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DOE OSTI2012

The University of Virginia Experimental and Theoretical High Energy Physics Final Closeout Report

The work covered in this report includes a joint project on using gauge-gravity duality to discover qualitatively new results on jet quenching in strongly-coupled QCD-like plasmas. Other topics addressed by the theoretical work include jet stopping and energy loss in weakly-coupled plasmas, perturbative QCD amplitudes, AdS/CMT, dynamical electroweak symmetry breaking with a heavy fourth generation, electroweak-scale ν R model, vacuum topological structure and chiral dynamics in strongly coupled gauge theory. Effort committed to the CMS experiment is reported, particularly the management, maintenance, operation and upgrade of the CMS electromagnetic detector (ECAL). Activities in various physics analyses including Supersymmetry, Higgs, Top, and QCD analyses are reported. Physics projects covering wide areas of physics at the LHC are reported. CY2010 saw the accumulation of a data sample corresponding to approximately 36 pb -1 ; in CY 2011 the data sample swelled to more than 5 fb -1 . The UVa CMS analysis efforts are focused on this large 2011 data sample in a suite of crucial measurements and searches. KTeV physics activities are reported. Efforts are reported pertaining to several experiments, including: HyperCP, CKM, MIPP, D, NO νA, and Mu2e.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
DOE OSTI2012

Closure Report for Corrective Action Unit 547: Miscellaneous Contaminated Waste Sites, Nevada National Security Site, Nevada

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 547 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 547 consists of the following three Corrective Action Sites (CASs), located in Areas 2, 3, and 9 of the Nevada National Security Site: (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; AND (3) CAS 09-99-06, Gas Sampling Assembly Closure activities began in August 2011 and were completed in June 2012. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for CAU 547 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The recommended corrective action for the three CASs in CAU 547 was closure in place with administrative controls. The following closure activities were performed: (1) Open holes were filled with concrete; (2) Steel casings were placed over vertical expansion joints and filled with cement; (3) Engineered soil covers were constructed over piping and exposed sections of the gas sampling system components; (4) Fencing, monuments, Jersey barriers, radiological postings, and use restriction (UR) warning signs were installed around the perimeters of the sites; (5) Housekeeping debris was picked up from around the sites and disposed; and (6) Radiological surveys were performed to confirm final radiological postings. UR documentation is included in Appendix D. The post-closure plan was presented in detail in the CADD/CAP for CAU 547 and is included as Appendix F of this report. The requirements are summarized in Section 5.2 of this report. The proposed post-closure requirements consist of visual inspections to determine the condition of postings and radiological surveys to verify contamination has not migrated. NNSA/NSO requests the following: (1) A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 547; and (2) The transfer of CAU 547 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2012

Zero Emission Bay Area (ZEBA) Fuel Cell Bus Demonstration: Second Results Report

This report presents results of a demonstration of 12 new fuel cell electric buses (FCEB) operating in Oakland, California. The 12 FCEBs operate as a part of the Zero Emission Bay Area (ZEBA) Demonstration, which also includes two new hydrogen fueling stations. This effort is the largest FCEB demonstration in the United States and involves five participating transit agencies. The ZEBA partnersare collaborating with the U.S. Department of Energy (DOE) and DOE's National Renewable Energy Laboratory (NREL) to evaluate the buses in revenue service. The first results report was published in August 2011, describing operation of these new FCEBs from September 2010 through May 2011. New results in this report provide an update through April 2012.

08 HYDROGEN↗
DOE OSTI2012

Closure Report for Corrective Action Unit 548: Areas 9, 10, 18, 19, and 20 Housekeeping Sites, Nevada National Security Site, Nevada

