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A report from the SUNY Albany Particle Physics Group summarizing our activities on the ATLAS experiment at the Large Hadron Collider. We summarize our work: on data analysis projects, on efforts to improve detector performance, and on service work to the experiment.

Sprint is one of the telecommunications industry leaders in the deployment of hydrogen fuel cell (HFC) systems to provide backup power for their mission critical wireless network facilities. With several hundred fuel cells commissioned in California, states in the gulf coast region, and along the upper eastern seaboard. A strong incentive for advancing the integration of fuel cells into the Sprint network came through the award of a Department of Energy (DOE) grant focused on Market Transformation activities for project (EE0000486). This grant was funded by the 2009 American Recovery and Reinvestment Act (ARRA). The funding provided by DOE ($7.295M) was allocated to support the installation of 260 new HFC systems, equipped with an on-site refillable Medium Pressure Hydrogen Storage Solution (MPHSS), as well as for the conversion of 21 low pressure hydrogen systems to the MPHSS, in hopes of reducing barriers to market acceptance.

Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length. Unfortunately, several nonconformance reports have been generated to document the discovery of a certified machine found out of tolerance during a calibration closeout. In an effort to reduce risk to product quality two solutions were proposed – shorten the calibration cycle which could be costly, or perform an interim check to monitor the machine’s performance between cycles. The CMM interim check discussed makes use of Renishaw’s Machine Checking Gauge. This off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. Data was gathered, analyzed, and simulated from seven machines in seventeen different configurations to create statistical process control run charts for on-the-floor monitoring.

This is the closeout report for the Indiana University portion of the National Computational Infrastructure for Lattice Gauge Theory project supported by the United States Department of Energy under the SciDAC program. It includes information about activities at Indian University, the University of Arizona, and the University of Utah, as those three universities coordinated their activities.

During the period of this grant faculty members, post-docs, and students, have participated in a number of experiments. These were KTeV, D0, CMS, and Mu2E. We have made important contributions to the hardware and the physics goals of each of these experiments.

The High Energy Physics group at the University of South Alabama has been supported by this research grant (DE-FG02-96ER40970) since 1996. One researcher, Dr. Merrill Jenkins, has been supported on this grant during this time worked on fixed target experiments at the Fermi National Accelerator Laboratory, west of Chicago, Illinois. These experiments have been E-705, E-771, E-871 (HyperCP) and E-921 (CKM) before it was canceled for budgetary reasons. After the cancellation of CKM, Dr. Jenkins joined the Compact Muon Solenoid (CMS) experiment as an associate member via the High Energy Physics Group at the Florida State University. A second, recently tenured faculty member, Dr. Romulus Godang joined the group in 2009 and has been supported by this grant since then. Dr. Godang is working on the BaBaR experiment at SLAC and has joined the Belle-II experiment located in Japan at KEK. According to the instructions sent to us by our grant monitor, we are to concentrate on the activities over the last three years in this closeout report.

New funding is sought to pursue planned closeout of the Cf-252 Loan Program. The work will be performed in phases. In the initial phase, users will be surveyed to determine whether they wish to take ownership of sources in their possession, or return them. In the second phase, sources will be recalled from non-DOE entities, and source ownership transfers will be performed. In the third phase, the remaining sources from DOE entities will be recalled. Initial funding of $350K is sought to fund the first phase, and to plan execution of the remaining phases given information collected from user surveys.

Closeout of Award #DE-FG02-CH11320. Final Technical Report: The project was effectively executed pursuant to the terms of the award.

The above grant was active at Michigan State University from 1994 until 2007. We summarize and document the various activities and key output under the grant, including degrees awarded to graduate students at MSU and through the VUBeam program sponsored by the grant, the books, publications and reports produced, the meetings organized, and the presentations given.

This report presents guidelines for Project Closeout. It is used to determine whether the Building America program is successfully facilitating improved design and practices to achieve energy savings goals in production homes. Its objective is to use energy simulations, targeted utility bill analysis, and feedback from project stakeholders to evaluate the performance of occupied BA communities.

The final report describes the study aimed at exploring the variable-resolution stretched-grid (SG) approach to decadal regional climate modeling using advanced numerical techniques. The obtained results have shown that variable-resolution SG-GCMs using stretched grids with fine resolution over the area(s) of interest, is a viable established approach to regional climate modeling. The developed SG-GCMs have been extensively used for regional climate experimentation. The SG-GCM simulations are aimed at studying the U.S. regional climate variability with an emphasis on studying anomalous summer climate events, the U.S. droughts and floods.

