A Plutonium-Contaminated Wound, 1985, USA (open access)

A Plutonium-Contaminated Wound, 1985, USA

A hand injury occurred at a U.S. facility in 1985 involving a pointed shaft (similar to a meat thermometer) that a worker was using to remove scrap solid plutonium from a plastic bottle. The worker punctured his right index finger on the palm side at the metacarpal-phalangeal joint. The wound was not through-and- through, although it was deep. The puncture wound resulted in deposition of ~48 kBq of alpha activity from the weapons-grade plutonium mixture with a nominal 12 to 1 Pu-alpha to {sup 241}Am-alpha ratio. This case clearly showed that DTPA was very effective for decorporation of plutonium and americium. The case is a model for management of wounds contaminated with transuranics: (1) a team approach for dealing with all of the issues surrounding the incident, including the psychological, (2) early surgical intervention for foreign-body removal, (3) wound irrigation with DTPA solution, and (4) early and prolonged DTPA administration based upon bioassay and in vivo dosimetry.
Date: February 2, 2012
Creator: Doran M. Christensen, DO, REAC /TS Associate Director and Staff Physician Eugene H. Carbaugh, CHP, Staff Scientist, Internal Dosimetry Manager, Pacific Northwest National Laboratory, Richland, Washington
Object Type: Article
System: The UNT Digital Library
Radioactive Demonstration of Final Mineralized Waste Forms for Hanford Waste Treatment Plant Secondary Waste by Fluidized Bed Steam Reforming Using the Bench Scale Reformer Platform (open access)

Radioactive Demonstration of Final Mineralized Waste Forms for Hanford Waste Treatment Plant Secondary Waste by Fluidized Bed Steam Reforming Using the Bench Scale Reformer Platform

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold …
Date: February 2, 2012
Creator: Crawford, C. L.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E.; Jantzen, Carol M. & Missimer, D. M.
Object Type: Report
System: The UNT Digital Library
Turkey: Background and U.S. Relations (open access)

Turkey: Background and U.S. Relations

Congress has an active role to play in shaping and overseeing U.S. relations with Turkey, and several Turkish domestic and foreign policy issues have significant relevance for U.S. interests. This report provides background information on Turkey and discusses possible policy options for Members of Congress and the Obama Administration. U.S. relations with Turkey—a longtime North Atlantic Treaty Organization (NATO) ally—have evolved over time as global challenges to U.S. interests have changed. Turkey's economic dynamism and geopolitical importance—it straddles Europe, the Middle East, and Central Asia and now has the world's 16th-largest economy—have increased its influence regionally and globally.
Date: February 2, 2012
Creator: Zanotti, Jim
Object Type: Report
System: The UNT Digital Library
Two-Stage, Integrated, Geothermal-CO2 Storage Reservoirs: An Approach for Sustainable Energy Production, CO2-Sequestration Security, and Reduced Environmental Risk (open access)

Two-Stage, Integrated, Geothermal-CO2 Storage Reservoirs: An Approach for Sustainable Energy Production, CO2-Sequestration Security, and Reduced Environmental Risk

We introduce a hybrid two-stage energy-recovery approach to sequester CO{sub 2} and produce geothermal energy at low environmental risk and low cost by integrating geothermal production with CO{sub 2} capture and sequestration (CCS) in saline, sedimentary formations. Our approach combines the benefits of the approach proposed by Buscheck et al. (2011b), which uses brine as the working fluid, with those of the approach first suggested by Brown (2000) and analyzed by Pruess (2006), using CO{sub 2} as the working fluid, and then extended to saline-formation CCS by Randolph and Saar (2011a). During stage one of our hybrid approach, formation brine, which is extracted to provide pressure relief for CO{sub 2} injection, is the working fluid for energy recovery. Produced brine is applied to a consumptive beneficial use: feedstock for fresh water production through desalination, saline cooling water, or make-up water to be injected into a neighboring reservoir operation, such as in Enhanced Geothermal Systems (EGS), where there is often a shortage of a working fluid. For stage one, it is important to find economically feasible disposition options to reduce the volume of brine requiring reinjection in the integrated geothermal-CCS reservoir (Buscheck et al. 2012a). During stage two, which begins as …
Date: February 2, 2012
Creator: Buscheck, T A; Chen, M; Sun, Y; Hao, Y & Elliot, T R
Object Type: Report
System: The UNT Digital Library

