Sample records for blanket certificate threshold

  1. ITER convertible blanket evaluation

    SciTech Connect (OSTI)

    Wong, C.P.C.; Cheng, E.

    1995-09-01T23:59:59.000Z

    Proposed International Thermonuclear Experimental Reactor (ITER) convertible blankets were reviewed. Key design difficulties were identified. A new particle filter concept is introduced and key performance parameters estimated. Results show that this particle filter concept can satisfy all of the convertible blanket design requirements except the generic issue of Be blanket lifetime. If the convertible blanket is an acceptable approach for ITER operation, this particle filter option should be a strong candidate.

  2. Materials for breeding blankets

    SciTech Connect (OSTI)

    Mattas, R.F.; Billone, M.C.

    1995-09-01T23:59:59.000Z

    There are several candidate concepts for tritium breeding blankets that make use of a number of special materials. These materials can be classified as Primary Blanket Materials, which have the greatest influence in determining the overall design and performance, and Secondary Blanket Materials, which have key functions in the operation of the blanket but are less important in establishing the overall design and performance. The issues associated with the blanket materials are specified and several examples of materials performance are given. Critical data needs are identified.

  3. Tritium breeding blanket

    SciTech Connect (OSTI)

    Smith, D.; Billone, M.; Gohar, Y. (Argonne National Lab., IL (USA)); Baker, C. (Oak Ridge National Lab., TN (USA)); Mori, S.; Kuroda, T.; Maki, K.; Takatsu, H.; Yoshida, H. (Japan Atomic Energy Research Inst., Tokyo (Japan)); Raffray, A. (California Univ., Los Angeles, CA (USA)); Sviatoslavsky, I. (Wisconsin Univ., Madison, WI (USA)); Simbolotti, G. (ENEA, Frascati (Italy). Centro Ricerche Energia); Dae

    1991-01-01T23:59:59.000Z

    The terms of reference for ITER provide for incorporation of a tritium breeding blanket with a breeding ratio as close to unity as practical. A breeding blanket is required to assure an adequate supply of tritium to meet the program objectives. Based on specified design criteria, a ceramic breeder concept with water coolant and an austenitic steel structure has been selected as the first option and lithium-lead blanket concept has been chosen as an alternate option. The first wall, blanket, and shield are integrated into a single unit with separate cooling systems. The design makes extensive use of beryllium to enhance the tritium breeding ratio. The design goals with a tritium breeding ratio of 0.8--0.9 have been achieved and the R D requirements to qualify the design have been identified. 4 refs., 8 figs., 2 tabs.

  4. ITER breeding blanket design

    SciTech Connect (OSTI)

    Gohar, Y.; Cardella, A.; Ioki, K.; Lousteau, D.; Mohri, K.; Raffray, R.; Zolti, E. [ITER Joint Central Team, Garching (Germany)] [and others

    1995-12-31T23:59:59.000Z

    A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase. It uses a ceramic breeder and water coolant for compatibility with the ITER machine design of the Basic Performance Phase. Lithium zirconate and lithium oxide am the selected ceramic breeders based on the current data base. Enriched lithium and beryllium neutron multiplier are used for both breeders. Both forms of beryllium material, blocks and pebbles are used at different blanket locations based on thermo-mechanical considerations and beryllium thickness requirements. Type 316LN austenitic steel is used as structural material similar to the shielding blanket. Design issues and required R&D data are identified during the development of the design.

  5. ITER blanket designs

    SciTech Connect (OSTI)

    Gohar, J.; Parker, R.; Rebut, P.H. [ITER Garching Joint Work Site, Garching bei Munchen (Germany)

    1994-12-31T23:59:59.000Z

    The ITER first wall, blanket, and shield system is being designed to handle 1.5{plus_minus}0.3 GW of fusion power and 3 MWa/m{sup 2} average neutron fluence. The reference shielding blanket (non breeding) uses austenitic steel structural material and water coolant with a copper first wall coated with beryllium. The first wall is protected by beryllium bumper limiters. The choice of copper first wall is dictated by the surface heat flux values anticipated during ITER operation. The water coolant is used at low pressure and low temperature. Liquid lithium is used as tritium breeder and coolant to alleviate issues of coolant breeder compatibility and reactivity. A layer of beryllium is incorporated in the blanket to improve the shielding performance and to insure tritium self-sufficiency. In addition, a shielding zone is incorporated at the back of the blanket to allow rewelding the vacuum vessel material during the ITER lifetime. The lithium coolant velocity required to remove the nuclear heating and the surface heat flux is 2 m/s, which produces a pressure drop of 0.6 MPa. Vanadium alloy (V-5Cr-5Ti) is being considered as the structural material because it can accommodate high heat loads and has good mechanical properties at high temperatures, high neutron fluence capability, low degradation under irradiation, good compatibility with liquid lithium, low decay heat, low waste disposal rating, and adequate strength to accommodate the electromagnetic loads during plasma disruption events.

  6. Certification of a weld produced by friction stir welding

    DOE Patents [OSTI]

    Obaditch, Chris; Grant, Glenn J

    2013-10-01T23:59:59.000Z

    Methods, devices, and systems for providing certification of friction stir welds are disclosed. A sensor is used to collect information related to a friction stir weld. Data from the sensor is compared to threshold values provided by an extrinsic standard setting organizations using a certification engine. The certification engine subsequently produces a report on the certification status of the weld.

  7. Construction Certifications

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Certifications Individual Permit: Construction Certifications Enhanced control measures were designed and installed at 67 Sites in 42 SMAs in 2012. Contact Environmental...

  8. Progress on DCLL Blanket Concept

    SciTech Connect (OSTI)

    Wong, Clement; Abdou, M.; Katoh, Yutai; Kurtz, Richard J.; Lumsdaine, A.; Marriott, Edward P.; Merrill, Brad; Morley, Neil; Pint, Bruce A.; Sawan, M.; Smolentsev, S.; Williams, Brian; Willms, Scott; Youssef, M.

    2013-09-01T23:59:59.000Z

    Under the US Fusion Nuclear Science and Technology Development program, we have selected the Dual Coolant Lead Lithium concept (DCLL) as a reference blanket, which has the potential to be a high performance DEMO blanket design with a projected thermal efficiency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. The self-cooled breeder PbLi is circulated for power conversion and for tritium breeding. A SiC-based flow channel insert (FCI) is used as a means for magnetohydrodynamic pressure drop reduction from the circulating liquid PbLi and as a thermal insulator to separate the high-temperature PbLi (~700°C) from the helium-cooled RAF/M steel structure. We are making progress on related R&D needs to address critical Fusion Nuclear Science and Facility (FNSF) and DEMO blanket development issues. When performing the function as the Interface Coordinator for the DCLL blanket concept, we had been developing the mechanical design and performing neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. We had estimated the necessary ancillary equipment that will be needed at the ITER site and a detailed safety impact report has been prepared. This provided additional understanding of the DCLL blanket concept in preparation for the FNSF and DEMO. This paper will be a summary report on the progress of the DCLL TBM design and R&Ds for the DCLL blanket concept.

  9. Fusion blanket design and optimization techniques.

    SciTech Connect (OSTI)

    Gohar, Y.

    2005-07-19T23:59:59.000Z

    In fusion reactors, the blanket design and its characteristics have a major impact on the reactor performance, size, and economics. The selection and arrangement of the blanket materials, dimensions of the different blanket zones, and different requirements of the selected materials for a satisfactory performance are the main parameters, which define the blanket performance. These parameters translate to a large number of variables and design constraints, which need to be simultaneously considered in the blanket design process. This represents a major design challenge because of the lack of a comprehensive design tool capable of considering all these variables to define the optimum blanket design and satisfying all the design constraints for the adopted figure of merit and the blanket design criteria. The blanket design techniques of the First Wall/Blanket/Shield Design and Optimization System (BSDOS) have been developed to overcome this difficulty and to provide the state-of-the-art techniques and tools for performing blanket design and analysis. This report describes some of the BSDOS techniques and demonstrates its use. In addition, the use of the optimization technique of the BSDOS can result in a significant blanket performance enhancement and cost saving for the reactor design under consideration. In this report, examples are presented, which utilize an earlier version of the ITER solid breeder blanket design and a high power density self-cooled lithium blanket design for demonstrating some of the BSDOS blanket design techniques.

  10. Ceramic Breeder Blanket for ARIES-CS

    SciTech Connect (OSTI)

    Raffray, A.R. [University of California-San Diego (United States); Malang, S. [Fusion Nuclear Technology Consulting (United States); El-Guebaly, L. [University of Wisconsin (United States); Wang, X. [University of California-San Diego (United States)

    2005-05-15T23:59:59.000Z

    This paper describes the conceptual design of a ceramic breeder blanket considered as one of the candidate blankets in the first phase of the ARIES-CS study. The blanket is coupled to a Brayton power cycle to avoid the safety concern associated with the possibility of Be/steam reaction in case of accident.

  11. Fusion reactor blanket-main design aspects

    SciTech Connect (OSTI)

    Strebkov, Yu.; Sidorov, A.; Danilov, I. [Research and Development Inst. of Power Engineering, Moscow (Russian Federation)

    1994-12-31T23:59:59.000Z

    The main function of the fusion reactor blanket is ensuring tritium breeding and radiation shield. The blanket version depends on the reactor type (experimental, DEMO, commercial) and its parameters. Blanket operation conditions are defined with the heat flux, neutron load/fluence, cyclic operation, dynamic heating/force loading, MHD effects etc. DEMO/commercial blanket design is distinguished e.g. by rather high heat load and neutron fluence - up to 100 W/cm{sup 2} and 7 MWa/m{sup 2} accordingly. This conditions impose specific requirements for the materials, structure, maintenance of the blanket and its most loaded components - FW and limiter. The liquid Li-Pb eutectic is one of the possible breeder for different kinds of blanket in view of its advantages one of which is the blanket convertibility that allow to have shielding blanket (borated water) or breeding one (Li-Pb eutectic). Using Li-Pb eutectic for both ITER and DEMO blankets have been considered. In the conceptual ITER design the solid eutectic blanket was carried out. The liquid eutectic breeder/coolant is suggested also for the advanced (high parameter) blanket.

  12. Quality Counts Certificate

    E-Print Network [OSTI]

    Chilek, Kevin

    2007-01-31T23:59:59.000Z

    This certificate accompanies the Quality Counts program. 1 page. It comes in packages of 25 certificates....

  13. Thermomechanical analysis of the ITER breeding blanket

    SciTech Connect (OSTI)

    Majumdar, S.; Gruhn, H. [Argonne National Lab., IL (United States); Gohar, Y.; Giegerich, M. [Max-Planck-Institut fuer Plasmaphysik, Muenchen (Germany). ITER Joint Central Team

    1997-03-01T23:59:59.000Z

    Thermomechanical performance of the ITER breeding blanket is an important design issue because it requires first, that the thermal expansion mismatch between the blanket structure and the blankets internals (such as, beryllium multiplier and tritium breeders) can be accommodated without creating high stresses, and second, that the thermomechanical deformation of various interfaces within the blanket does not create high resistance to heat flow and consequent unacceptably high temperatures in the blanket materials. Thermomechanical analysis of a single beryllium block sandwiched between two stainless steel plates was carried out using the finite element code ABAQUS to illustrate the importance of elastic deformation on the temperature distributions. Such an analysis for the whole ITER blanket needs to be conducted in the future. Uncertainties in the thermomechanical contact analysis can be reduced by bonding the beryllium blocks to the stainless steel plates by a thin soft interfacial layer.