This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 548, Areas 9, 10, 18, 19, and 20 Housekeeping Sites, and complies with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 548 consists of the following Corrective Action Sites (CASs), located in Areas 9, 10, 12, 18, 19, and 20 of the Nevada National Security Site: · CAS 09-99-02, Material Piles (2) · CAS 09-99-04, Wax, Paraffin · CAS 09-99-05, Asbestos, Vermiculite · CAS 09-99-07, Tar Spill · CAS 10-22-02, Drums · CAS 10-22-05, Gas Block · CAS 10-22-07, Gas Block · CAS 10-22-34, Drum · CAS 10-22-38, Drum; Cable · CAS 12-99-04, Epoxy Tar Spill · CAS 12-99-08, Cement Spill · CAS 18-14-01, Transformers (3) · CAS 19-22-01, Drums · CAS 19-22-11, Gas Block (2) · CAS 19-44-01, Fuel Spill · CAS 20-22-07, Drums (2) · CAS 20-22-09, Drums (3) · CAS 20-22-14, Drums (2) · CAS 20-22-16, Drums (2) · CAS 20-24-09, Battery Closure activities began in July 2011 and were completed in December 2011 and included removal and disposal of material piles, spills, sanitary debris, a lead acid battery, lead and steel shot, and stained soil. Activities were conducted according to the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2003). Closure activities generated sanitary waste, hydrocarbon waste, low-level waste, hazardous waste, and mixed waste. Some wastes exceeded land disposal limits and required offsite treatment prior to disposal. Other wastes met land disposal restrictions and were disposed in appropriate onsite or offsite landfills. NNSA/NSO requests the following: · A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 548 · The transfer of CAU 548 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2011

Characteristics of Range Hoods in California Homes -- Data Collected from a Real Estate Web Site

Venting range hoods are important residential ventilation components that remove pollutants generated by cooking activities and natural gas cooking burners. To address the lack of data on range hood installations in California, we conducted a survey by examining photographs of homes for sale or rent listed on a popular real estate web site. The survey was conducted in November 2010 and April–May 2011. Posted photos of the homes were reviewed to determine if a hood was installed, the type of hood, and two installation details that can impact performance, namely the height above the cooktop and the degree to which the hood covers the cooktop burners. We additionally collected information about the homes, including asking price for purchase or rent, type of building (e.g. detached house, townhouse or apartment), building age, floor area, and cooktop fuel type. Listings were first sampled to focus on homes built since 2005, then randomly sampled to include varied prices and locations around the state. Data were obtained for 1002 homes built between 1865 and 2011 (median year built 1989). Homes for sale varied in asking price from $\$$16,000 to $\$$16,500,000 (median $\$$353,000) and homes for rent varied from $\$$500 to $\$$25,000 (median $\$$2125) per month. Approximately 74% of the sample had natural gas cooktops. In this sample, natural gas cooktops were more prevalent in more expensive homes than in less expensive homes. Across the entire sample, 7.4 % appeared to have no hood installed, 33% had a short hood, 13% had a deep hood and 47% had a microwave over the range. The percentage of these hoods that vent to the outdoors could not be determined. Hood type was related to coverage of the cooktop. For deep hoods, 76% appeared to cover most or all of the cooktop burners. For short hoods, 70% covered about three quarters of the cooktop. And for microwaves the vast majority (96%) covered the back burners but not the front burners. Hood type was also correlated with asking price or monthly rent, with deep hoods most common in the most expensive homes. Hood type was also correlated with home age, with microwave hoods more common in newer homes. Installation height was related to device type with microwaves installed lower (closer) to the cooktop (median 18 inches), and short hoods (median 28 inches) and deep hoods (median 30 inches) installed higher. Deep range hoods are more common with natural gas cooktops than with electric cooktops, and slightly fewer homes with natural gas cooktops lack a range hood (7%) than homes with electric cooktops (9%). This study provides limited but useful information about the characteristics of range hoods in California homes and demonstrates the potential value of non-traditional forms of data collection.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2012

Pilot-Scale Removal of Fluoride from Legacy Plutonium Materials Using Vacuum Salt Distillation

Between September 2009 and January 2011, the Savannah River National Laboratory (SRNL) and HB-Line designed, developed, tested, and successfully deployed a system for the distillation of chloride salts. In 2011, SRNL adapted the technology for the removal of fluoride from fluoride-bearing salts. The method involved an in situ reaction between potassium hydroxide (KOH) and the fluoride salt to yield potassium fluoride (KF) and the corresponding oxide. The KF and excess KOH can be distilled below 1000°C using vacuum salt distillation (VSD). The apparatus for vacuum distillation contains a zone heated by a furnace and a zone actively cooled using either recirculated water or compressed air. During a vacuum distillation operation, a sample boat containing the feed material is placed into the apparatus while it is cool, and the system is sealed. The system is evacuated using a vacuum pump. Once a sufficient vacuum is attaned, heating begins. Volatile salts distill from the heated zone to the cooled zone where they condense, leaving behind the non-volatile material in the feed boat. Studies discussed in this report were performed involving the use of non-radioactive simulants in small-scale and pilot-scale systems as well as radioactive testing of a small-scale system with plutonium-bearing materials. Aspects of interest include removable liner design considerations, boat materials, in-line moisture absorption, and salt deposition.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2011

