of the product delivered to MVTC. Discussions were held with BBP and Energy Systems Associates (ESA) about the test program. Material and energy balances on Boiler No.1 and a plan for data collection were prepared. Presentations describing the University of Pittsburgh Wood/Coal Co-Firing Program were provided to the Pittsburgh Chapter of the Pennsylvania Society of Professional Engineers, and the Upgraded Coal Interest Group and the Biomass Interest Group (BIG) of …
Date:
August 21, 2001
Creator:
Cobb, James T., Jr.; Geiger, Gene E.; III, William W. Elder; Barry, William P.; Wang, Jun & Li, Hongming
System:
The UNT Digital Library
Preliminary Dynamic Modeling of the Hanford Waste Treatment Plant Melter Offgas
This report documents preliminary versions of the models that include the components of the offgas systems from the melters through the exhaust stacks and the vessel ventilation systems. The models consider only the two major chemical species in the offgas stream: air and steam or water vapor. Model mass and energy balance calculations are designed to show the dynamic behavior of gas pressure and flow throughout the offgas systems in response to transient driving forces.
Date:
September 21, 2001
Creator:
Smith, F. G., III
System:
The UNT Digital Library
Direct catalytic conversion of methane and light hydrocarbon gases. Quarterly report No. 2, January 16, 1987--April 15, 1987
The goal of this research is to develop catalysts that directly convert methane and light hydrocarbons to intermediates that can, as economics dictate, be subsequently converted either to liquid fuels or value-added chemicals. In this program we are exploring two approaches to developing such catalysts. The first approach consists of developing advanced catalysts for reforming methane. We will prepare the catalysts by reacting organometallic complexes of transition metals (Fe, Ru, Rh, and Re) with zeolitic and rare-earth-exchanged zeolitic supports to produce surfaceconfined metal complexes in the zeolite pores. Our second approach entails synthesizing the porphyrin and phthalocyanine complexes of Cr, Mn, Ru, Fe, and/or Co within the pores of zeolitic supports for use as selective oxidation catalysts for methane and light hydrocarbons. During the second quarter of this project, we concentrated on methane reforming. Two ruthenium clusters (Ru{sub 4} and Ru{sub 6}) supported on three types of support materials ({beta}-alumina, 5 {Angstrom} molecular sieves, and {gamma}-zeolite) were tested for methane reforming. The effects of cluster size, supporting material, and reaction conditions were evaluated. The methane conversions range from 1.74 to 10.11% at 750{degrees}C. The reaction product contains hydrogen, C{sub 2} hydrocarbons, and C{sub 6} or higher hydrocarbons. Up to 48.34% …
Date:
May 21, 1987
Creator:
Wilson, R. B., Jr. & Chan, Yee Wai
System:
The UNT Digital Library
Compilation of Disposable Solid Waste Cask Evaluations
The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask …
Date:
June 21, 2007
Creator:
Thielges, J. R. & Chastain, S. A.
System:
The UNT Digital Library
Potential radiation damage: Storage tanks for liquid radioactive waste
High level waste at SRS is stored in carbon steel tanks constructed during the period 1951 to 1981. This waste contains radionuclides that decay by alpha, beta, or gamma emission or are spontaneous neutronsources. Thus, a low intensity radiation field is generated that is capable of causing displacement damage to the carbon steel. The potential for degradation of mechanical properties was evaluated by comparing the estimated displacement damage with published data relating changes in Charpy V-notch (CVN) impact energy to neutron exposure. Experimental radiation data was available for three of the four grades of carbonsteel from which the tanks were constructed and is applicable to all four steels. Estimates of displacement damage arising from gamma and neutron radiation have been made based on the radionuclide contents for high level waste that are cited in the Safety Analysis Report (SAR) for the Liquid Waste Handling Facilities in the 200-Area. Alpha and beta emissions do not penetrate carbon steel to a sufficient depth to affect the bulk properties of the tank walls but may aggravate corrosion processes. The damage estimates take into account the source of the waste (F- or H-Area), the several types of tank service, and assume wateras an attenuating …
Date:
August 21, 1992
Creator:
Caskey, G. R., Jr.
System:
The UNT Digital Library
Molecular Characterization of the Role of a Calcium Channel in Plant Development
A stimulus-induced change in cellular Ca2+ levels is a critical component of energy transduction in plant and animal development. Demonstrating Ca2+'s involvement in any developmental process requires identification of mechanisms that regulate these Ca2+ changes. In plants, biochemical studies have implicated the activity of Ca2+ channels in increases in cellular Ca2+ levels; however, molecular evidence for these transporters is lacking. Our studies used the mosses Physcomitrella patens and Funaria hygrometrica to establish a role for Ca2+ in hormone-induced morphogenesis and to use this developmental process to identify transporters responsible for increasing cytosolic Ca2+ levels. Using 1,4-dihydropyridines (DHPs), molecules that block Ca2+ movement through voltage-dependent channels in animal cells, we have shown that Ca2+ is important early in the transition from filamentous to meristematic-like growth that occurs in response to the plant hormone cytokinin. In addition to inhibiting moss growth (see below), these Ca2+ channel blockers prevent Ca2+ transport into moss cells (Schumaker and Gizinski, 1993) and bind specifically to two proteins in the moss plasma membrane (Schumaker and Gizinski, 1994; 1996; Dietrich et al., unpublished results). We used tandem mass spectrometry of the partially purified DHP-binding proteins with the goal of identifying the putative Ca2+ channel and providing sequence information …
Date:
December 21, 2004
Creator:
Schumaker, Karen S.
System:
The UNT Digital Library