  14. US solid breeder blanket design for ITER

    SciTech Connect (OSTI)

    Gohar, Y.; Attaya, H.; Billone, M.; Lin, C.; Johnson, C.; Majumdar, S.; Smith, D. (Argonne National Lab., IL (USA)); Goranson, P.; Nelson, B.; Williamson, D.; Baker, C. (Oak Ridge National Lab., TN (USA)); Raffray, A.; Badawi, A.; Gorbis, Z.; Ying, A.; Abdou, M. (California Univ., Los Angeles, CA (USA)); Sviatoslavsky, I.; Blanchard, J.; Mogahed, E.; Sawan, M.; Kulcinski, G. (Wisconsin Univ., Madison, WI (USA))

    1990-09-01T23:59:59.000Z

    The US blanket design activity has focused on the developments and the analyses of a solid breeder blanket concept for ITER. The main function of this blanket is to produce the necessary tritium required for the ITER operation and the test program. Safety, power reactor relevance, low tritium inventory, and design flexibility are the main reasons for the blanket selection. The blanket is designed to operate satisfactorily in the physics and the technology phases of ITER without the need for hardware changes. Mechanical simplicity, predictability, performance, minimum cost, and minimum R D requirements are the other criteria used to guide the design process. The design aspects of the blanket are summarized in this paper. 2 refs., 7 figs., 3 tabs.

  15. Fission reactor experiments for solid breeder blankets

    SciTech Connect (OSTI)

    Gierszewski, P.J.; Abdou, M.A.; Puigh, R.

    1986-11-01T23:59:59.000Z

    The testing needs for solid breeder blanket development are different from those for liquid breeder blankets. In particular, a reasonable number of moderate volume test sites in a neutron environment are needed. Existing fission reactors are shown to be able to provide this environment with reasonable simulation of many important blanket conditions. Three major additional fission reactor tests are identified beyond those presently underway. These are thermal behavior, advanced in-situ tritium recovery and nuclear submodule experiments.

  16. US Demo test blankets in ITER

    SciTech Connect (OSTI)

    Waganer, L.M.; Lee, V.D [McDonnell Douglas Aerospace, St. Louis, MO (United States); Abdou, M.A.; Ying, A.Y. [Univ. of California, Los Angeles, CA (United States); Hua, T.; Sze, D.K. [Argonne National Lab., IL (United States); Dagher, M.A. [Rockwell International Corp., Canoga Park, CA (United States)

    1996-12-31T23:59:59.000Z

    This paper summarizes the current status of the Demo blanket test systems and how the ITER reactor design and operations are being accommodated. The US blanket program is planning to develop a liquid metal breeder and a solid breeder blanket for testing and evaluation. The test blanket modules will have prototypical components, materials, and coolants representative of power reactor systems. The modules are to be located in the ITER horizontal test ports and installed/removed with special remote handling equipment. Adjacent ITER blanket neutronic and temperature conditions suggest the use of an isolation frame surrounding the test blanket modules or submodules. This frame will also provide additional shielding to protect the adjacent vacuum vessel. The frame and blanket module are attached to the surrounding backplate to transfer static and dynamic loads. All coolants and tritium-bearing fluids will be routed out of the midplane port to special heat exchangers and tritium separation systems. Special remote handling equipment is being designed to install and extract the test blanket modules. Dedicated transporters will be used to move the blanket and shielding modules to dedicated hot cells. Special facility areas will be provided immediately outside the port areas for the heat exchangers, pumps, and tritium-separation systems. 1 ref., 6 figs.

  17. Packed fluidized bed blanket for fusion reactor

    DOE Patents [OSTI]

    Chi, John W. H. (Mt. Lebanon, PA)

    1984-01-01T23:59:59.000Z

    A packed fluidized bed blanket for a fusion reactor providing for efficient radiation absorption for energy recovery, efficient neutron absorption for nuclear transformations, ease of blanket removal, processing and replacement, and on-line fueling/refueling. The blanket of the reactor contains a bed of stationary particles during reactor operation, cooled by a radial flow of coolant. During fueling/refueling, an axial flow is introduced into the bed in stages at various axial locations to fluidize the bed. When desired, the fluidization flow can be used to remove particles from the blanket.

  18. Status of fusion reactor blanket design

    SciTech Connect (OSTI)

    Smith, D.L.; Sze, D.K.

    1986-11-01T23:59:59.000Z

    This paper provides a brief review of the Blanket Comparison and Selection Study (BCSS)/sup 1/ and an overview of more recent fusion reactor blanket design efforts. Specific areas covered include improvements in leading blanket concepts identified in the BCSS, viz., self-cooled liquid metal concepts, helium-cooled solid breeder concepts, and helium-cooled liquid breeder concepts. In addition, a summary of innovative blanket concepts and design features is presented. The key features and critical issues associated with these designs are identified.

  19. Low technology high tritium breeding blanket concept

    SciTech Connect (OSTI)

    Gohar, Y.; Baker, C.C.; Smith, D.L.; Billone, M.C.; Cha, Y.S.; Clemmer, R.; Finn, P.A.; Hassanein, A.M.; Johnson, C.E.; Liu, Y.

    1987-10-01T23:59:59.000Z

    The main function of this low technology blanket is to produce the necessary tritium for INTOR operation with minimum first wall coverage. The INTOR first wall, blanket, and shield are constrained by the dimensions of the reference design and the protection criteria required for different reactor components and dose equivalent after shutdown in the reactor hall. It is assumed that the blanket operation at commercial power reactor conditions and the proper temperature for power generation can be sacrificed to achieve the highest possible tritium breeding ratio with minimum additional research and developments and minimal impact on reactor design and operation. A set of blanket evaluation criteria has been used to compare possible blanket concepts. Six areas: performance, operating requirements, impact on reactor design and operation, safety and environmental impact, technology assessment, and cost have been defined for the evaluation process. A water-cooled blanket was developed to operate with a low temperature and pressure. The developed blanket contains a 24 cm of beryllium and 6 cm of solid breeder both with a 0.8 density factor. This blanket provides a local tritium breeding ratio of approx.2.0. The water coolant is isolated from the breeder material by several zones which eliminates the tritium buildup in the water by permeation and reduces the changes for water-breeder interaction. This improves the safety and environmental aspects of the blanket and eliminates the costly process of the tritium recovery from the water. 12 refs., 13 tabs.

  20. BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE Especially Designed for Students of insurance. Your coverage is governed by a policy of student accident and sickness insurance underwritten

  1. BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE Especially Designed for International Students is governed by a policy of student accident and sickness insurance underwritten by BCS Insurance Company BCS

  2. Environmental Certification

    E-Print Network [OSTI]

    Environmental Compliance Inspector Certification 2009 Candidate Handbook This booklet contains... ° Subject matter for the Environmental Compliance Inspector tests ° Education and experience requirements Contents Environmental Compliance Inspector 2009 Candidate Handbook This handbook contains information

  3. Methods to enhance blanket power density

    SciTech Connect (OSTI)

    Hsu, P.Y.; Miller, L.G.; Bohn, T.S.; Deis, G.A.; Longhurst, G.R.; Masson, L.S.; Wessol, D.E.; Abdou, M.A.

    1982-06-01T23:59:59.000Z

    The overall objective of this task is to investigate the extent to which the power density in the FED/INTOR breeder blanket test modules can be enhanced by artificial means. Assuming a viable approach can be developed, it will allow advanced reactor blanket modules to be tested on FED/INTOR under representative conditions.

  4. Development of Solid Breeder Blanket at JAERI

    SciTech Connect (OSTI)

    Enoeda, Mikio; Hatano, Toshihisa; Tsuchiya, Kunihiko; Ochiai, Kentaro; Kawamura, Yoshinori; Hayashi, Kimio; Nishitani, Takeo; Nishi, Masataka; Akiba, Masato [Japan Atomic Energy Research Institute (Japan)

    2005-05-15T23:59:59.000Z

    Japan Atomic Energy Research Institute (JAERI) has been performing blanket development based on the long-term research program of fusion blankets in Japan, which was approved by the Fusion Council of Japan in 1999. The blanket development consists of out-pile R and D, In-pile R and D, TBM Neutronics and TPR Tests and Tritium Recovery System R and D. Based on the achievements of element technology development, the R and D program is now stepping to the engineering testing phase, in which scalable mockup tests will be performed for obtaining engineering data unique to the specific structure of the components, with the objective to define the fabrication specification of test blanket modules for ITER. This paper presents the major achievements of the element technology development of solid breeder blanket in JAERI.

  5. ARIES-IV Nested Shell Blanket Design

    SciTech Connect (OSTI)

    Wong, C.P.C.; Redler, K.; Reis, E.E.; Will, R. [General Atomics, San Diego, CA (United States); Cheng, E. [TSI Research, Inc. (United States); Hasan, C.M.; Sharafat, S. [California Univ., Los Angeles, CA (United States)

    1993-11-01T23:59:59.000Z

    The ARIES-IV Nested Shell Blanket (NSB) Design is an alternate blanket concept of the ARIES-IV low activation helium-cooled reactor design. The reference design has the coolant routed in the poloidal direction and the inlet and outlet plena are located at the top and bottom of the torus. The NSB design has the high velocity coolant routed in the toroidal direction and the plena are located behind the blanket. This is of significance since the selected structural material is SiC-composite. The NSB is designed to have key high performance components with characteristic dimensions of no larger than 2 m. These components can be brazed to form the blanket module. For the diverter design, we eliminated the use of W as the divertor coating material by relying on the successful development of the gaseous divertor concept. The neutronics and thermal-hydraulic performance of both blanket concepts are similar. The selected blanket and divertor configurations can also meet all the projected structural, neutronics and thermal-hydraulics design limits and requirements. With the selected blanket and divertor materials, the design has a level of safety assurance rate of I (LSA-1), which indicates an inherently safe design.

  6. A review of ITER blanket designs

    SciTech Connect (OSTI)

    Green, L.; Carelli, M.D.; Stefani, F. [Westinghouse Science & Technology Center, Pittsburgh, PA (United States); Morgan, G.D. [McDonnell Douglas Corp., St. Louis, MO (United States); Mattas, R. [Argonne National Lab., IL (United States)

    1994-11-01T23:59:59.000Z

    Changes in ITER requirements and conditions in the Engineering Design Activity (EDA), and the desire to obtain greater operating flexibility, led to a reconsideration of the ITER Conceptual Design Activity (CDA) blanket designs. The current strategy is to follow a two-tiered development approach: The reference design blanket is non-breeding, and satisfies only the basic performance phase (BPP) functional requirements. This blanket would need to be changed out for the extended performance (EPP). A lower level development effort is also underway on a tritium-breeding blanket. The decision as to which of the two designs to adopt will be made at the end of a two-year development effort. This paper describes the present candidate blankets and the issues associated with each of them. The reference design is a non-breeding, low temperature, low pressure, water cooled, austenitic stainless steel (316SS) blanket/shield (BS). The first wall (FW), which may be integral with or separate from the BS, is a bonded copper-alloy/SS structure with a beryllium coating. Critical issues here are copper-SS bonding, fabricability, and radiation damage and stress corrosion cracking of the SS. The breeding blanket utilizes vanadium alloy structural material, with lithium as the breeder. The coolants are either lithium (self-cooled) or high pressure helium. The primary issues here are the need to electrically insulate the flow channels, the qualification of vanadium as a structural material, and the fabrication of large vanadium structures.

