This report describes a research project that was conducted from August 15, 1985 to February 28, 1992. The project was based on the ultrasonic studies of natural and synthetic silicate melts, and the study of Brillouin scattering of synthetic silicates and oxides. Measurements of the compressional wave velocity and attenuation can be established using the ultrasonic methods. Temperature dependences of silicates can be established by the Brillouin scattering. (MB)

A summary of total cumulative fuel consumption differences by fuel type through 1990 for four improvement scenarios is presented for Commonwealth Edison Company (CE) and for Illinois Power Company (IP). In all scenarios, liquid-fuel consumption is reduced. Generation is shifted to the coal and/or nuclear units for which improved availability has been assumed. For a 2% improvement in both planned (POR) and forced outage rates (FOR), a total of more than 16 million barrels of No. 6 oil will have been saved by 1990 by the two companies. This is the result of improving 10,894 MW on the CE system and 2234 MW on the IP system. For the two utilities combined, gross savings (in 1978 dollars) range from $83 million for a 1% POR improvement to $346 million for 2% improvements in both POR and FOR. In terms of their effect on ratepayers, these savings would be even greater since gross receipt taxes and other charges would be applied to a smaller-generation cost base under the improvement scenarios. Caution must be exercised however, since results do not take into consideration the costs of achieving the improved performance. The proportion of net benefits that would be passed on to ratepayers …

A safety analysis was performed to determine if normal operations and/or potential accidents at the 851 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but two of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exceptions were the linear accelerator and explosives, which were classified as moderate hazards per the requirements given in DOE Order 5481.1A. This safety analysis concluded that the operation at this facility will present no undue risk to the health and safety of LLNL employees or the public.

"World best practice" energy intensity values, representingthe most energy-efficient processes that are in commercial use in atleast one location worldwide, are provided for the production of iron andsteel, aluminium, cement, pulp and paper, ammonia, and ethylene. Energyintensity is expressed in energy use per physical unit of output for eachof these commodities; most commonly these are expressed in metric tonnes(t). The energy intensity values are provided by major energy-consumingprocesses for each industrial sector to allow comparisons at the processlevel. Energy values are provided for final energy, defined as the energyused at the production facility as well as for primary energy, defined asthe energy used at the production facility as well as the energy used toproduce the electricity consumed at the facility. The "best practice"figures for energy consumption provided in this report should beconsidered as indicative, as these may depend strongly on the materialinputs.

The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights signifi cant environmental and public protection programs and efforts. Some historical and early 2008 information is included where appropriate.

An advanced simulation environment to model incompressible MHD flows relevant to blanket conditions in fusion reactors has been developed at HyPerComp in research collaboration with TEXCEL. The goals of this phase-II project are two-fold: The first is the incorporation of crucial physical phenomena such as induced magnetic field modeling, and extending the capabilities beyond fluid flow prediction to model heat transfer with natural convection and mass transfer including tritium transport and permeation. The second is the design of a sequence of benchmark tests to establish code competence for several classes of physical phenomena in isolation as well as in select (termed here as “canonical”,) combinations. No previous attempts to develop such a comprehensive MHD modeling capability exist in the literature, and this study represents essentially uncharted territory. During the course of this Phase-II project, a significant breakthrough was achieved in modeling liquid metal flows at high Hartmann numbers. We developed a unique mathematical technique to accurately compute the fluid flow in complex geometries at extremely high Hartmann numbers (10,000 and greater), thus extending the state of the art of liquid metal MHD modeling relevant to fusion reactors at the present time. These developments have been published in noted international journals. …

This literature review presents treatment options for nitrate, iodine-129, and uranium, which are present in groundwater at the 200-ZP-I Groundwater Operable Unit (OU) within the 200 West Area of the Hanford Site. The objective of this review is to determine available methods to treat or sequester these contaminants in place (i.e., in situ) or to pump-and-treat the groundwater aboveground (i.e., ex situ). This review has been conducted with emphasis on commercially available or field-tested technologies, but theoretical studies have, in some cases, been considered when no published field data exist. The initial scope of this literature review included only nitrate and iodine-I 29, but it was later expanded to include uranium. The focus of the literature review was weighted toward researching methods for treatment of nitrate and iodine-129 over uranium because of the relatively greater impact of those compounds identified at the 200-ZP-I OU.