Proceedings of the Inaugural Meeting of the International Forum for Reactor Aging Management (IFRAM)

In almost all countries with nuclear power plants (NPPs), regulatory authorities and the nuclear industry are looking at some form of extended operating periods. To support life extension activities it is necessary to ensure the continued safety and reliability of system, structures, and components, and the component materials. Internationally, a variety of individual national and international activities have been initiated including Plant Life Management through the International Atomic Energy Agency, Electric Power Research Institute’s Long Term Operation program, and various national programs in managing materials degradation and related topics. The U.S. Nuclear Regulatory Commission (NRC) engaged the international community in workshops in 2005-2006 to identify research needs and to collect information in an expert panel report on Proactive Management of Materials Degradation (PMMD), which was reported in NUREG/CR-6923. These results are also available via an Information Tool on the internet at http://pmmd.pnl.gov. This information builds on the extensive compilations known as the GALL Report (Generic Aging Lessons Learned, NUREG-1801, Vols. 1 and 2). Pacific Northwest National Laboratory (PNNL) recently issued a report on the review of various international activities in PMMD (PNNL-17779). There have also been initiatives by Electricite de France, Tokyo Electric Power Company, EPRI, and others to establish a "Materials Aging Institute." Within the materials degradation research community there are also networks and technical meetings focused on some elements of PMMD. In spite of all these efforts, there is currently no forum to bring together these diverse activities and provide coordinated information exchange and prioritization of materials aging management/PMMD topics. It is believed that the International Forum for Reactor Aging Management (IFRAM) would be a good way to achieve this goal and help develop new approaches for ensuring continued safe operation in existing and future nuclear power plants. To begin addressing this need, NRC has established a Proactive Management of Materials Degradation Program for managing in-service degradation of metallic components in aging NPPs. The NRC is seeking to facilitate the establishment of IFRAM as a network of international experts who would exchange information on operating experience, best practices, and emerging knowledge. These experts would be willing to work jointly and leverage the separate efforts of existing national programs into a unified approach to enable the potential for the safe and economic life extension of NPPs. A proposal for establishing IFRAM was developed and presented at Engagement workshops in Seoul, Korea (October 2009) and Petten, The Netherlands (May 2010). Participants in both groups demonstrated strong interest in the establishment of IFRAM. Therefore the Global Steering Committee was formed to plan and carry out the start-up of IFRAM in 2011. This group finalized the documents for IFRAM and organized the kick-off meeting. This document records the contents of the inaugural meeting of IFRAM, which was held August 4-5, 2011, at the Cheyenne Mountain Resort in Colorado Springs, Colorado. Representatives from Asia, Europe, and the United States met to share information on reactor aging management and make plans for the future. Professor Tetsuo Shoji was elected chairperson of the Leadership Council. This kick-off event transformed the dream of an international forum into a reality. IFRAM has begun to achieve its mission.

Reactor Aging Management↗
DOE OSTI2012

Spreader Bar Radiation Detection Project Data Collection Report

A feasibility assessment of spreader-bar radiation detection (SBRD) systems was commissioned by NA-22 in the summer of 2009. To validate modeling results and allow performance to be based on actual measurements, a full-scale mockup of a SBRD system was built. The full-scale mockup consists of an actual spreader instrumented with 32 sodium iodide gamma detectors. Two sets of data collections were performed using the SBRD mockup. The first set measured the uniformity of radiation detection throughout the Inter-Modal Cargo Container (IMCC). The second set of data collections measured the response of the system to shielded sources. Plywood was used as the simulated cargo (shielding) material and sources were placed at varying depths within it. Both sets of data collections were performed using a forty-foot and a twenty-foot IMCC. In all, over 8700 spectra were collected during the October 2011 through December 2011 time period. This effort is a partnership between Sandia National Laboratories (SNL) and Pacific Northwest National Laboratory (PNNL). Sandia was responsible for design and construction of the SBRD mockup and collection of the data. PNNL was responsible for design of the data collection plan and analysis of the collected data.