  7. ADVANCED HIGH PERFORMANCE SOLID WALL BLANKET CONCEPTS

    SciTech Connect (OSTI)

    WONG, CPC; MALANG, S; NISHIO, S; RAFFRAY, R; SAGARA, S

    2002-04-01T23:59:59.000Z

    OAK A271 ADVANCED HIGH PERFORMANCE SOLID WALL BLANKET CONCEPTS. First wall and blanket (FW/blanket) design is a crucial element in the performance and acceptance of a fusion power plant. High temperature structural and breeding materials are needed for high thermal performance. A suitable combination of structural design with the selected materials is necessary for D-T fuel sufficiency. Whenever possible, low afterheat, low chemical reactivity and low activation materials are desired to achieve passive safety and minimize the amount of high-level waste. Of course the selected fusion FW/blanket design will have to match the operational scenarios of high performance plasma. The key characteristics of eight advanced high performance FW/blanket concepts are presented in this paper. Design configurations, performance characteristics, unique advantages and issues are summarized. All reviewed designs can satisfy most of the necessary design goals. For further development, in concert with the advancement in plasma control and scrape off layer physics, additional emphasis will be needed in the areas of first wall coating material selection, design of plasma stabilization coils, consideration of reactor startup and transient events. To validate the projected performance of the advanced FW/blanket concepts the critical element is the need for 14 MeV neutron irradiation facilities for the generation of necessary engineering design data and the prediction of FW/blanket components lifetime and availability.

  8. Blanket management method for liquid metal fast breeder reactors

    SciTech Connect (OSTI)

    Carelli, M.D.

    1986-04-22T23:59:59.000Z

    The method is described of moving blanket assemblies during refueling in a heterogeneous-type core for a liquid-metal-cooled fast-breeder nuclear reactor to improve the performance thereof. The core consists of fissile-material-containing fuel assemblies and fertile-material-containing blanket assemblies, the blanket assemblies including a plurality of inner blanket assemblies positioned in predetermined different locations within the interior of the core and radial blanket assemblies positioned proximate the periphery of the core.

  9. Multilayer insulation blanket, fabricating apparatus and method

    DOE Patents [OSTI]

    Gonczy, John D. (Oak Lawn, IL); Niemann, Ralph C. (Downers Grove, IL); Boroski, William N. (Aurora, IL)

    1992-01-01T23:59:59.000Z

    An improved multilayer insulation blanket for insulating cryogenic structures operating at very low temperatures is disclosed. An apparatus and method for fabricating the improved blanket are also disclosed. In the improved blanket, each successive layer of insulating material is greater in length and width than the preceding layer so as to accommodate thermal contraction of the layers closest to the cryogenic structure. The fabricating apparatus has a rotatable cylindrical mandrel having an outer surface of fixed radius that is substantially arcuate, preferably convex, in cross-section. The method of fabricating the improved blanket comprises (a) winding a continuous sheet of thermally reflective material around the circumference of the mandrel to form multiple layers, (b) binding the layers along two lines substantially parallel to the edges of the circumference of the mandrel, (c) cutting the layers along a line parallel to the axle of the mandrel, and (d) removing the bound layers from the mandrel.

  10. Method of fabricating a multilayer insulation blanket

    DOE Patents [OSTI]

    Gonczy, John D. (Oak Lawn, IL); Niemann, Ralph C. (Downers Grove, IL); Boroski, William N. (Aurora, IL)

    1993-01-01T23:59:59.000Z

    An improved multilayer insulation blanket for insulating cryogenic structures operating at very low temperatures is disclosed. An apparatus and method for fabricating the improved blanket are also disclosed. In the improved blanket, each successive layer of insulating material is greater in length and width than the preceding layer so as to accommodate thermal contraction of the layers closest to the cryogenic structure. The fabricating apparatus has a rotatable cylindrical mandrel having an outer surface of fixed radius that is substantially arcuate, preferably convex, in cross-section. The method of fabricating the improved blanket comprises (a) winding a continuous sheet of thermally reflective material around the circumference of the mandrel to form multiple layers, (b) binding the layers along two lines substantially parallel to the edges of the circumference of the mandrel, (c) cutting the layers along a line parallel to the axle of the mandrel, and (d) removing the bound layers from the mandrel.

  11. BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    BLANKET STUDENT ACCIDENT AND SICKNESS INSURANCE Especially Designed for the Dependents. It is not a contract of insurance. Your coverage is governed by a policy of student accident and sickness insurance

  12. Blanket design and optimization demonstrations of the first wall/blanket/shield design and optimization system (BSDOS).

    SciTech Connect (OSTI)

    Gohar, Y.; Nuclear Engineering Division

    2005-05-01T23:59:59.000Z

    In fusion reactors, the blanket design and its characteristics have a major impact on the reactor performance, size, and economics. The selection and arrangement of the blanket materials, dimensions of the different blanket zones, and different requirements of the selected materials for a satisfactory performance are the main parameters, which define the blanket performance. These parameters translate to a large number of variables and design constraints, which need to be simultaneously considered in the blanket design process. This represents a major design challenge because of the lack of a comprehensive design tool capable of considering all these variables to define the optimum blanket design and satisfying all the design constraints for the adopted figure of merit and the blanket design criteria. The blanket design capabilities of the First Wall/Blanket/Shield Design and Optimization System (BSDOS) have been developed to overcome this difficulty and to provide the state-of-the-art research and design tool for performing blanket design analyses. This paper describes some of the BSDOS capabilities and demonstrates its use. In addition, the use of the optimization capability of the BSDOS can result in a significant blanket performance enhancement and cost saving for the reactor design under consideration. In this paper, examples are presented, which utilize an earlier version of the ITER solid breeder blanket design and a high power density self-cooled lithium blanket design for demonstrating some of the BSDOS blanket design capabilities.

  13. Blanket Design and Optimization Demonstrations of the First Wall/Blanket/Shield Design and Optimization System (BSDOS)

    SciTech Connect (OSTI)

    Gohar, Yousry [Argonne National Laboratory (United States)

    2005-05-15T23:59:59.000Z

    In fusion reactors, the blanket design and its characteristics have a major impact on the reactor performance, size, and economics. The selection and arrangement of the blanket materials, dimensions of the different blanket zones, and different requirements of the selected materials for a satisfactory performance are the main parameters, which define the blanket performance. These parameters translate to a large number of variables and design constraints, which need to be simultaneously considered in the blanket design process. This represents a major design challenge because of the lack of a comprehensive design tool capable of considering all these variables to define the optimum blanket design and satisfying all the design constraints for the adopted figure of merit and the blanket design criteria. The blanket design capabilities of the First Wall/Blanket/Shield Design and Optimization System (BSDOS) have been developed to overcome this difficulty and to provide the state-of-the-art research and design tool for performing blanket design analyses. This paper describes some of the BSDOS capabilities and demonstrates its use. In addition, the use of the optimization capability of the BSDOS can result in a significant blanket performance enhancement and cost saving for the reactor design under consideration. In this paper, examples are presented, which utilize an earlier version of the ITER solid breeder blanket design and a high power density self-cooled lithium blanket design for demonstrating some of the BSDOS blanket design capabilities.

  14. Environmental Certificate Program

    E-Print Network [OSTI]

    Rose, Michael R.

    Environmental Management Certificate Program Accelerate Your Career Environmentaland Facilities of excellence. Environmental Management Certificate Program Compliance with regulatory requirements, remediation Irvine Extension's Certificate Program in Environmental Manage- ment prepares professionals at every

  15. Plan and Strategy for ITER Blanket Testing in Japan

    SciTech Connect (OSTI)

    Enoeda, Mikio [Japan Atomic Energy Research Institute (Japan); Akiba, Masato [Japan Atomic Energy Research Institute (Japan); Tanaka, Satoru [University of Tokyo (Japan); Shimizu, Akihiko [Kyushu University (Japan); Hasegawa, Akira [Tohoku University (Japan); Konishi, Satoshi [Kyoto University (Japan); Kimura, Akihiko [Kyoto University (Japan); Kohyama, Akira [Kyoto University (Japan); Sagara, Akio [National Institute of Fusion Science (Japan); Muroga, Takeo [National Institute of Fusion Science (Japan)

    2005-05-15T23:59:59.000Z

    The Fusion Council of Japan has established the long-term program for the development of blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan, while liquid breeder blankets and high temperature solid breeder blanket have been identified as the attractive advanced blanket. Japan Atomic Energy Research Institute (JAERI) is leading the development of solid breeder blankets, while, universities and National Institute for Fusion Science (NIFS) are developing the advanced blankets for potential options of the fusion power demonstration plant and commercial power plants. ITER blanket module testing is regarded as one of the most important milestones, by which integrity of candidate blanket design is qualified for the fusion power demonstration plant, together with material irradiation data by International Fusion Material Irradiation Facility (IFMIF). Japan is investigating the possibility of testing all types of blankets under TBWG framework with both of JAERI and universities/NIFS involvements. This paper presents a plan and strategy for the development of test blanket modules and ITER blanket module testing in Japan.

  16. The requirements for processing tritium recovered from liquid lithium blankets: The blanket interface

    SciTech Connect (OSTI)

    Clemmer, R.G.; Finn, P.A.; Greenwood, L.R.; Grimm, T.L.; Sze, D.K.; Bartlit, J.R.; Anderson, J.L.; Yoshida, H.; Naruse

    1988-03-01T23:59:59.000Z

    We have initiated a study to define a blanket processing mockup for Tritium Systems Test Assembly. Initial evaluation of the requirements of the blanket processing system have been started. The first step of the work is to define the condition of the gaseous tritium stream from the blanket tritium recovery system. This report summarizes this part of the work for one particular blanket concept, i.e., a self-cooled lithium blanket. The total gas throughput, the hydrogen to tritium ratio, the corrosive chemicals, and the radionuclides are defined. The key discoveries are: the throughput of the blanket gas stream (including the helium carrier gas) is about two orders of magnitude higher than the plasma exhaust stream;the protium to tritium ratio is about 1, the deuterium to tritium ratio is about 0.003;the corrosion chemicals are dominated by halides;the radionuclides are dominated by C-14, P-32, and S-35;their is high level of nitrogen contamination in the blanket stream. 77 refs., 6 figs., 13 tabs.

  17. Electromagnetically Restrained Lithium Blanket APEX Interim Report November, 1999

    E-Print Network [OSTI]

    California at Los Angeles, University of

    to avoid corrosion or fire. Lithium's high electrical conductivity may possibly permit efficient, compactElectromagnetically Restrained Lithium Blanket APEX Interim Report November, 1999 6-1 CHAPTER 6: ELECTROMAGNETICALLY RESTRAINED LITHIUM BLANKET Contributors Robert Woolley #12;Electromagnetically Restrained Lithium

  18. U. S. ITER shield and blanket design activities

    SciTech Connect (OSTI)

    Baker, C.C.

    1989-03-01T23:59:59.000Z

    This paper summarizes nuclear-related work in support of the U.S. effort for the Internatinoal Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid-breeder blanket, a helium-cooled, solid-breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He/sup 3/.

  19. armored blanket development: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    award of a blanket contract for the supply of encapsulated-winding dry-type power transformers CERN Preprints Summary: This document concerns the award of a blanket contract for...

  20. Assessment of Hypothermia Blankets Using an Advanced Thermal Manikin: Preprint

    SciTech Connect (OSTI)

    Rugh, J. P.; Barazanji, K.