U.S. Department of Energy Summary of 2012 Occupational Radiation Exposure

This poster provides graphic data for 2010-2012 of collective total effective dose (TED) by site, and graphical data for 2008-2012 of components of TED, average measurable TED, percentage of collective TED above dose, collective dose and average measurable dose (1974-2012), and numbers of individuals in the DOE workforce, total number of records of monitored individuals, and number of individuals with a measurable dose. Also, there is a table of the number of individuals receiving >2 rems administrative control level and >5 rems annual limit for 2008-2012.
Date: February 2, 2012
Creator: unknown
Object Type: Poster
System: The UNT Digital Library
VARIABILITY OF KD VALUES IN CEMENTITIOUS MATERIALS AND SEDIMENTS (open access)

VARIABILITY OF KD VALUES IN CEMENTITIOUS MATERIALS AND SEDIMENTS

Measured distribution coefficients (K{sub d} values) for environmental contaminants provide input data for performance assessments (PA) that evaluate physical and chemical phenomena for release of radionuclides from wasteforms, degradation of engineered components and subsequent transport of radionuclides through environmental media. Research efforts at SRNL to study the effects of formulation and curing variability on the physiochemical properties of the saltstone wasteform produced at the Saltstone Disposal Facility (SDF) are ongoing and provide information for the PA and Saltstone Operations. Furthermore, the range and distribution of plutonium K{sub d} values in soils is not known. Knowledge of these parameters is needed to provide guidance for stochastic modeling in the PA. Under the current SRS liquid waste processing system, supernate from F & H Tank Farm tanks is processed to remove actinides and fission products, resulting in a low-curie Decontaminated Salt Solution (DSS). At the Saltstone Production Facility (SPF), DSS is mixed with premix, comprised of blast furnace slag (BFS), Class F fly ash (FA), and portland cement (OPC) to form a grout mixture. The fresh grout is subsequently placed in SDF vaults where it cures through hydration reactions to produce saltstone, a hardened monolithic waste form. Variation in saltstone composition and …
Date: February 2, 2012
Creator: Almond, P.; Kaplan, D. & Shine, E.
Object Type: Report
System: The UNT Digital Library
Veterans and Homelessness (open access)

Veterans and Homelessness

This report discusses several issues relating to homelessness among veterans, which has become more prominent since the beginning of the conflicts in Iraq and Afghanistan.
Date: February 2, 2012
Creator: Perl, Libby
Object Type: Report
System: The UNT Digital Library
Cryogenic thermonuclear fuel implosions on the National Ignition Facility (open access)

Cryogenic thermonuclear fuel implosions on the National Ignition Facility

None
Date: January 2, 2012
Creator: Glenzer, S. H.; Callahan, D.; Mackinnon, A. J.; Kline, J. L.; Grim, G.; Alger, E. T. et al.
Object Type: Article
System: The UNT Digital Library
Fusion-Fission Hybrid for Fissile Fuel Production without Processing (open access)

Fusion-Fission Hybrid for Fissile Fuel Production without Processing

Two scenarios are typically envisioned for thorium fuel cycles: 'open' cycles based on irradiation of {sup 232}Th and fission of {sup 233}U in situ without reprocessing or 'closed' cycles based on irradiation of {sup 232}Th followed by reprocessing, and recycling of {sup 233}U either in situ or in critical fission reactors. This study evaluates a third option based on the possibility of breeding fissile material in a fusion-fission hybrid reactor and burning the same fuel in a critical reactor without any reprocessing or reconditioning. This fuel cycle requires the hybrid and the critical reactor to use the same fuel form. TRISO particles embedded in carbon pebbles were selected as the preferred form of fuel and an inertial laser fusion system featuring a subcritical blanket was combined with critical pebble bed reactors, either gas-cooled or liquid-salt-cooled. The hybrid reactor was modeled based on the earlier, hybrid version of the LLNL Laser Inertial Fusion Energy (LIFE1) system, whereas the critical reactors were modeled according to the Pebble Bed Modular Reactor (PBMR) and the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) design. An extensive neutronic analysis was carried out for both the hybrid and the fission reactors in order to track the fuel …
Date: January 2, 2012
Creator: Fratoni, M.; Moir, R. W.; Kramer, K. J.; Latkowski, J. F.; Meier, W. R. & Powers, J. J.
Object Type: Report
System: The UNT Digital Library