Kallenbach, Gene Anthony↗
DOE OSTI2012

Winter and Breeding Bird Surveys at Los Alamos National Laboratory Progress Report for 2010 to 2012

Los Alamos National Security, LLC (LANS) biologists on the Resources Management Team at Los Alamos National Laboratory (LANL) initiated a multi-year monitoring program for migratory birds in Fiscal Year (FY) 2011 to implement the Biological Resources Management Plan and to comply with Federal laws, Executive Orders, and regulations related to migratory birds. The objective of this on-going study is to monitor patterns and trends of bird abundance and richness over time at LANL. LANS biologists completed a second year of surveys in the winter of 2011 and the summer of 2012. Four habitat types were surveyed for this project and they included 1) mixed conifer forest, 2) ponderosa pine forest, 3) pinyon-juniper woodland and 4) riparian/wetland. Transects were 2.0 to 2.5 kilometers (km) in length and contained nine survey points spaced approximately 250 meters (m) apart. Winter surveys took place in each of the four habitat types in December, January, and February. The summer breeding bird surveys were conducted in each of the four habitat types in May, June, and July.

Basic Biological Sciences(59)↗
DOE OSTI2012

Developing an Energy Performance Modeling Startup Kit

In 2011, the NAHB Research Center began the first part of the multi-year effort by assessing the needs and motivations of residential remodelers regarding energy performance remodeling. The scope is multifaceted - all perspectives will be sought related to remodeling firms ranging in size from small-scale, sole proprietor to national. This will allow the Research Center to gain a deeperunderstanding of the remodeling and energy retrofit business and the needs of contractors when offering energy upgrade services. To determine the gaps and the motivation for energy performance remodeling, the NAHB Research Center conducted (1) an initial series of focus groups with remodelers at the 2011 International Builders' Show, (2) a second series of focus groups with remodelers at theNAHB Research Center in conjunction with the NAHB Spring Board meeting in DC, and (3) quantitative market research with remodelers based on the findings from the focus groups. The goal was threefold, to: Understand the current remodeling industry and the role of energy efficiency; Identify the gaps and barriers to adding energy efficiency into remodeling; and Quantify and prioritize the supportneeds of professional remodelers to increase sales and projects involving improving home energy efficiency. This report outlines all three of these tasks with remodelers.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗
DOE OSTI2012

Advanced High-Temperature Reactor Dynamic System Model Development: April 2012 Status

The Advanced High-Temperature Reactor (AHTR) is a large-output fluoride-salt-cooled high-temperature reactor (FHR). An early-phase preconceptual design of a 1500 MW(e) power plant was developed in 2011 [Refs. 1 and 2]. An updated version of this plant is shown as Fig. 1. FHRs feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The AHTR is designed to be a “walk away” reactor that requires no action to prevent large off-site releases following even severe reactor accidents. This report describes the development of dynamic system models used to further the AHTR design toward that goal. These models predict system response during warmup, startup, normal operation, and limited off-normal operating conditions. Severe accidents that include a loss-of-fluid inventory are not currently modeled. The scope of the models is limited to the plant power system, including the reactor, the primary and intermediate heat transport systems, the power conversion system, and safety-related or auxiliary heat removal systems. The primary coolant system, the intermediate heat transport system and the reactor building structure surrounding them are shown in Fig. 2. These systems are modeled in the most detail because the passive interaction of the primary system with the surrounding structure and heat removal systems, and ultimately the environment, protects the reactor fuel and the vessel from damage during severe reactor transients. The reactor silo also plays an important role during system warmup. The dynamic system modeling tools predict system performance and response. The goal is to accurately predict temperatures and pressures within the primary, intermediate, and power conversion systems and to study the impacts of design changes on those responses. The models are design tools and are not intended to be used in reactor qualification. The important details to capture in the primary system relate to flows within the reactor vessel during severe events and the resulting temperature profiles (temperature and duration) for major components. Critical components include the fuel, reactor vessel, primary piping, and the primary-to-intermediate heat exchangers (P-IHXs). The major AHTR power system loops are shown in Fig. 3. The intermediate heat transfer system is a group of three pumped salt loops that transports the energy produced in the primary system to the power conversion system. Two dynamic system models are used to analyze the AHTR. A Matlab/Simulink-based model initiated in 2011 has been updated to reflect the evolving design parameters related to the heat flows associated with the reactor vessel. The Matlab model utilizes simplified flow assumptions within the vessel and incorporates an empirical representation of the Direct Reactor Auxiliary Cooling System (DRACS). A Dymola/Modelica model incorporates a more sophisticated representation of primary coolant flow and a physics-based representation of the three-loop DRACS thermal hydraulics. This model is not currently operating in a fully integrated mode. The Matlab model serves as a prototype and provides verification for the Dymola model, and its use will be phased out as the Dymola model nears completion. The heat exchangers in the system are sized using spreadsheet-based, steady-state calculations. The detail features of the heat exchangers are programmed into the dynamic models, and the overall dimensions are used to generate realistic plant designs. For the modeling cases where the emphasis is on understanding responses within the intermediate and primary systems, the power conversion system may be modeled as a simple boundary condition at the intermediate-to-power conversion system heat exchangers.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2012