    2009-07-01T23:59:59.000Z

    A thermal manikin developed at NREL helped to assess thermal blankets used to treat U.S. Army personnel suffering from hypothermia. The chemical blanket showed the best thermal performance.

  1. Evaluation of the parfait blanket concept for fast breeder reactors

    E-Print Network [OSTI]

    Ducat, Glenn Alexander

    1974-01-01T23:59:59.000Z

    An evaluation of the neutronic, thermal-hydraulic, mechanical and economic characteristics of fast breeder reactor configurations containing an internal blanket has been performed. This design, called the parfait blanket ...

  2. The economics of fuel depletion in fast breeder reactor blankets

    E-Print Network [OSTI]

    Brewer, Shelby Templeton

    1972-01-01T23:59:59.000Z

    A fast breeder reactor fuel depletion-economics model was developed and applied to a number of 1000 MWe UMBR case studies, involving radial blanket-radial reflector design, radial blanket fuel management, and sensitivity ...

  3. Neutronics Assessment of Blanket Options for the HAPL Laser Inertial Fusion Energy Chamber

    E-Print Network [OSTI]

    Raffray, A. René

    -cooled lithium blanket, a helium-cooled solid breeder blanket, and a dual-coolant lithium lead blanket of the reference blanket. Keywords-Laser fusion; lithium blanket; solid breeder; lithium lead; tritium breedingNeutronics Assessment of Blanket Options for the HAPL Laser Inertial Fusion Energy Chamber M

  4. 147 SDSU Curriculum Guide 2010 Certificate Programs

    E-Print Network [OSTI]

    Ponce, V. Miguel

    147 SDSU Curriculum Guide 2010 Certificate Programs Types of Certificate Programs General Guidelines for All Certificate Programs Academic Certificate Programs Professional Certificate programs Cosponsored Certificate Programs Other Certificates #12;148 SDSU Curriculum Guide 2010 University Guidelines

  5. Thermal resistance gaps for solid breeder blankets using packed beds

    SciTech Connect (OSTI)

    Gorbis, Z.R.; Raffray, A.R.; Tillack, M.S.; Abdou, M.A.

    1989-03-01T23:59:59.000Z

    The main design features of a new concept for solid breeder blanket thermal resistance gaps are described and analysis is shown for the blanket thermal characteristics. The effective thermal conductivity of a helium-beryllium packed bed configuration is studied, including the effect of a purge stream. Possible applications of this concept to ITER blanket designs are stressed.

  6. Experimental Studies of Active Temperature Control in Solid Breeder Blankets

    E-Print Network [OSTI]

    Tillack, Mark

    1 Experimental Studies of Active Temperature Control in Solid Breeder Blankets M. S. Tillack, A. R barrier regions for solid breeder blankets. In particular, particle beds have been studied because breeder blankets is thermomechanical behavior in the fusion environment. Stable and predictable

  7. Breeding Blanket Concepts for Fusion and Materials Requirements

    E-Print Network [OSTI]

    Raffray, A. René

    blanket design is described and key material issues discussed #12;5 Ceramic Breeder + Be and Ferritic1 Breeding Blanket Concepts for Fusion and Materials Requirements A. R. Raffray1, M. Akiba2, V-0417, USA 2Blanket Engineering Laboratory, JAERI, Naka-machi, Naka-gun, Ibaraki-ken, 311-0193 Japan 3ITER

  8. Use of gamma spectroscopy for neutronic analysis of LMFBR Blankets

    E-Print Network [OSTI]

    Kang, Ch?ang-sun

    It was the purpose of the present investigation to extend and apply Ge(Li) gamma-ray spectroscopy to the study of fast reactor blankets. The focal point for this research was the Blanket Test Facility at the MITR and Blanket ...

  9. Ceramic breeder blanket development for fusion experimental reactor in JAERI

    SciTech Connect (OSTI)

    Kurasawa, T.; Takatsu, H.; Sato, S. [JAERI, Ibaraki-ken (Japan)] [and others

    1994-12-31T23:59:59.000Z

    Ceramic breeding blanket is a promising breeding blanket concept for the fusion experimental reactor, and world-wide efforts have been devoted to the design and R&D. Irradiation damages of both of breeding materials and neutron multipliers are one of the critical issues for this type of blanket, and usage of these materials as a form of small pebbles has been proposed so as to accommodate expected irradiation damages without degradation of breeding capability. The present paper outlines the progress of the design of layered pebble bed breeding blanket and also shows preliminary results of concept development related to higher fusion power accommodation and convertible blanket.

  10. Water-cooled solid-breeder blanket concept for ITER

    SciTech Connect (OSTI)

    Gohar, Y.; Baker, C.C.; Attaya, H.; Billone, M.; Clemmer, R.C.; Finn, P.A.; Hassanein, A.; Johnson, C.E.; Majumdar, S.; Mattas, R.F.

    1989-03-01T23:59:59.000Z

    A water cooled solid-breeder blanket concept was developed for ITER. The main function of this blanket is to produce the necessary tritium for the ITER operation. Several design features are incorporated in this blanket concept to increase its attractiveness. The main features are the following: (a) a multilayer concept which reduces fabrication cost; (b) a simple blanket configuration which results in reliability advantages; (c) a very small breeder volume is employed to reduce the tritium inventory and the blanket cost; (d) a high tritium breeding ratio eliminates the need for an outside tritium supply; (e) a low-pressure system decreases the required steel fraction for structural purposes; (f) a low-temperature operation reduces the swelling concerns for beryllium; and (g) the small fractions of structure and breeder materials used in the blanket reduce the decay heat source. The key features and design analyses of this blanket are summarized in this paper.

  11. Thermal control of ceramic breeder blankets

    SciTech Connect (OSTI)

    Raffray, A.R.; Tillack, M.S.; Abdou, M.A. (Univ. of California, Los Angeles, CA (United States))

    1993-05-01T23:59:59.000Z

    Thermal control is an important issue for ceramic breeder blankets since the breeder needs to operate within its temperature window for the tritium release and inventory to be acceptable. A thermal control region is applicable not only to situations where the coolant can be run at low temperature, such as for the International Thermonuclear Experimental Reactor (ITER) base blanket, but also to ITER test module and power reactor situations, where it would allow for ceramic breeder operation over a wide range of power densities in space and time. Four thermal control mechanisms applicable to ceramic breeder blanket designs are described: A helium gap, a beryllium sintered block region, a beryllium sintered block region with a metallic felt at the beryllium-cladding interface, and a beryllium packed-bed region. Key advantages and issues associated with each of these mechanisms are discussed. Experimental and modeling studies focusing on beryllium packed-bed thermal conductivity and wall conductance, and beryllium sintered block-stainless steel cladding contact resistance are then described. Finally, an assessment of the potential of the different mechanisms for both passive and active control is carried out based on example calculations for a given set of ITER-like conditions. 28 refs., 33 figs., 3 tabs.

  12. Processing and waste disposal representative for fusion breeder blanket systems

    SciTech Connect (OSTI)

    Finn, P.A.; Vogler, S.

    1987-01-01T23:59:59.000Z

    This study is an evaluation of the waste handling concepts applicable to fusion breeder systems. Its goal is to determine if breeder blanket waste can be disposed of in shallow land burial, the least restrictive method under US Nuclear Regulatory regulations. The radionuclides expected in the materials used in fusion reactor blankets are described, as are plans for reprocessing and disposal of the components of different breeder blankets. An estimate of the operating costs involved in waste disposal is made.

  13. apt blanket system: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    for the supply of automation systems and fieldbus equipment CERN Preprints Summary: This document concerns the renewal of two blanket purchase contracts for the supply of...

  14. High power density self-cooled lithium-vanadium blanket.

    SciTech Connect (OSTI)

    Gohar, Y.; Majumdar, S.; Smith, D.

    1999-07-01T23:59:59.000Z

    A self-cooled lithium-vanadium blanket concept capable of operating with 2 MW/m{sup 2} surface heat flux and 10 MW/m{sup 2} neutron wall loading has been developed. The blanket has liquid lithium as the tritium breeder and the coolant to alleviate issues of coolant breeder compatibility and reactivity. Vanadium alloy (V-4Cr-4Ti) is used as the structural material because it can accommodate high heat loads. Also, it has good mechanical properties at high temperatures, high neutron fluence capability, low degradation under neutron irradiation, good compatibility with the blanket materials, low decay heat, low waste disposal rating, and adequate strength to accommodate the electromagnetic loads during plasma disruption events. Self-healing electrical insulator (CaO) is utilized to reduce the MHD pressure drop. A poloidal coolant flow with high velocity at the first wall is used to reduce the peak temperature of the vanadium structure and to accommodate high surface heat flux. The blanket has a simple blanket configuration and low coolant pressure to reduce the fabrication cost, to improve the blanket reliability, and to increase confidence in the blanket performance. Spectral shifter, moderator, and reflector are utilized to improve the blanket shielding capability and energy multiplication, and to reduce the radial blanket thickness. Natural lithium is used to avoid extra cost related to the lithium enrichment process.

  15. Innovative Liquid Breeder Blanket Design Activities in Japan

    SciTech Connect (OSTI)

    Sagara, Akio [National Institute for Fusion Science (Japan); Tanaka, Teruya [National Institute for Fusion Science (Japan); Muroga, Takeo [National Institute for Fusion Science (Japan); Hashizume, Hidetoshi [Tohoku University (Japan); Kunugi, Tomoaki [Kyoto University (Japan); Fukada, Satoshi [Kyushu University (Japan); Shimizu, Akihiko [Kyushu University (Japan)

    2005-04-15T23:59:59.000Z

    In order to clarify key engineering issues and to enhance key R and D activities for D-T fusion blankets, many design activities on innovative liquid blanket systems are on going as collaboration studies in Japan. Recently an improved long-life Flibe blanket has been proposed, and the self-cooled Li/V blanket design has started. For Flibe systems, much progress has been made on tritium permeation barrier, energy conversion system, free surface designs, and thermofluid loop experiments. For Li/V systems, evaluation studies have proceeded on Be-free nuclear properties and allowable crack fraction on multilayered MHD insulation coatings.

  16. Systematic methodology for estimating direct capital costs for blanket tritium processing systems

    SciTech Connect (OSTI)

    Finn, P.A.

    1985-01-01T23:59:59.000Z

    This paper describes the methodology developed for estimating the relative capital costs of blanket processing systems. The capital costs of the nine blanket concepts selected in the Blanket Comparison and Selection Study are presented and compared.

  17. Thermal control of solid breeder blankets

    SciTech Connect (OSTI)

    Raffray, A.R.; Ying, A.; Gorbis, Z.; Tillack, M.S.; Abdou, M.A.

    1991-12-31T23:59:59.000Z

    An assessment of the thermal control mechanisms applicable to solid breeder blanket designs under ITER-like operating conditions is presented in this paper. Four cases are considered: a helium gap; a sintered block Be region; a sintered block helium region with a metallic felt at the Be/clad interface; and a Be packed bed region. For these cases, typical operating are explored to determine the ranges of wall load which can be accommodated while maintaining the breeder within its allowable operating temperature window. The corresponding region thicknesses are calculated to help identify practicality and design tolerances.

  18. Thermal control of solid breeder blankets

    SciTech Connect (OSTI)

    Raffray, A.R.; Ying, A.; Gorbis, Z.; Tillack, M.S.; Abdou, M.A.

