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FLUKA: A Multi-Particle Transport Code

Description: This report describes the 2005 version of the Fluka particle transport code. The first part introduces the basic notions, describes the modular structure of the system, and contains an installation and beginner's guide. The second part complements this initial information with details about the various components of Fluka and how to use them. It concludes with a detailed history and bibliography.
Date: December 14, 2005
Creator: Ferrari, A.; Sala, P. R.; Fasso, A. & Ranft, J.
Partner: UNT Libraries Government Documents Department

Boeing Petroleum Services, Inc. use of overtime at the Strategic Petroleum Reserve

Description: The Strategic Petroleum Reserve (SPR) is responsible for purchasing and storing crude oil to mitigate the potential adverse impact of any future disruptions in crude oil imports. Boeing Petroleum Services, Inc. (BPS) operates the SPR under a US Department of Energy (DOE) management and operating contract. The objective of this audit was to determine whether BPS established and used controls to minimize the use of overtime. The audit disclosed that BPS had established procedures to minimize the use of overtime but did not enforce their use. BPS did not (1) provide timely and adequate written overtime justifications; (2) prepare adequate work schedules; (3) properly implement two employee work shifts; or (4) adhere to DOE overtime budget constraints. These conditions existed because BPS management (a) did not ensure that established procedures were followed and (b) was primarily concerned with ensuring that the Strategic Petroleum Reserve Project Management Office (SPRPMO) contract overtime premium ceiling was not exceeded, rather than minimizing the use of overtime. During the audit, the SPRPMO manager directed BPS to institute tighter overtime controls that should reduce overtime by an estimated $2.2 million annually. Our report identifies various corrective actions for strengthening internal controls and improving the controls over overtime. Management of the SPRPMO concurred fully with the finding, associated recommendations, and estimated monetary impact.
Date: December 14, 1992
Partner: UNT Libraries Government Documents Department

Design criteria document, Maintenance Shop/Support Facility, K-Basin Essential Systems Recovery, Project W-405

Description: During the next 10 years a substantial amount of work is scheduled in the K-Basin Area related to the storage and eventual removal of irradiated N-Reactor fuel. Currently, maintenance support activities are housed in existing structures that were constructed in the early 1950`s. These forty-year-old facilities and their supporting services are substandard, leading to inefficiencies. Because of numerous identified deficiencies and the planned increase in the numbers of K-Basin maintenance personnel, adequate maintenance support facilities that allow efficient operations are needed. The objective of this sub-project of Project W-405 is to provide a maintenance and storage facility which meets the K-Basin Maintenance Organization requirements as defined in Attachment 1. In Reference A, existing guidelines and requirements were used to allocate space for the maintenance activities and to provide a layout concept (See Attachment 2). The design solution includes modifying the existing 190 K-E building to provide space for shops, storage, and administration support functions. The primary reason for the modification is to simplify siting/permitting and make use of existing infrastructure. In addition, benefits relative to design loads will be realized by having the structure inside 190K-E. The new facility will meet the Maintenance Organization approved requirements in Attachment 1 relating to maintenance activities, storage areas, and personnel support services. This sub-project will also resolve outstanding findings and/or deficiencies relating to building fire protection, HVAC requirements, lighting replacement/upgrades, and personnel facilities. Compliance with building codes, local labor agreements and safety standards will result.
Date: December 14, 1994
Creator: Strehlow, M. W. B.
Partner: UNT Libraries Government Documents Department

Design criteria document, Fire Protection Task, K Basin Essential Systems Recovery, Project W-405

Description: The K Basin were constructed in the early 1950`s with a 20 year design life. The K Basins are currently in their third design life and are serving as a near term storage facility for irradiated N Reactor fuel until an interim fuel storage solution can be implemented. In April 1994, Project W-405, K Basin Essential Systems Recovery, was established to address (among other things) the immediate fire protection needs of the 100K Area. A Fire Barrier Evaluation was performed for the wall between the active and inactive areas of the 105KE and 105KW buildings. This evaluation concludes that the wall is capable of being upgraded to provide an equivalent level of fire resistance as a qualified barrier having a fire resistance rating of 2 hours. The Fire Protection Task is one of four separate Tasks included within the scope of Project W405, K Basin Essential systems Recovery. The other three Tasks are the Water Distribution System Task, the Electrical System Task, and the Maintenance Shop/Support Facility Task. The purpose of Project W-405`s Fire Protection Task is to correct Life Safety Code (NFPA 101) non-compliances and to provide fire protection features in Buildings 105KE, 105KW and 190KE that are essential for assuring the safe operation and storage of spent nuclear fuel at the 100K Area Facilities` Irradiated Fuel Storage Basins (K Basins).
Date: December 14, 1994
Creator: Johnson, B. H.
Partner: UNT Libraries Government Documents Department