The following pages describe the high energy physics program at the University of Arizona which was funded by DOE grant DE-FG03-95ER40906, for the period 1 February 1995 to 31 January 2004. In this report, emphasis was placed on more recent accomplishments. This grant was divided into two tasks, a theory task (Task A) and an experimental task (Task B but called Task C early in the grant period) with separate budgets. Faculty supported by this grant, for at least part of this period, include, for the theory task, Adrian Patrascioiu (now deceased), Ina Sarcevic, and Douglas Toussaint., and, for the experimental task, Elliott Cheu, Geoffrey Forden, Kenneth Johns, John Rutherfoord, Michael Shupe, and Erich Varnes. Grant monitors from the Germantown DOE office, overseeing our grant, changed over the years. Dr. Marvin Gettner covered the first years and then he retired from the DOE. Dr. Patrick Rapp worked with us for just a few years and then left for a position at the University of Puerto Rico. Dr. Kathleen Turner took his place and continues as our grant monitor. The next section of this report covers the activities of the theory task (Task A) and the last section the activities of the experimental task (Task B).

We are conducting a collaborative research program on two tokamaks, HT-7 and EAST (Experimental Advanced Superconducting Tokamak, formerly HT-7U), with the Institute of Plasma Physics of the Chinese Academy of Sciences (CASIPP) located in Hefei, PRC. The work that we planned for this year included conducting transport experiments on HT-7, completing plans for expansion of the HT-7 diagnostic set, and reaching an agreement on how UT-FRC can best participate in experiments on HT-7U. These goals were accomplished as summarized in the next section. Note that the experimental portion of the work is still underway. The experimental campaign for HT-7 began just a few weeks before this report was compiled.

The report covers the 2003-04 contract period, with a retrospective of the 11 years for the contract, from 1993 to 2004. This includes personnel, technical publications and reports, plus research laboratories employed. Specific information is given in eight research areas, reporting on all technology developed and/or deployed by the University of Florida.

During the closeout session, members of the technical assistance team conveyed to the site how impressed they were at the thoroughness of the site's investigation and attempts at remediation. Team members were uniformly pleased at the skilled detection work to identify sources, make quick remediation decisions, and change course when a strategy did not work well. The technical assistance team also noted that, to their knowledge, this is the only DOE site at which a world-class scientist has had primary responsibility for the environmental restoration activities. This has undoubtedly contributed to the successes observed and DOE should take careful note. The following overall recommendations were agreed upon: (1) The site has done a phenomenal job of characterization and identifying and removing source terms. (2) Technologies selected to date are appropriate and high impact, e.g. collection trenches are an effective remedial strategy for this complicated geology. The site should continue using technology that is adapted to the site's unique geology, such as the collection trenches. (3) The site should develop a better way to determine the basis of cleanup for all sites. (4) The sentinel well system should be evaluated and modified, if needed, to assure that the sentinel wells provide coverage to the current site boundary. Potential modifications could include installation, abandonment or relocation of wells based on the large amount of data collected since the original sentinel well system was designed. (5) Modeling to assist in remedial design and communication should continue. (6) The site should develop a plan to ensure institutional memory. (7) The most likely possibility for improving closure to 2006 is by removing the residual source of the Old Town plume and establishing the efficacy of remediation for the 51/64 plume.

The Cast Metal Coalition, composed of more than 22 research providers and universities and 149 industrial partners, has completed a four-year research and development partnership with the Department of Energy. This report provides brief summaries of the 29 projects performed by the Coalition. These projects generated valuable information in such aspects of the metals industry as process prediction technologies, quality control, improved alloys, product machinability, and casting process improvements.

This documents the documentation that is required to be turned over to Operations with the Canister Cleaning System (CCS). The Acceptance for Beneficial Use will be updated as required prior to turnover. This document is prepared for the purposes of documenting an agreement among the various disciplines and organizations within the Spent Nuclear Fuel (SNF) Project as to what is required in terms of installed components of the CCS. This documentation will be used to achieve project closeout and turnover of ownership of the CCS to K Basins Operations.