    1991-01-01T23:59:59.000Z

    An assessment of the thermal control mechanisms applicable to solid breeder blanket designs under ITER-like operating conditions is presented in this paper. Four cases are considered: a helium gap; a sintered block Be region; a sintered block helium region with a metallic felt at the Be/clad interface; and a Be packed bed region. For these cases, typical operating are explored to determine the ranges of wall load which can be accommodated while maintaining the breeder within its allowable operating temperature window. The corresponding region thicknesses are calculated to help identify practicality and design tolerances.

  19. An assessment of the base blanket for ITER

    SciTech Connect (OSTI)

    Raffray, A.R.; Abdou, M.A.; Ying, A.

    1991-01-01T23:59:59.000Z

    Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has many attractive features such as a tritium breeding ratio (TBR) of 0.8--0.9 and a reasonably low tritium inventory. However, some concerns regarding the risk, cost and benefit of the base blanket have been raised. These include uncertainties associated with the solid breeder thermal control and the potentially high cost of the amount of Be used to achieve high TBR and to provide the necessary thermal barrier between the high temperature solid breeder and low temperature coolant. This work addresses these concerns. The basis for the selection of a breeding blanket is first discussed in light of the incremental risk, cost and benefits relative to a non-breeding blanket. Key issues associated with the CDA breeding blanket configurations are then analyzed. Finally, alternative schemes that could enhance the attractiveness and flexibility of a breeding blanket are explored.

  20. An assessment of the base blanket for ITER

    SciTech Connect (OSTI)

    Raffray, A.R.; Abdou, M.A.; Ying, A.

    1991-12-31T23:59:59.000Z

    Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has many attractive features such as a tritium breeding ratio (TBR) of 0.8--0.9 and a reasonably low tritium inventory. However, some concerns regarding the risk, cost and benefit of the base blanket have been raised. These include uncertainties associated with the solid breeder thermal control and the potentially high cost of the amount of Be used to achieve high TBR and to provide the necessary thermal barrier between the high temperature solid breeder and low temperature coolant. This work addresses these concerns. The basis for the selection of a breeding blanket is first discussed in light of the incremental risk, cost and benefits relative to a non-breeding blanket. Key issues associated with the CDA breeding blanket configurations are then analyzed. Finally, alternative schemes that could enhance the attractiveness and flexibility of a breeding blanket are explored.

  1. PROGRESS ON DCLL BLANKET CONCEPT C.P.C. Wonga

    E-Print Network [OSTI]

    Abdou, Mohamed

    Lithium concept (DCLL) as a reference blanket, which has the potential to be a high performance DEMO and test blanket module (TBM) studies have identified the Dual Coolant Lead Lithium (DCLL) as the primary are limited to a maximum steel structure temperature of corrosion

  2. MHD Effects on Heat Transfer in a Molten Salt Blanket

    SciTech Connect (OSTI)

    Smolentsev, Sergey; Miraghaie, Reza; Abdou, Mohamed [University of California (United States)

    2005-04-15T23:59:59.000Z

    Heat transfer in closed channel flows of molten salts (MS)s, such as FLiBe or FLiNaBe, has been considered under specific reactor conditions. MHD effects have been accessed for two blanket concepts: self-cooled MS blanket, and dual-coolant MS blanket. The effect of heat transfer degradation due to turbulence reduction by a magnetic field in the First Wall channels of the self-cooled blanket was analyzed with the K-{epsilon} model of turbulence. In the dual-coolant blanket, the MS flow is laminar. A 2-D MHD code was used to calculate the laminar velocity profile first. Then, the temperature field was calculated using a 3-D temperature code. Reasonable interface temperatures below the material limit of 550 deg. C, and low heat escape from the breeder zone have been demonstrated. Model limitations and the ways of their improvement are also discussed.

  3. Building Operator Certification

    E-Print Network [OSTI]

    Lilley, D.

    2013-01-01T23:59:59.000Z

    Building Operator Certification Energy Efficiency through Operator Training CATEE December 18, 2013 – San Antonio, TX Dennis Lilley, CEM, PMP ESL-KT-13-12-49 CATEE 2013: Clean Air Through Energy Efficiency Conference, San Antonio, Texas Dec. 16...-18 Building Operator Certification Energy Efficiency through Operator Training What is Building Operator Certification? Industry-recognized credential in energy efficient building operation practices Created with 100 industry experts Launched in 1996 9...

  4. Certification Status Search Tool

    E-Print Network [OSTI]

    Certification Status Search Tool (SB/DVBE) Illustrated User Manual #12;2 Certification Status Search Tool (SB/DVBE) Rev. 5/14/09 Copyright © 2008 RFP Depot, LLC dba BidSync All Rights Reserved://www.bidsync.com #12;3 Certification Status Search Tool (SB/DVBE) Rev. 5/14/09 Introduction BidSync is a powerful e

  5. The Breeding Blanket Interface (BBI): Recent results for the solid breeder and the aqueous salt solution blanket concepts

    SciTech Connect (OSTI)

    Clemmer, R.G.; Finn, P.A.; Greenwood, L.R.; Sze, D.K.; Bartlit, J.R.; Sherman, R.; Anderson, J.L.; Yoshida, H.; Naruse, Y.; Enoeda, M.; Okuno, K. (Argonne National Lab., IL (USA); Los Alamos National Lab., NM (USA); Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))

    1989-10-01T23:59:59.000Z

    The Tritium Systems Test Assembly (TSTA) at Los Alamos is a full-scale facility dedicated to testing tritium processing for fusion reactors. We are involved in a study of adding a Breeder Blanket Interface (BBI) to the TSTA. The BBI is to test the processing required for the tritium output streams for the various fusion reactor breeder blankets. In the current phase of the study, we are evaluating the characteristics of the output from various breeding blankets types. Emphasis is placed on defining the output stream with respect to H/T ratio, impurity content, and radionuclide content. Reported herein is an assessment for two blanket concepts: solid breeder blanket (ceramic, Li{sub 2}O), and aqueous salt solution. 24 refs., 2 figs., 2 tabs.

  6. National Certification Standard

    Broader source: Energy.gov (indexed) [DOE]

    Certification Standard for the Geothermal Heat Pump Industry Principal Investigator John Kelly Geothermal Heat Pump Consortium GSHP Demonstration Projects May 18, 2010 This...

  7. U.S. technical report for the ITER blanket/shield: A. blanket: Topical report, July 1990--November 1990

    SciTech Connect (OSTI)

    Not Available

    1995-01-01T23:59:59.000Z

    Three solid-breeder water-cooled blanket concepts have been developed for ITER based on a multilayer configuration. The primary difference among the concepts is in the fabricated form of breeder and multiplier. All the concepts have beryllium for neutron multiplication and solid-breeder temperature control. The blanket design does not use helium gaps or insulator material to control the solid breeder temperature. Lithium oxide (Li{sub 2}O) and lithium zirconate (Li{sub 2}ZrO{sub 3}) are the primary and the backup breeder materials, respectively. The lithium-6 enrichment is 95%. The use of high lithium-6 enrichment reduces the solid breeder volume required in the blanket and consequently the total tritium inventory in the solid breeder material. Also, it increases the blanket capability to accommodate power variation. The multilayer blanket configuration can accommodate up to a factor of two change in the neutron wall loading without violating the different design guidelines. The blanket material forms are sintered products and packed bed of small pebbles. The first concept has a sintered product material (blocks) for both the beryllium multiplier and the solid breeder. The second concept, the common ITER blanket, uses a packed bed breeder and beryllium blocks. The last concept is similar to the first except for the first and the last beryllium zones. Two small layers of beryllium pebbles are located behind the first wall and the back of the last beryllium zone to reduce the total inventory of the beryllium material and to improve the blanket performance. The design philosophy adopted for the blanket is to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. Also, the reliability and the safety aspects of the blanket are enhanced by using low-pressure water coolant and the separation of the tritium purge flow from the coolant system by several barriers.

  8. An Identity and Certificate Manager

    E-Print Network [OSTI]

    Wu, Brian C

    2007-01-01T23:59:59.000Z

    We have designed and implemented a software library, called Identity and Certificate Manager (ICM), for managing, using, and exchanging application-level usernames, users' digital certificates, and cryptographic ...

  9. Neutronic assessment of He-cooled molten Li fusion blanket

    SciTech Connect (OSTI)

    Han, B. [Nuclear Engineering Dept., Seoul National Univ., San 56-1, Shinlim-dong, Kwanak-gu, Seoul (Korea, Republic of); Kim, Y. [Korea Atomic Energy Research Inst., 150, Deokjin-dong, Yuseong-gu, Daejeon (Korea, Republic of); Kim, C. H. [Nuclear Engineering Dept., Seoul National Univ., San 56-1, Shinlim-dong, Kwanak-gu, Seoul (Korea, Republic of)

    2006-07-01T23:59:59.000Z

    This study is intended to assess overall neutronic performances of He-cooled molten Li (HCML) blanket with a reflector and investigate the impact of {sup 6}Li enrichment on tritium breeding ratio (TBR). To precisely evaluate the neutronic performances of the reflected HCML blanket, three-dimensional D-shape torus model is utilized and Monte-Carlo calculations are performed. In this study, the neutronic characteristics of five potential reflector candidates are compared and the reflected blanket is also optimized from the neutronic point of view. Taking into account the material availability and potential safety features, a high-density graphite reflector can be a practical choice for a high-performance HCML blanket. The graphite-reflected HCML blanket shows the best performances when the reflector is placed such that the blanket is divided into a thick front region and a thin back region. The HCML blanket with a slightly-enriched Li (8-10 wt% {sup 6}Li) breeder shows the highest TBR. (authors)

  10. EU Blanket Design Activities and Neutronics Support Efforts

    SciTech Connect (OSTI)

    Fischer, U. [Forschungszentrum Karlsruhe (Germany); Batistoni, P. [ENEA Fusion Division (Italy); Boccaccini, L.V. [Forschungszentrum Karlsruhe (Germany); Giancarli, L. [CEA Saclay (France); Hermsmeyer, S. [Forschungszentrum Karlsruhe (Germany); Poitevin, Y. [CEA Saclay (France)

    2005-05-15T23:59:59.000Z

    An overview is provided of the design activities and the related neutronics support efforts conducted in the European Union for the development of breeder blankets for future fusion power reactors. The EU fusion programme considers two blanket lines, the Helium-Cooled Pebble Bed (HCPB) blanket with Lithium ceramics pebbles (Li{sub 4}SiO{sub 4} or Li{sub 2}TiO{sub 3}) as breeder and beryllium pebbles as neutron multiplier, and the Helium-Cooled Lithium-Lead (HCLL) blanket with the Pb-Li eutectic alloy as breeder and neutron multiplier. The blanket design and the related R and D efforts are based on the use of the same coolant and the same modular blanket structure to minimise the development costs as much as possible. The neutronic support efforts include design analyses for the layout and optimization of the modular HCPB/HCLL blankets based on detailed three-dimensional Monte Carlo calculations as well as underlying neutronics activities conducted in the frame of the European Fusion and Activation File (EFF/EAF) projects to develop qualified nuclear data and computational tools for reliable neutronics design calculations.