The concentration of radionuclides and metals in vegetation adjacent to and in the SRL Seepage Basins

Description: In 1991 the trees on the dikes surrounding the SRL Seepage Basins were sampled and analyzed to inventory the contaminants transported from the basins into the vegetation. Tree leaves and wood were collected and analyzed for {sup 90}Sr, {sup 60}Co, {sup 137}Cs, {sup 238}Pu, {sup 239,240}Pu, {sup 242,244}Cm, {sup 241}Am, Ba, Cr, Hg, Mg, Mn, Ni, and Pb. The concentrations of contaminants were influenced by sample type (leaves versus wood), species type (pines versus hardwoods), and location relative to distance from the basin. The total inventory of each contaminant in the trees was estimated. The relationships between leaf and wood, pines and hardwood, location, and mass of the material in each of these classes were used to weight the total inventory estimate. The radionuclide with the largest inventory was 0.7 mCi for {sup 90}Sr. The metallic contaminant with the largest inventory was Mn at 200 gm.
Date: December 14, 1992
Creator: Murphy, C. E. Jr.
Partner: UNT Libraries Government Documents Department

The concentration of radionuclides and metals in vegetation adjacent to and in the SRL Seepage Basins

Description: In 1991 the trees on the dikes surrounding the SRL Seepage Basins were sampled and analyzed to inventory the contaminants transported from the basins into the vegetation. Tree leaves and wood were collected and analyzed for [sup 90]Sr, [sup 60]Co, [sup 137]Cs, [sup 238]Pu, [sup 239,240]Pu, [sup 242,244]Cm, [sup 241]Am, Ba, Cr, Hg, Mg, Mn, Ni, and Pb. The concentrations of contaminants were influenced by sample type (leaves versus wood), species type (pines versus hardwoods), and location relative to distance from the basin. The total inventory of each contaminant in the trees was estimated. The relationships between leaf and wood, pines and hardwood, location, and mass of the material in each of these classes were used to weight the total inventory estimate. The radionuclide with the largest inventory was 0.7 mCi for [sup 90]Sr. The metallic contaminant with the largest inventory was Mn at 200 gm.
Date: December 14, 1992
Creator: Murphy, C. E. Jr.
Partner: UNT Libraries Government Documents Department

45-Day safety screen results for single shell tank 241-AP-106, liquid grab samples, riser 1, 30{degrees} and 150{degrees} in conjunction with evaporator campaign 95-1

Description: This is the 45-Day report for the fiscal year 1995 safety screening characterization of three liquid grab samples from single shell tank 241-AP-106. The required analyses are differential scanning calorimetry (DSC), thermal gravimetric analysis (TGA) and appearance (APPR). No analytes exceeded the notification limits, therefore, secondary analyses (RSST, cyanide, and hot persulfate-total organic carbon) were not required. Summary data tables 2, 3 and 4 present the appearance, DSC and TGA data, respectively. Total alpha analyses are not included in this report, because it is not required for liquid grab samples.
Date: December 14, 1994
Creator: Miller, G. L.
Partner: UNT Libraries Government Documents Department

In Situ Field Testing of Processes

Description: The purpose of this Analysis/Model Report (AMR) is to update and document the data and subsequent analyses from ambient field-testing activities performed in underground drifts of the Yucca Mountain Site Characterization Project (YMP). This revision updates data and analyses presented in the initial issue of this AMR. This AMR was developed in accordance with the ''Technical Work Plan for Unsaturated Zone (UZ) Flow and Transport Process Model Report'' and ''Technical Work Plan for UZ Flow, Transport, and Coupled Processes Process Model Report. These activities were performed to investigate in situ flow and transport processes. The evaluations provide the necessary framework to: (1) refine and confirm the conceptual model of matrix and fracture processes in the unsaturated zone (UZ) and (2) analyze the impact of excavation (including use of construction water and effect of ventilation) on the UZ flow and transport processes. This AMR is intended to support revisions to ''Conceptual and Numerical Models for UZ Flow and Transport'' and ''Unsaturated Zone Flow and Transport Model Process Model Report''. In general, the results discussed in this AMR are from studies conducted using a combination or a subset of the following three approaches: (1) air-injection tests, (2) liquid-release tests, and (3) moisture monitoring using in-drift sensors or in-borehole sensors, to evaluate the impact of excavation, ventilation, and construction-water usage on the surrounding rocks. The liquid-release tests and air-injection tests provide an evaluation of in situ fracture flow and the competing processes of matrix imbibition. Only the findings from testing and data not covered in the ''Seepage Calibration Model and Seepage Testing Data'' are analyzed in detail in the AMR.
Date: December 14, 2001
Creator: Wang, J.
Partner: UNT Libraries Government Documents Department