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. The 2007 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. A very small amount of material had seeped from Tank 12 from a previously identified leaksite. The material observed had dried on the tank wall and did not reach the annulus floor. A total of 5945 photographs were made and 1221 visual and video inspections were performed during 2007. Additionally, ultrasonic testing was performed on four Waste Tanks (15, 36, 37 and 38) in accordance with approved inspection plans that met the requirements of WSRC-TR-2002- 00061, Revision 2 'In-Service Inspection Program for High Level Waste Tanks'. The Ultrasonic Testing (UT) In-Service Inspections (ISI) are documented in a separate report that is prepared by the ISI programmatic Level III UT Analyst. Tanks 15, 36, 37 and 38 are documented in 'Tank Inspection NDE Results for Fiscal Year 2007'; WSRC-TR-2007-00064.

This report provides documentation of the design and certification of drop pad (targets) at the National Transportation Research Center (NTRC) Packaging Research Facility(PRF). Based on the evaluation performed, it has been demonstrated that the small (interior) drop pad (target) meets the regulatory definition of a flat, essentially unyielding, horizontal surface for packages weighing up to 3,150 lb (1,432 kg). The large (exterior) drop pad (target) meets the regulatory definition of a flat, essentially unyielding, horizontal surface for packages weighing up to 28,184 lb (12,811 kg).

In 2001, under DOE's Superconductivity Partnership Initiative (SPI), E. I. du Pont de Nemours & Co. (Dupont) was awarded a cost-share contract to build a fully functional full-scale model high temperature superconducting reciprocating magnet unit specifically designed for the koalin clay industry. After competitive bidding, American Superconductor (AMSC) was selected to provide the coil for the magnet. Dupont performed the statement of work until September 2004, when it stopped work, with the concurrence of DOE, due to lack of federal funds. DOE had paid all invoices to that point, and Dupont had provided all cost share. At this same time, Dupont determined that this program did not fit with its corporate strategies and notified DOE that it was not interesting in resuming the program when funding became available. AMSC expressed interest in assuming performance of the Agreement to Dupont and DOE, and in March 2005, this project was transferred to AMSC by DOE amendment to the original contract and Novation Agreement between AMSC and Dupont. Design drawings and some hardware components and subassemblies were transferred to AMSC. However, no funding was obligated by DOE and AMSC never performed work on the project. This report contains a summary of the work …

A safety analysis was performed to determine if normal operations and/or potential accidents at the 850 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but one of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exception was explosives, which was classified as a moderate hazard per the requirements given in DOE Order 5481.1A. This safety analysis concluded that the operation at this facility will present no undue risk to the health and safety of LLNL employees or the public.

A safety analysis was performed to determine if normal operations and/or potential accidents at the 804 and 845 Firing Facilities at Site 300 could present undue hazards to the general public, peronnel at Site 300, or have an adverse effect on the environment. The normal operation and credible accident that might have an effect on these facilities or have off-site consequence were considered. It was determined by this analysis that all but one of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exception was explosives. Since this hazard has the potential for causing significant on-site and minimum off-site consequences, Bunkers 804 and 845 have been classified as moderate hazard facilties per DOE Order 5481.1A. This safety analysis concluded that the operation at these facilities will present no undue risk to the health and safety of LLNL employees or the public.

The purpose of this investigation was to evaluate several different cleaning procedures on welds with very low heat inputs. The study evaluated the Oak Ridge Y-12 Plant's chemical cleaning, another type of chemical cleaning, ion cleaning, and diamond-machined cleaning. The results showed that the diamond-machining process provides better weld joint surfaces and sound welds with minimum oxide inclusion and porosity.