  11. Solid breeder blanket option for the ITER conceptual design

    SciTech Connect (OSTI)

    Gohar, Y.; Attaya, H.; Billone, M.C.; Finn, P.; Majumdar, S.; Turner, L.R.; Baker, C.C.; Nelson, B.E.; Raffray, R. (Argonne National Lab., IL (USA); Oak Ridge National Lab., TN (USA); California Univ., Los Angeles, CA (USA))

    1989-10-01T23:59:59.000Z

    A solid-breeder water-cooled blanket option was developed for ITER based on a multilayer configuration. The blanket uses beryllium for neutron multiplication and lithium oxide for tritium breeding. The material forms are sintered products for both material with 0.8 density factor. The lithium-6 enrichment is 90%. This blanket has the capability to accommodate a factor of two change in the neutron wall loading without violating the different design guidelines. The design philosophy adopted for the blanket is to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. At the same time, the reliability and the safety aspects of the blanket are enhanced by the use of a low-pressure coolant and the separation of the tritium purge lines from the coolant system. The blanket modules are made by hot vacuum forming and diffusion bonding a double wall structure with integral cooling channels. The different aspects of the blanket design including tritium breeding, nuclear heat deposition, activation analyses, thermal-hydraulics, tritium inventory, structural analyses, and water coolant conditions are summarized in this paper. 12 refs., 2 figs., 1 tab.

  12. Overview of EU activities on DEMO liquid metal breeder blanket

    SciTech Connect (OSTI)

    Giancarli, L.; Proust, E. [DRN/DMT/SERMA, Gif-sur-Yvette (France); Benamati, G. [CRE Brasimone, Camugnano (Italy)] [and others

    1994-12-31T23:59:59.000Z

    The European test-blanket development programme, started in 1988, is aiming at the selection by 1995 of two DEMO-relevant blanket lines to be tested in ITER. At present, four lines of blanket are under development, two of them using solid and the other two liquid breeder materials. As far as liquid breeders are concerned, two lines of blankets have been selected within the European Union, the water-cooled lithium-lead (the eutectic Pb-17Li) blankets and the dual-coolant Pb-17Li blankets. Designs have been developed considering an agreed set of DEMO specifications, such as, for instance, a fusion power of 2,200 MW, a neutron wall-loading of 2MW/m{sup 2}, a life-time of 20,000 hours, and the use of martensitic steel as a structural material. Moreover, an experimental program has been set up in order to address the main critical issues for each line. The present paper gives an overview of both design and experimental activities within the European Union concerning these two lines of liquid breeder blankets.

  13. Fusion Engineering and Design 81 (2006) 433441 An overview of US ITER test blanket module program

    E-Print Network [OSTI]

    Abdou, Mohamed

    2006-01-01T23:59:59.000Z

    blankets: (1) a helium-cooled solid breeder concept with ferritic steel structure and Be neutron multiplierLi liquid breeder blanket concepts in ITER are identified. © 2005 Elsevier B.V. All rights reserved. Keywords: ITER test blanket module program; Helium-cooled solid breeder blanket; Dual-coolant lead

  14. EFFECTIVE THERMAL CONDUCTIVITY OF LITHIUM CERAMIC PEBBLE BEDS FOR FUSION BLANKETS: A REVIEW

    E-Print Network [OSTI]

    Abdou, Mohamed

    a significant interest as solid breeders for the fusion blankets during the last three decades. The solid for the fusion solid breeder blankets. In order to study the heat transfer in the blanket, effective conductivityEFFECTIVE THERMAL CONDUCTIVITY OF LITHIUM CERAMIC PEBBLE BEDS FOR FUSION BLANKETS: A REVIEW A. ABOU

  15. Export Compliance Certificate Program

    E-Print Network [OSTI]

    Barrett, Jeffrey A.

    Export Compliance Certificate Program Accelerate Your Career BusinessandManagement extension.uci.edu/export bearing the UC seal signifies a well- known, uncompromising standard of academic excellence. #12;Export Compliance Certificate Program The importance of understanding export controls and how to develop

  16. Business Analyst Certificate Program

    E-Print Network [OSTI]

    Rose, Michael R.

    Business Analyst Certificate Program BusinessandManagement extension.uci.edu/ba #12;Business Analyst Certificate Program Business Analysts Capture Requirements to Build What the Customer Wants. The Business Analyst serves as the key liaison between the client, stakeholders, and the solutions team

  17. Graduate Certificate in Transportation

    E-Print Network [OSTI]

    Bertini, Robert L.

    Graduate Certificate in Transportation Nohad A. Toulan School of Urban Studies and Planning of Engineering and Computer Science integrated transportation systems. The Graduate Certificate in Transportation their capabilities. Students in the program can choose among a wide range of relevant courses in transportation

  18. Scandinavian Studies Certificate

    E-Print Network [OSTI]

    Saldin, Dilano

    , green energy, sustainability, and information technology. To complete the certificate, students must, and Sweden. Certificate programs are similar to minors. They are comprised of 15 to 26 credits University, UWM's sister university in Sweden. Students attending Malardalen University pay UWM tuition

  19. ORACLE CERTIFICATION Oracle Database

    E-Print Network [OSTI]

    Loudon, Catherine

    ORACLE CERTIFICATION Oracle Database Administration Certificate Program Train with the best. Get your Oracle Database Administration education from the number-one provider* of Oracle training-on, lab-based understanding of Oracle, the world's leading database platform, and long the product

  20. IBM Certification White Paper

    E-Print Network [OSTI]

    surrounding IT certification vary depending on geography, company strategy and the product it supports by individuals and the companies that employ them as a differentiator in the IT Industry. As competition, certification offers several other advantages for both individuals and companies including: · Increased income

  1. A Solid breeder tokamak blanket designed for failure mode operation

    E-Print Network [OSTI]

    Chen, Franklin Fun Kun

    1977-01-01T23:59:59.000Z

    The objective of this study was to evaluate a new concept for a Tokamak type fusion reactor blanket. The design was based on using a packed bed of lithium aluminate as the breeding material with helium gas cooling. The ...

  2. Helium-cooled lithiuim compound suspension blanket concept for ITER

    SciTech Connect (OSTI)

    Gohar, Y.; Baker, C.C.; Attaya, H.; Billone, M.; Clemmer, R.C.; Finn, P.A.; Hassanein, A.; Johnson, C.E.; Majumdar, S.; Mattas, R.F.

    1988-08-01T23:59:59.000Z

    This blanket concept uses a dilute suspension of fine solid breeder particles (Li/sub 2/O, LiAlO/sub 2/, or Li/sub 4/SiO/sub 4/) in a carrier gas (He) as the coolant and the tritium breeding stream. A small fraction of this stream is processed outside the reactor for tritium recovery. The blanket consists of a beryllium multiplier and carbon/steel reflector. A steel clad is used for all materials. A carbon reflector is employed to reduce the beryllium thickness used in the blanket for a specific tritium breeding ratio. The breeder particle size has to exceed few microns (greater than or equal to2 microns) to avoid sticking problems on the cold surfaces of the heat exchanger. The helium gas pressure is in the range of 2 to 3 MPa to carry the blanket and the heat exchanger loop. The solid breeder concentration in the helium stream is 1 to 5 volume percent. A high lithium-6 enrichment is used to produce a high tritium breeding ratio and to reduce the breeder concentration in the helium gas. At a lithium-6 enrichment of 90%, the local tritium breeding ratio is 2.03 based on a one-dimensional poloidal model. The total thickness of the helium stream is only 4 cm out of the 50 cm total blanket thickness. The blanket uses a 35 cm of beryllium for neutron multiplication. A simple multi-layer design is employed where the blanket sector has the helium coolant flowing in the poloidal direction. The blanket concept has several unique advantages which are very beneficial for fusion reactors including ITER. 10 refs., 2 tabs.

  3. Evaluation of organic moderator/coolants for fusion breeder blankets

    SciTech Connect (OSTI)

    Romero, J.B.

    1980-03-01T23:59:59.000Z

    Organic coolants have several attractive features for fusion breeder blanket design. Their apparent compatibility with lithium and their ideal physical and nuclear properties allows straight-forward, high performance designs. Radiolytic damage can be reduced to about the same order as comparable fission systems by using multiplier/stripper blanket designs. Tritium recovery from the organic should be straightforward, but additional data is needed to make a better assessment of the economics of the process.

  4. U.S. Plans and Strategy for ITER Blanket Testing

    SciTech Connect (OSTI)

    Abdou, M. [UCLA Fusion Engineering Sciences (United States); Sze, D. [UCSD Advanced Energy Technology Group (United States); Wong, C. [General Atomics (United States); Sawan, M. [University of Wisconsin Fusion Technology Institute, Madison (United States); Ying, A. [UCLA Fusion Engineering Sciences (United States); Morley, N.B. [UCLA Fusion Engineering Sciences (United States); Malang, S

    2005-04-15T23:59:59.000Z

    Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER from Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation in the ITER Test Blanket Module (TBM) Program. A US strategy for ITER-TBM has evolved that emphasizes international collaboration. A study was initiated to select the two blanket options for the US ITER-TBM in light of new R and D results from the US and world programs over the past decade. The study is led by the Plasma Chamber community in partnership with the Materials, PFC, Safety, and physics communities. The study focuses on assessment of the critical feasibility issues for candidate blanket concepts and it is strongly coupled to R and D of modeling and experiments. Examples of issues are MHD insulators, SiC insert viability and compatibility with PbLi, tritium permeation, MHD effects on heat transfer, solid breeder 'temperature window' and thermomechanics, and chemistry control of molten salts. A dual coolant liquid breeder and a helium-cooled solid breeder blanket concept have been selected for the US ITER-TBM.

  5. APT Blanket System Loss-of-Helium-Gas Accident Based on Initial Conceptual Design - Helium Supply Rupture into Blanket Module

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    The model results are used to determine if beam power shutdown is necessary (or not) as a result of the LOHGA accident to maintain the blanket system well below any of the thermal-hydraulic constraints imposed on the design. The results also provide boundary conditions to the detailed bin model to study the detailed temperature response of the hot blanket module structure. The results for these two cases are documented in the report.

  6. 401 Certification (Vermont)

    Broader source: Energy.gov [DOE]

    A 401 Certification is required for any project that triggers a federal permit or license. Examples include licenses from the Nuclear Regulatory Commission and any project which requires a permit...

  7. SHIELD certification package

    SciTech Connect (OSTI)

    Boman, C.

    1992-02-01T23:59:59.000Z

    Certification as applied to existing computer codes includes the verification and validation process, placing the code in configuration control, establishing user qualification standards and training requirements. All software intended for use in critical calculations must be certified. This report is intended to fulfill the requirements for the certification of the SHIELD, SHLDED, GEDIT, GENPRT, FIPROD, FPCALC, and PROCES modules of the SHIELD system built February, 1992, by W.S. Parks. These modules are used for burnup, cooling, separate, and edit calculations.

  8. certification, compliance and enforcement regulations for Commercial...

    Office of Environmental Management (EM)

    certification, compliance and enforcement regulations for Commercial Refrigeration Equipment (CRE) certification, compliance and enforcement regulations for Commercial...

  9. Overview of design activities for Li/V blankets

    SciTech Connect (OSTI)

    Sze, D.K.; Mattas, R.F.

    1997-12-31T23:59:59.000Z

    Recent fusion power plant design studies in the US have been conducted within the ARIES project. The most recent design of Li/V blankets was conducted as part of the ARIES-RS design. The ARIES-RS fusion power plant design study is based on reversed-shear (RS) physics with a Li/V (lithium breeder and vanadium structure) blanket. The reversed-shear discharge has been documented in many large tokamak experiments. The plasma in the RS mode has a high beta, low current, and low current drive requirement. Therefore, it is an attractive physics regime for a fusion power plant. The blanket system based on a Li/V has high temperature operating capability, good tritium breeding, excellent high heat flux removal capability, long structural life time, low activation, low after heat and good safety characteristics. For these reasons, the ARIES-RS reactor study selected Li/V as the reference blanket. The combination of attractive physics and attractive blanket engineering is expected to result in a superior power plant design.