The 300 Area has been divided into three operable units 300-FF-1, 300-FF-2, and 300-FF-5 all of which are in various stages of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) process. The 300-FF-1 Operable Unit, the subject of this report, includes liquid waste disposal sites, landfills, and a burial ground. This Remedial Design Report/Remedial Action Work Plan (RDR/RAWP) provides a summary description of each waste site included in the 300-FF-1 Operable Unit, the basis for remedial actions to be taken, and the remedial action approach and management process for implementing these actions. The remedial action approach and management sections provide a description of the remedial action process description, the project schedule, the project team, required planning documentation, the remedial action change process, the process for verifying attainment of the remedial action goals, and the required CERCLA and RCRA closeout documentation. Appendix A provides additional details on each waste site. In addition to remediation of the waste sites, waste generated during the remedial investigation/feasibility study portions of the project will also be disposed at the Environmental Restoration Disposal Facility (ERDF). Appendix B provides a summary of the modeling performed in the 300-FF-1 Phase 3 FS and a description of the modeling effort to be used to show attainment of the remedial action goals. Appendix C provides the sampling and analysis plan (SAP) for all sampling and field-screening activities performed during remediation and for verification of attainment with the remedial action goals. Appendix D provides the public involvement plan, prepared to ensure information is provided to the public during remedial design and remedial action processes.

Consistent with established Advanced Neutron Source (ANS) project policy for the use of probabilistic risk assessment (PRA) in design, a task has been established to use PRA techniques to help guide the design and safety analysis of the ANS cold sources. The work discussed in this report is the first formal output of the cold source PRA task. The major output at this stage is a list of design basis accidents, categorized into approximate frequency categories. This output is expected to focus attention on continued design work to define and optimize the design such that design basis accidents are better defined and have acceptable outcomes. Categorizing the design basis events (DBEs) into frequency categories should prove helpful because it will allow appropriate acceptance criteria to be applied. Because the design of the cold source is still proceeding, it is beyond the scope of this task to produce detailed event probability calculations or even, in some cases, detailed event sequence definitions. That work would take place as a logically planned follow-on task, to be completed as the design matures. Figure 1.1 illustrates the steps that would typically be followed in selecting design basis accidents with the help of PRA. Only those steps located above the dashed line on Fig. 1.1 are included in the scope of the present task. (Only an informal top-level failure modes and effects analysis was done.) With ANS project closeout expected in the near future, the scope of this task has been abbreviated somewhat beyond the state of available design information on the ANS cold sources, or what could be achieved in a reasonable time. This change was necessary to ensure completion before the closeout and because the in-depth analytical support necessary to define fully some of the accidents has already been curtailed.

Acceptance criteria for uranium check standards used to verify fluorimeter calibration have been developed. This work was done in response to Tiger Team finding QA/BMP-5, item 4. Data used as input to these calculations is retained in the Tiger Team closeout file, located in the Technical Service Division managers office. 3 refs., 4 tabs.

Documentation is provided in this report for the closeout of IE Bulletin 80-15 for nuclear power reactors. This bulletin pertained to a possible loss of the Emergency Notification System (ENS) upon loss of offsite power. Closeout is based on the implementation and verification of six (6) required actions by licensees of nuclear power reactors in operation or near to receiving an operating license when the bulletin was issued on June 18, 1980. Evaluation of utility responses and NRC/Region inspection reports indicates that the bulletin is closed for all of the 69 nuclear power reactors to which it was issued for action and which were not shut down indefinitely or permanently at the time of issuance of this report. Background information is supplied in the Introduction and Appendix A. Nuclear fuel facilities as well as nuclear power facilities were identified in the enclosures to the bulletin. However, per an NRC memorandum, the closeout of the bulletin for nuclear fuel facilities is not within the scope of this report.

Documentation is provided in this report for the closeout of IE Bulletin 79-17 and its revision on the safety-related subject of pipe cracks in stagnant borated water systems at operating plants with pressurized water reactors (PWRs). Closeout is based on the implementation and verification of actions required by the bulletin. Evaluation of utility responses and NRC/Region inspection reports indicates that the bulletin is closed for all of the 41 operating PWRs to which it was issued for action. It is concluded that the concerns of the bulletin have been resolved. Background information is supplied in the Introduction and Appendix A.