Consider the problem of testing goodness-of-fit to a specified location-scale family when evidence is to be combined from several independent samples, from populations with possibly different location and scale parameters. The procedure studied is that of computing standardized residuals from each sample and then combining these into one set to be treated essentially as though they came from one sample. It is shown that the limiting distribution of any location-scale invariant goodness-of-fit statistic so applied is precisely the same as for the corresponding one-sample problem. 13 references.

The Emergency Core Cooling System (ECCS) for the LOFT reactor may need to be disabled for modifications or repairs of hardware or instrumentation or for component testing during periods when the reactor system is hot and pressurized, or it may be desirable to enable the ECCS to be disabled without the necessity of cooling down and depressurizing the reactor. LTR 113-47 has shown that the LOFT ECCS can be safely bypassed or disabled when the total core power does not exceed 25 kW. A modified policy involves disabling the automatic actuation of the LOFT ECCS, but still retaining the manual activation capability. Disabling of the automatic actuation can be safely utilized, without subjecting the fuel cladding to unacceptable temperatures, when the LOFT power decays to 70 kW; this power level permits a maximum delay of 20 minutes following a LOCA for the manual actuation of ECCS.

Modifications to the 100-K water plant will be made, under Project CG-775, to increase total process water flow rates to 175,000 gpm or greater. Included in the modifications will be the installation of new pump impellers for the primary and secondary process water pumps located in the 190-K Buildings.

This report describes a research project that was conducted from August 15, 1985 to February 28, 1992. The project was based on the ultrasonic studies of natural and synthetic silicate melts, and the study of Brillouin scattering of synthetic silicates and oxides. Measurements of the compressional wave velocity and attenuation can be established using the ultrasonic methods. Temperature dependences of silicates can be established by the Brillouin scattering. (MB)

Memos, agendas, regional hydrology, and field trip reports are included for the INEL oversight program; they relate to the hydrogeology of INEL and ICPP, and to the cleanup effort at these sites.

Results are reported in two areas: (1) understanding the mechanism of superplasticity in those that show unusual resistance to intergranular cavitation, and (2) understanding the growth of heteroepitaxial films of oxides by CVD (NiO, TiO{sub 2}).

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During the 0000--0800 shift on August 21, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 2, 3 and 4 monitors indicating a possible fuel element failure in Loop 1. The KER Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant and coupon samples taken from Loop 1.

Recent high tank drawdown data obtained at F reactor during periodic high velocity flushes indicated a reduction in flow to the reactor due to building of corrosion products in the high tank discharge lines. The apparent flow reduction at F reactor was verified by conducting a high tank drawdown test. Visual inspection of B, D, and F high tank discharge lines revealed comparable densities of corrosion product buildup, and high tank drawdown data during high velocity flushes at B and D also indicated a reduction in flow. High tank flow rate to the reactor under simulated emergency conditions needed to be accurately determined to establish current backup adequacy. This report presents the results of the tests which were conducted at D reactor on January 20, 1963 and at B reactor on February 11, 1963.

In 2002, the EPA amended 40 CFR 61 Subpart H and 40 CFR 61 Appendix B Method 114 to include requirements from ANSI/HPS N13.1-1999 Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stack and Ducts of Nuclear Facilities for major emission points. Additionally, the WDOH amended the Washington Administrative Code (WAC) 246-247 Radiation protection-air emissions to include ANSI/HPS N13.1-1999 requirements for major and minor emission points when new permitting actions are approved. A result of the amended regulations is the requirement to prepare a written technical basis for the radiological air emission sampling and monitoring program. A key component of the technical basis is the Potential Impact Category (PIC) assigned to an emission point. This paper discusses the PIC assignments for the Pacific Northwest National Laboratory (PNNL) Integrated Laboratory emission units; this revision includes five PIC categories.

Memos, agendas, regional hydrology, and field trip reports are included for the INEL oversight program; they relate to the hydrogeology of INEL and ICPP, and to the cleanup effort at these sites.