  10. Neutronics Analysis of a Molten Salt Blanket for the HAPL Laser Fusion Power Plant with Magnetic

    E-Print Network [OSTI]

    Raffray, A. René

    of this blanket were compared to those of a lithium-lead blanket in two chamber core configurations. Because chemistry control of the corrosive TF and F2. In order to compare the performance parameters, we carried out

  11. Electric Blanket Delivers K.O. to Space Heater During #EnergyFaceoff...

    Office of Environmental Management (EM)

    Electric Blanket Delivers K.O. to Space Heater During EnergyFaceoff Round Three Electric Blanket Delivers K.O. to Space Heater During EnergyFaceoff Round Three November 19, 2014...

  12. Neutronics design aspects of reference ARIES-I fusion blanket

    SciTech Connect (OSTI)

    Cheng, E.T. (TSI Research, Solana Beach, CA (USA))

    1990-12-01T23:59:59.000Z

    A SiC composite blanket concept was recently conceived for a deuterium-tritium burning, 1000 MW(e) tokamak fusion reactor design, ARIES-I. SiC composite structural material was chosen due to its very low activation features. High blanket nuclear performance and thermal efficiency, adequate tritium breeding, and a low level of activation are important design requirements for the ARIES-I reactor. The major approaches, other than using SiC as structural material, in meeting these design requirements, are to employ beryllium, the only low activation neutron multiplying material, and isotopically tailored Li{sub 2}ZrO{sub 3}, a tritium breeding material stable at high temperature, as blanket materials. 5 refs., 4 figs., 2 tabs.

  13. Progress in blanket designs using SiCf/SiC composites L. Giancarli a,

    E-Print Network [OSTI]

    Raffray, A. René

    Progress in blanket designs using SiCf/SiC composites L. Giancarli a, 1, H. Golfier b , S. Nishio c the use of SiCf/SiC composite as structural material for fusion power reactor breeding blanket. SeveralCf/SiC. # 2002 Published by Elsevier Science B.V. Keywords: Blanket designs; SiCf/SiC composites; Self

  14. MODELING TRITIUM TRANSPORT IN PBLI BREEDER BLANKETS UNDER STEADY STATE , M. Abdou1

    E-Print Network [OSTI]

    Abdou, Mohamed

    MODELING TRITIUM TRANSPORT IN PBLI BREEDER BLANKETS UNDER STEADY STATE H. Zhang1 , A. Ying1 , M breeder blankets under realistic reactor-like conditions in this paper. Tritium concentration. Tritium behavior in the liquid metal breeder blanket requires a thorough understanding of the sequence

  15. Fusion Engineering and Design 81 (2006) 659664 Solid breeder test blanket module design and analysis

    E-Print Network [OSTI]

    Abdou, Mohamed

    2006-01-01T23:59:59.000Z

    Fusion Engineering and Design 81 (2006) 659­664 Solid breeder test blanket module design This paper presents the design and analysis for the US ITER solid breeder blanket test articles. Objectives of solid breeder blanket testing during the first phase of the ITER operation focus on exploration

  16. Blanket/First Wall Challenges and Required R&D on the pathway to DEMO

    E-Print Network [OSTI]

    Abdou, Mohamed

    Ceramic Breeder Blanket Technology." · J. Van Lew et al, "Discrete element method simulations to determineBlanket/First Wall Challenges and Required R&D on the pathway to DEMO ISFNT11 Invited paper and Technology Center, UCLA Barceloneta, Barcelona #12;Introductory Remarks 2 · The importance of blanket

  17. Fusion Engineering and Design 46 (1999) 177183 ITER reference breeding blanket design

    E-Print Network [OSTI]

    Raffray, A. René

    1999-01-01T23:59:59.000Z

    breeding blanket with a lithium ceramic as breeder material and beryllium as neutron multiplierFusion Engineering and Design 46 (1999) 177­183 ITER reference breeding blanket design M. Ferrari a The ITER reference breeding blanket design is water-cooled and is characterised by the use of the neutronic

  18. Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials

    E-Print Network [OSTI]

    Abdou, Mohamed

    Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials, Russian Federation Abstract Within the framework of the ITER Test Blanket Working Group, the ITER Parties have made several proposals for test blanket modules to be tested in ITER from the first day of H

  19. Modular Dual Coolant Pb-17Li Blanket Design For ARIES-CS Compact Stellarator Power Plant

    E-Print Network [OSTI]

    Raffray, A. René

    of the study. The preferred blanket concept is a dual coolant blanket with a He- cooled ferritic steel firstModular Dual Coolant Pb-17Li Blanket Design For ARIES-CS Compact Stellarator Power Plant X.R. Wanga from the engineering effort during the second phase of ARIES-CS study on the conceptual design

  20. Liquid Walls Innovative Concepts for First Walls and Blankets

    E-Print Network [OSTI]

    Abdou, Mohamed

    with existing technology · Size of plasma devices and power plants can be substantially reduced High PoloidalLiquid Walls Innovative Concepts for First Walls and Blankets Mohamed Abdou Professor, Mechanical as part of the US Restructured Fusion Program Strategy to enhance innovation · Natural Questions

  1. Accelerator driven production of tritium: target and blanket design 

    E-Print Network [OSTI]

    Ragusa, Jean Concetto

    1996-01-01T23:59:59.000Z

    investigated. The target designs in the heterogeneous systems were 1 / liquid lead, and 2/ layers of solid lead plates cooled by heavy water. The tritium breeding blanket assemblies contained either lithium oxide or molten fluorine salt with or without UF4...

  2. Fusion-reactor blanket-material safety-compatibility studies

    SciTech Connect (OSTI)

    Jeppson, D.W.; Muhlestein, L.D.; Keough, R.F.; Cohen, S.

    1982-11-01T23:59:59.000Z

    Blanket material selection for fusion reactors is strongly influenced by the desire to minimize safety and environmental concerns. Blanket material safety compatibility studies are being conducted to identify and characterize blanket-coolant-material interactions under postulated reactor accident conditions. Recently completed scoping compatibility tests indicate that : (1) ternary oxides (LiAlO/sub 2/, Li/sub 2/ZrO/sub 3/, Li/sub 2/SiO/sub 3/, Li/sub 4/SiO/sub 4/ and LiTiO/sub 3/) at postulated blanket operating temperatures are compatible with water coolant, while liquid lithium and Li/sub 7/Pb/sub 2/ alloy reactions with water generate heat, aerosol and hydrogen; (2) lithium oxide and Li/sub 17/Pb/sub 83/ alloy react mildly with water requiring special precautions to control hydrogen release; (3) liquid lithium reacts substantially, while Li/sub 17/Pb/sub 83/ alloy reacts mildly with concrete to produce hydrogen; and (4) liquid lithium-air reactions present some major safety concerns.

  3. September 14-16, 2004/ARR CERAMIC BREEDER BLANKET

    E-Print Network [OSTI]

    California at San Diego, University of

    . Dual-Coolant blanket concept with He-cooled steel structure and self-cooled liquid metal (Li or Pb-17Li · Optimization studies · Conclusions #12;September 14-16, 2004/ARR 3 Engineering Activities During Phase I for Down Selection to a Couple of Combinations for Detailed Studies During Phase II - Three Possible

  4. Geology Department Graduate Certificates: These certificates are designed to provide practicing professionals an opportunity to

    E-Print Network [OSTI]

    Geology Department Graduate Certificates: These certificates are designed to provide practicing are offered: Certificate in Engineering Geology Purpose The Graduate Certificate in Engineering Geology provides practicing geologists an opportunity to upgrade their engineering geology credentials while

  5. Forest management certification

    E-Print Network [OSTI]

    Liskiewicz, Maciej

    to the Montreal Process, certification systems lay out a set of criteria for sustainable management. Consumers. Each captures unique aspects of forestry and natural- resources management, offers indoor and outdoor.va.nrcs.usda.gov NRCS's natural resources conservation programs help people reduce soil erosion, enhance water supplies

  6. Database Management Certificate Program

    E-Print Network [OSTI]

    Rose, Michael R.

    Database Management Certificate Program DATABASE TECHNOLOGIES 13 Today, organizations in every to obtain general data analysis and management skills or apply both Oracle and Microsoft SQL Server database capabilities of relational databases in conjunction with the new "Big Data" management frameworks for data

  7. Top Threshold Physics

    E-Print Network [OSTI]

    Andre H. Hoang

    2006-04-21T23:59:59.000Z

    Running a future Linear Collider at the top pair threshold allows for precise measurements of the mass, the widths and the couplings of the top quark. I give a nontechnical review on recent theoretical developments and the theory status in top threshold physics concerning QCD corrections and top quark finite lifetime and electroweak effects. I also discuss threshold physics in the context of measurements of the top Yukawa coupling from $e^+e^-\\to t\\bar t H$ and of squark pair production.

  8. US ITER (International Thermonuclear Experimental Reactor) shield and blanket design activities

    SciTech Connect (OSTI)

    Baker, C.C.

    1988-08-01T23:59:59.000Z

    This paper summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He/sup 3/. 1 ref., 2 tabs.

  9. Degree Information 37 Transcripted Graduate Certificate Programs

    E-Print Network [OSTI]

    program Energy Sustainability Engineering Certificate Program Graduate Certificate in Advanced the student's career goals. Energy Sustainability Engineering Certificate. The graduate level Energy--environmentally benign, economically competitive, and socially acceptable--to engineer the sustainability of energy

  10. Certification/enforcement analysis

    SciTech Connect (OSTI)

    None

    1980-06-01T23:59:59.000Z

    Industry compliance with minimum energy efficiency standards will be assured through a two-part program approach of certification and enforcement activities. The technical support document (TSD) presents the analyses upon which the proposed rule for assuring that consumer product comply with applicable energy efficiency standards is based. Much of the TSD is based upon support provided DOE by Vitro Laboratories. The OAO Corporation provided additional support in the development of the sampling plan incorporated in the proposed rule. Vitro's recommended approach to appliance certification and enforcement, developed after consideration of various program options, benefits, and impacts, establishes the C/E program framework, general criteria, and procedures for assuring a specified level of energy efficiency performance of covered consumer products. The results of the OAO analysis are given in Volume II of the TSD.

  11. 148 SDSU Curriculum Guide 2010 University Guidelines for Certificate Programs

    E-Print Network [OSTI]

    Ponce, V. Miguel

    148 SDSU Curriculum Guide 2010 University Guidelines for Certificate Programs (Guidelines Based on Executive Order 806) Types of Certificate Programs San Diego State University offers two types of certificate programs: · Academic certificate programs, and · Professional certificate programs. Academic

  12. TORT certification package

    SciTech Connect (OSTI)

    Frost, R.L.

    1993-10-01T23:59:59.000Z

    The TORT code has been certified. TORT is a three-dimensional discrete ordinates transport theory code, than can solve neutron, photon, or coupled neutron/photon problems. The code will be used primarily for shielding and radiation field calculations SRS. As defined in this work, certification dies not imply validation. The code must be validated for a particular type of calculation before it can be used for critical applications.

  13. An Overview of US ITER Test Blanket Module Program

    SciTech Connect (OSTI)

    Ying, A.; Abdou, Mohamed A.; Wong, Clement; Malang, S.; Morley, Neil B.; Sawan, M.; Merrill, Brad; Sze, Dai Kai; Kurtz, Richard J.; Willms, Scott; Ulrickson, Mike; Zinkle, Steven J.