Online Produced Water Treatment Catalog and Decision Tool

The objective of this project was to create an internet-based Water Treatment Technology Catalog and Decision Tool that will increase production, decrease costs and enhance environmental protection. This is to be accomplished by pairing an operator's water treatment cost and capacity needs to specific water treatments. This project cataloged existing and emerging produced water treatment technologies and allows operators to identify the most cost-effective approaches for managing their produced water. The tool captures the cost and capabilities of each technology and the disposal and beneficial use options for each region. The tool then takes location, chemical composition, and volumetric data for the operator's water and identifies the most cost effective treatment options for that water. Regulatory requirements or limitations for each location are also addressed. The Produced Water Treatment Catalog and Decision Tool efficiently matches industry decision makers in unconventional natural gas basins with: 1) appropriate and applicable water treatment technologies for their project, 2) relevant information on regulatory and legal issues that may impact the success of their project, and 3) potential beneficial use demands specific to their project area. To ensure the success of this project, it was segmented into seven tasks conducted in three phases over a three year period. The tasks were overseen by a Project Advisory Council (PAC) made up of stakeholders including state and federal agency representatives and industry representatives. ALL Consulting has made the catalog and decision tool available on the Internet for the final year of the project. The second quarter of the second budget period, work was halted based on the February 18, 2011 budget availability; however previous project deliverables were submitted on time and the deliverables for Task 6 and 7 were completed ahead of schedule. Thus the application and catalog were deployed to the public Internet. NETL did not provide additional funds and work on the project stopped on February 18, 2011. NETL ended the project on March 31, 2012.

03 NATURAL GAS↗
DOE OSTI2012

Fukushima Daiichi accident study: status as of April 2012

Japan suffered an immense tragedy as a result of the 2011 Tohuku earthquake and resulting tsunami that caused widespread damage to the infrastructure of the country and more than 20,000 deaths, most from the tsunami. The magnitude 9 (Mw)1 earthquake, centered roughly 20 miles deep and 43 miles east of Japan, took place at 14:46 (JST) on March 11, 2011, and produced catastrophic damage to buildings, roads, communications, and regional electrical power. Damage to the Sendai region was especially large owing to its proximity to the epicenter of the seismic event that produced a tsunami with an estimated height that exceeded 14 meters at the site of the Fukushima reactors. The earthquake at 14:46 JST resulted in a scram and a regional loss of electrical power, requiring the Fukushima Daiichi power plants (Units 1, 2, and 3) to start emergency on-site diesel powered generators to maintain cooling at the plants. Unit 4 was defueled at the time for maintenance, and Units 5 and 6 were in a state of cold shutdown for maintenance.