Documentation is provided in this report for the closeout of IE Bulletin 80-10 regarding contamination of nonradioactive systems resulting in the potential for unmonitored, uncontrolled release of radioactivity to the environment. Closeout is based on the documentation and verification of four actions required by the bulletin for holders of an operating license for a nuclear power facility at the time the bulletin was issued (05-06-80). The bulletin was issued for information to holders of a construction permit for a nuclear power facility. Evaluation of utility responses and NRC/Region inspection reports in accordance with the closeout criterion indicates that the bulletin is closed for 65 (98%) of the 66 nuclear power facilities to which it was issued for action. A follow-up item is proposed for the facility with open status, for the use of NRC regional inspectors in ensuring successful completion of required actions. When the bulletin is closed as anticipated for the facility which requires follow-up (see page C-1), the concerns of the bulletin will have been resolved completely. Background information is supplied in the Introduction and Appendix A.

This report demonstrates why a load-management agreement is the best rate format for customer thermal energy storage (TES) from electricity. The first section presents the basic operating and cost characteristics of TES systems as well as potential problems that affect rate setting. Then, the criteria for choosing a rate structure are put forth, and the various rate formats available are analyzed considering the above information. Finally, the means of achieving the maximum social benefits using a load-management agreement are explored.

Documentation is provided in this report for the closeout of IE Bulletin 79-03A, on the subject of faulty fusion welded austenitic stainless steel pipe (without filler metal) used or planned for use in safety-related systems. The investigation found that the bulletin has been closed administratively for all of the 121 facilities for which responses were required. The bulletin asked licensees for information only and did not include any requirement for corrective action. It is concluded that the concerns of the bulletin have been resolved at all except four facilities (two locations), and a recommendation is given for followup. This bulletin was issued by the NRC on April 4, 1980 as a followup to Bulletin 79-03 (closeout report NUREG/CR-5283). The purpose of the followup bulletin was to obtain further information about the impact of centerline lack of weld penetration (CLP) on the subject pipe. The NRC's concern was based on the finding from responses and investigations for initial Bulletin 79-03 that the ASME Code requirements for volumetric examination of piping were insufficient for detection of CLP. The problem with SA-312/A312 Type 300 Series fusion welded material was found to apply to all manufacturers, not just to the one mentioned in themore » initial bulletin.« less

Documentation is provided in this report for the closeout of IE Bulletin 86-02 regarding static O'' ring differential pressure switches Series 102 or 103 supplied by SOR, Incorporated, as electrical equipment important to safety. Closeout is based on the implementation and verification of either one or six actions required by the bulletin for holders of an operating license or a construction permit for a nuclear power plant. All six actions are required when the facility is equipped with the switches of concern in systems subject to limiting conditions for operations in technical specifications. Evaluation of utility responses and NRC/Region inspection reports in accordance with two criteria indicates that the bulletin is closed for 116 (97%) of the 119 nuclear power facilities to which it was issued for action. Followup items are proposed for the three (3) facilities with open status, for the use of NRC regional inspectors in ensuring successful completion of required and corrective actions. A conclusion based on the utility responses is presented.

Documentation is provided in this report for the closeout of IE Bulletin 83-06 regarding nonconformities of certain materials which were obtained directly or indirectly from the Tube-Line Corporation (T-L) for use in safety-related systems. Closeout is based on the implementation and verification of four (4) required actions by licensees and holders of construction permits of nuclear power reactor and nuclear fuel facilities. From evaluation of responses and NRC/Region inspection reports, it is concluded that the concerns of the bulletin have been resolved. The bulletin is closed for all of the 120 power reactor facilities and for both of the two nuclear fuel facilities to which it was issued for action. Background information is supplied in the Introduction and Appendix A. 3 refs., 5 tabs.

Documentation is provided in this report for the closeout of IE Bulletin 80-09 on the safety-related subject of ITT General Controls (ITT-GC) Hydramotor actuators models AH-90 and NH-90. The problems reported about inadequate springs and faulty sizing could affect the operation of safety-related equipment installed in nuclear power facilities. Closeout is based on the implementation and verification of actions required by this bulletin. It is concluded that the concerns of the bulletin have been resolved. Evaluation of utility responses and NRC/Region inspection reports indicates that the bulletin is closed for all of the 119 nuclear power reactor facilities in operation or under construction.