Gauntt, Randall O.↗
DOE OSTI2012

Iodine Sorbent Performance in FY 2012 Deep Bed Tests

Nuclear fission results in the production of fission products and activation products, some of which tend to be volatile during used fuel reprocessing and evolve in gaseous species into the reprocessing facility off-gas systems. Analyses have shown that I-129, due to its radioactivity, high potential mobility in the environment, and high longevity (half life of 15.7 million years), can require control efficiencies of up to 1,000x or higher to meet regulatory emission limits. Iodine capture is an important aspect of the Separations and Waste Forms Campaign Off-gas Sigma Team (Jubin 2011, Pantano 2011). Deep-bed iodine sorption tests for both silver-functionalized Aerogel and silver zeolite sorbents were performed during Fiscal Year 2012. These tests showed that: • Decontamination factors were achieved that exceed reasonably conservative estimates for DFs needed for used fuel reprocessing facilities in the U.S. to meet regulatory requirements for I-129 capture. • Silver utilizations approached or exceeded 100% for high inlet gas iodine concentrations, but test durations were not long enough to approach 100% silver utilization for lower iodine concentrations. • The depth of the mass transfer zone was determined for both low iodine concentrations (under 10 ppmv) and for higher iodine concentrations (between 10-50 ppmv); the depth increases over time as iodine is sorbed. • These sorbents capture iodine by chemisorption, where the sorbed iodine reacts with the silver to form very non-volatile AgI. Any sorbed iodine that is physisorbed but not chemically reacted with silver to form AgI might not be tightly held by the sorbent. The portion of sorbed iodine that tends to desorb because it is not chemisorbed (reacted to form AgI) is small, under 1%, for the AgZ tests, and even smaller, under 0.01%, for the silver-functionalized Aerogel.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2012

Independent Verification Survey Summary and Results for the Argonne National Laboratory Building 330 Project Footprint, Argonne, Illinois (Final Report)

ORISE conducted onsite verification activities of the Building 330 project footprint during the period of June 6 through June 7, 2011. The verification activities included technical reviews of project documents, visual inspections, radiation surface scans, and sampling and analysis. The draft verification report was issued in July 2011 with findings and recommendations. The contractor performed additional evaluations and remediation.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2012

Phase II Characterization Survey of the USNS Bridge (T-AOE 10), Military Sealift Fleet Support Command, Naval Station, Norfolk, Virginia (Final Report)

In March 2011, the USNS Bridge was deployed off northeastern Honshu, Japan with the carrier USS Ronald Reagan to assist with relief efforts after the 2011 Tōhoku earthquake and tsunami. During that time, the Bridge was exposed to air-borne radioactive materials leaking from the damaged Fukushima I Nuclear Power Plant. The proximity of the Bridge to the air-borne impacted area resulted in the contamination of the ship’s air-handling systems and the associated components, as well as potential contamination of other ship surfaces due to either direct intake/deposition or inadvertent spread from crew/operational activities. Preliminary surveys in the weeks after the event confirmed low-level contamination within the heating, ventilation, and air conditioning (HVAC) ductwork and systems, and engine and other auxiliary air intake systems. Some partial decontamination was performed at that time. In response to the airborne contamination event, Military Sealift Fleet Support Command (MSFSC) contracted Oak Ridge Associated Universities (ORAU), under provisions of the Oak Ridge Institute for Science and Education (ORISE) contract, to assess the radiological condition of the Bridge. Phase I identified contamination within the CPS filters, ventilation systems, miscellaneous equipment, and other suspect locations that could not accessed at that time (ORAU 2011b). Because the Bridge was underway during the characterization, all the potentially impacted systems/spaces could not be investigated. As a result, MSFSC contracted with ORAU to perform Phase II of the characterization, specifically to survey systems/spaces previously inaccessible. During Phase II of the characterization, the ship was in port to perform routine maintenance operations, allowing access to the previously inaccessible systems/spaces.

45 MILITARY TECHNOLOGY, WEAPONRY, AND NATIONAL DEF↗
DOE OSTI2013

Particles and Nuclei International Conference PANIC11 at MIT Young Scientist Support (Final Scientific/Technical Report)

The first Particles and Nuclei International Conference (PANIC11) in the LHC era brought 539 participants to the Massachusetts Institute of Technology from 24-29 July 2011. PANIC11 is the latest conference in a triennial series, which showcases recent progress worldwide in particle and nuclear physics. PANIC11 was held in the year celebrating the 150th anniversary of the founding of MIT as well as the centennial of Rutherford’s May 1911 seminal paper, which explained the discovery of the atomic nucleus. Further, 2011 was the 65th anniversary of MIT’s Laboratory for Nuclear Science, which hosted PANIC11. With strong support by the US Department of Energy, many national laboratories from around the world, industrial sponsors, and by MIT, the conference supported the extensive participation of young scientists, students and postdocs, who were the majority of participants, making for a very lively conference. Broad international participation was enhanced by IUPAP support for scientists from developing countries. The NSF supported video recording and broadcasting via an MIT public website of the plenary sessions, the public lectures, and the pre-conference pedagogical lectures, as well as outreach and participation of students from local high schools.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
DOE OSTI2013

Development of Genomic and Genetic Tools for Foxtail Millet, and Use of These Tools in the Improvement of Biomass Production for Bioenergy Crops-Transformation Technologies (Final Report)

Foxtail millet (Setaria italica L.) is a warm-season, C4 annual crop commonly grown for grain and forage worldwide. It has a relatively short generation time, yet produces hundreds of seeds per inflorescence. The crop is inbred and it has a small-size genome (~500 Mb). These features make foxtail millet an attractive grass model, especially for bioenergy crops. While a number of genomic tools have been established for foxtail millet, including a fully sequenced genome and molecular markers, the objectives of this project were to develop a tissue culture system, determine the best explant(s) for tissue culture, optimize transient gene expression, and establish a stable transformation system for foxtail millet cultivar Yugu1. In optimizing a tissue culture medium for the induction of calli and somatic embryos from immature inflorescences and mature seed explants, Murashige and Skoog medium containing 2.5 mg l-1 2,4-dichlorophenoxyacetic acid and 0.6 mg l-1 6- benzylaminopurine was determined to be optimal for callus induction of foxtail millet. The efficiency of callus induction from explants of immature inflorescences was significantly higher at 76% compared to that of callus induction from mature seed explants at 68%. The calli induced from this medium were regenerated into plants at high frequency (~100%) using 0.2 mg l-1 kinetin in the regeneration media. For performing transient gene expression, immature embryos were first isolated from inflorescences. Transient expression of the GUS reporter gene in immature embryos was significantly increased after sonication, a vacuum treatment, centrifugation and the addition of L-cysteine and dithiothreitol, which led to the efficiency of transient expression at levels greater than 70% after Agrobacterium inoculation. Inoculation with Agrobacterium was also tested with germinated seeds. The radicals of germinated seeds were pierced with needles and dipped into Agrobacterium solution. This method achieved a 10% transient expression efficiency. Throughout these analyses, using plasmids with the hygromycin selectable marker, it was determined that 1.5 mg l-1 hygromycin was the optimal dose for genetic transformation of foxtail millet. In contrast, the nptII selectable marker appeared to yield many escapes. Three methods of transformation were employed in an attempt to produce stable transformants. An in planta transformation experiment, similar to the floral dip method used in Arabidopsis, which utilized a red fluorescent protein pporRFP from coral Porites porites and the hygromycin selectable marker, was tested using immature inflorescences. Although several plants were PCR positive using endpoint and Real-Time PCR and there was transient expression using pporRFP and GUS reporters, no plants were positive on Southern blot. Dipping in Agrobacterium may damage the anther or the pistil because seed production was significantly reduced. Agrobacterium transformation using embryogenic calli was also tested. Although hundreds of plants were regenerated from selection, none were positive using PCR. The third method was to wound germinated seeds with an Agrobacterium coated needle, but none of the plants were PCR positive. Although the Yugu1 genotype was recalcitrant to genetic transformation, several avenues of future research should be considered for foxtail millet. Calli from different foxtail millet genotypes should be screened and selected for regeneration potential, and some genotypes may be more amenable to transformation. Additional selectable markers should also be tested as hygromycin appears to be too stringent and there are too many escapes with nptII. This project has provided training for the following personnel: Dr. Xinlu Chen (postdoc), Xiaomei Liu (postdoc), Jayashree Desai (postdoc) and Kyle Berk (Undergraduate researcher). Conference presentations and peer-reviewed journal articles partly supported by this grant includes the following: 1. Baxter H., Equi R., Chen X, Berk K. and Zale J. Establishing Efficient in vitro Protocols For Foxtail Millet (Setaria italica L. cv. Yugi 1). Plant & Animal Genomes XVIII Conference XVIII, San Diego, California, January 2010 2. Chen X, Zale J and Chen F. The Regeneration and Transformation of Foxtail Millet (Setaria italica), A Model Biofuel Crop. Genomic Science Awardee Meeting IX and USDA-DOE Plant Feedstock Genomics for Bioenergy Awardee Meeting, Crystal City, Virginia, April 2011 3. Chen, F., Tholl, D., Bohlmann, J., and Pichersky, E. (2011) The family of terpene synthases in plants: A mid-size family of genes for specialized metabolism that is highly diversified throughout the kingdom. Plant J. 66: 212-229.

59 BASIC BIOLOGICAL SCIENCES↗