    2006-01-01T23:59:59.000Z

    A testing strategy and corresponding test plan have been presented for the two proposed US candidate breeder blankets: 1) a helium-cooled solid breeder concept with ferritic steel structure and Be neutron multiplier, but without a fully independent TBM, and 2) a dual-coolant helium-cooled ferritic steel structure with self-cooled LiPb breeding zone that uses a flow channel insert as MHD and thermal insulator. Example test module designs, and configuration choices for each line of ITER TBM are shown and discussed in the paper. In addition, near-term R&D items for decision-making on testing of both solid breeder and dual-coolant PbLi liquid breeder blanket concepts in ITER are identified.

  14. APT {sup 3}He target/blanket. Topical report

    SciTech Connect (OSTI)

    NONE

    1995-03-01T23:59:59.000Z

    The {sup 3}He target/blanket (T/B) preconceptual design for the 3/8-Goal facility is based on a 1000-MeV, 200-mA accelerator to produce a high-intensity proton beam that is expanded and then strikes one of two T/B modules. Each module consists of a centralized neutron source made of tungsten and lead, a proton beam backstop region made of zirconium and lead, and a moderator made of D{sub 2}O. Helium-3 gas is circulated through the neutron source region and the blanket to create tritium through neutron capture. The gas is continually processed to extract the tritium with an online separation process.

  15. Energy Department Issues Green Building Certification System...

    Office of Environmental Management (EM)

    Issues Green Building Certification System Final Rule to Support Increased Energy Measurement and Efficient Building Design Energy Department Issues Green Building Certification...

  16. Central Characterization Program (CCP) Transuranic Waste Certification...

    Office of Environmental Management (EM)

    Certification Plan Central Characterization Program (CCP) Transuranic Waste Certification Plan This document was used to determine facts and conditions during the Department of...

  17. Blanket comparison and selection study. Final report. Volume 2

    SciTech Connect (OSTI)

    Not Available

    1984-09-01T23:59:59.000Z

    The study focused on: (1) Development of reference design guidelines, evaluation criteria, and a methodology for evaluating and ranking candidate blanket concepts. (2) Compilation of the required data base and development of a uniform systems analysis for comparison. (3) Development of conceptual designs for the comparative evaluation. (4) Evaluation of leading concepts for engineering feasibility, economic performance, and safety. (5) Identification and prioritization of R and D requirements for the leading blanket concepts. Sixteen concepts (nine TMR and seven tokamak) which were identified as leading candidates in the early phases of the study, were evaluated in detail. The overall evaluation concluded that the following concepts should provide the focus for the blanket R and D program: (Breeder/Coolant/Structure), Lithium/Lithium/Vanadium Alloy, Li/sub 2/O/Helium/Ferritic Steel, LiPb Alloy/LiPb Alloy/Vanadium Alloy, and Lithium/Helium/Ferritic Steel. The primary R and D issues for the Li/Li/V concept are the development of an advanced structural alloy, resolution of MHD and corrosion problems, provision for an inert atmosphere (e.g., N/sub 2/) in the reactor building, and the development of non-water cooled near-plasma components, particularly for the tokamak. The main issues for the LiPb/LiPb/V concepts are similar to the Li/Li/V blanket with the addition of resolving the tritium recovery issue. The R and D issues for Li/sub 2/O/He/FS concept include resolution of the tritium recovery/containment issue, achieving adequate tritium breeding and resolving other solid breeder issues such as swelling and fabrication concerns. Major concerns for the Li/He/FS concept are related to its rather poor economic performance. Improvement of its economic performance will be somewhat concept-dependent and will be more of a systems engineering issue.

  18. Blanket comparison and selection study. Final report. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1984-09-01T23:59:59.000Z

    The study focused on: (1) Development of reference design guidelines, evaluation criteria, and a methodology for evaluating and ranking candidate blanket concepts. (2) Compilation of the required data base and development of a uniform systems analysis for comparison. (3) Development of conceptual designs for the comparative evaluation. (4) Evaluation of leading concepts for engineering feasibility, economic performance, and safety. (5) Identification and prioritization of R and D requirements for the leading blanket concepts. Sixteen concepts (nine TMR and seven tokamak) which were identified as leading candidates in the early phases of the study, were evaluated in detail. The overall evaluation concluded that the following concepts should provide the focus for the blanket R and D program: (Breeder/Coolant/Structure), Lithium/Lithium/Vanadium Alloy, Li/sub 2/O/Helium/Ferritic Steel, LiPb Alloy/LiPb Alloy/Vanadium Alloy, and Lithium/Helium/Ferritic Steel. The primary R and D issues for the Li/Li/V concept are the development of an advanced structural alloy, resolution of MHD and corrosion problems, provision for an inert atmosphere (e.g., N/sub 2/) in the reactor building, and the development of non-water cooled near-plasma components, particularly for the tokamak. The main issues for the LiPb/LiPb/V concept are similar to the Li/Li/V blanket with the addition of resolving the tritium recovery issue. The R and D issues for Li/sub 2/O/He/FS concept include resolution of the tritium recovery/containment issue, achieving adequate tritium breeding and resolving other solid breeder issues such as swelling and fabrication concerns. Major concerns for the Li/He/FS concept are related to its rather poor economic performance. Improvement of its economic performance will be somewhat concept-dependent and will be more of a systems engineering issue.

  19. A Helical Coolant Channel Design for the Solid Wall Blanket

    SciTech Connect (OSTI)

    Mogahed, E.A. [University of Wisconsin-Madison (United States)

    2003-07-15T23:59:59.000Z

    A helical coolant channel scheme is proposed for the APEX solid wall blanket module. The self-coolant breeder in this system is FLIBE (LiF)2(BeF2). The structural material is the nanocomposited alloy 12YWT. The neutron multiplier used in the current design is either stationary or slow moving liquid lead. The purpose of this study is to design a blanket that can handle a high wall loading (5 MW/m{sup 2}). In the mean time the design provides means to attain the maximum possible blanket outlet temperature and meet all engineering limits on temperature of structural material and liquids. An important issue for such a design is to optimize the system for minimum pressure loss. For advanced ferritic steel (12YWT) an upper temperature limit of 800 deg. C is expected, and a limit of 700 deg. C at the steel/FLIBE interface is recommended.The blanket module is composed of two main continuous routes. The first route is three helical rectangular channels side-by-side that surround a central box. The helical channels are fed from the bottom and exit at the top to feed the central channels in the central box. The coolant helical channels have a cross sectional area with a length of about 10 cm and a width that changes according to the position around the central box. For instance: the width of the coolant channels facing the plasma is the narrowest while it is the widest in the back (farthest from the plasma).In this design the coolant runs around the central box for only 5 turns to cover the total height of the first wall (6.8 m). The design is optimized with the FW channel width as a parameter with the heat transfer requirements at the first wall as the constraints.

  20. 1-pin blanket mockup: Results of the extended test campaign

    SciTech Connect (OSTI)

    Ferrari, M.; Talarico, C. [EURATOM-ENEA, Frascati (Italy); Furrer, M.; Simbolotti, G. [ENEA, S. Maria in Galeria (Italy)

    1996-12-31T23:59:59.000Z

    Following a preliminary test campaign (200 thermal cycles) on a solid breeder blanket mockup, an extended test campaign (about 1000 thermal cycles) has been carried out by ENEA. The duration of the test campaign represents a significant fraction of the blanket module lifetime in the ITER device. In particular, these out-of-pile experiments have been performed in order to test (both functional and endurance testing) the thermal-hydraulic and thermo-mechanical performance of a water cooled breeder-in-tube blanket mockup (1-PIN) using Li{sub 2}ZrO{sub 3} pebbles as a breeder material. The test campaign has been completed and the resulting data concerning thermal and thermal-hydraulic parameters have been elaborated and analyzed by means of a comparison with theoretical predictions based on a proper thermal-hydraulic model. The post test examination of the pebbles is in progress in order to investigate the thermo-mechanical behavior of the breeder material under cycling. The paper deals with the first part of the results. 6 refs., 11 figs., 1 tab.

  1. Professional Certificate in Risk Management

    E-Print Network [OSTI]

    Carleton University

    Professional Certificate in Risk Management 2010 Program 3 Part-time Courses CRM01: Essentials of Risk Management ­ Next Session Fall 2010 CRM02: Risk Control ­ Jan. 12 - April 26, 2010 CRM03: Risk to apply for the Canadian Risk Management (CRM) designation. #12;Professional Certificate in Risk

  2. Helium-cooled, FLiBe-breeder, beryllium-multiplier blanket for MINIMARS

    SciTech Connect (OSTI)

    Moir, R.W.; Lee, J.D.

    1986-06-01T23:59:59.000Z

    We adapted the helium-cooled, FLiBe-breeder blanket to the commercial tandem-mirror fusion-reactor design, MINIMARS. Vanadium was used to achieve high performance from the high-energy-release neutron-capture reactions and from the high-temperature operation permitted by the refractory property of the material, which increases the conversion efficiency and decreases the helium-pumping power. Although this blanket had the highest performance among the MINIMARS blankets designs, measured by Mn/sub th/ (blanket energy multiplication times thermal conversion efficiency), it had a cost of electricity (COE) 18% higher than the University of Wisconsin (UW) blanket design (42.5 vs 35.9 mills/kW.h). This increased cost was due to using higher-cost blanket materials (beryllium and vanadium) and a thicker blanket, which resulted in higher-cost central-cell magnets and the need for more blanket materials. Apparently, the high efficiency does not substantially affect the COE. Therefore, in the future, we recommend lowering the helium temperature so that ferritic steel can be used. This will result in a lower-cost blanket, which may compensate for the lower performance resulting from lower efficiency.

  3. APT Blanket System Model Based on Initial Conceptual Design - Integrated 1D TRAC System Model

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    This report documents the approaches taken in establishing a 1-dimensional integrated blanket system model using the TRAC code, developed by Los Alamos National Laboratory.

  4. DORT certification package

    SciTech Connect (OSTI)

    Frost, R.L.

    1994-01-01T23:59:59.000Z

    The DORT code has been certified. DORT is a two-dimensional discrete ordinates transport theory code, that can solve neutron, photon, or coupled neutron/photon problems. It is anticipated that DORT will be used for criticality calculations as well as for shielding and radiation field analysis at SRS. In addition to the DORT module itself, 5 utility programs that are useful in certain DORT applications have been certified. These modules are: GIP, DOS, GRTUNCL, BNDRYS, and RTFLUM. As defined in this work, certification does not imply validation. These codes must be validated for a particular type of calculation before they can be used for critical applications.

  5. Certification des structures d'hospitalisation domicile VS certification ISO 9000

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Certification des structures d'hospitalisation à domicile VS certification ISO 9000 RYM BEN comparative entre la certification ISO 9000 (International Organisation for Standardization) et la certification des HAD. Il s'agit de comparer la certification ISO 9000 à celle des établissements de santé et

  6. Study of MHD Corrosion and Transport of Corrosion Products of Ferritic/Martensitic Steels in the Flowing PbLi and its Application to Fusion Blanket

    E-Print Network [OSTI]

    Saeidi, Sheida

    2014-01-01T23:59:59.000Z

    components of a liquid breeder blanket of a fusion powerPb-17Li breeder first wall and blanket concept developmentPb-17Li breeder first wall and blanket concept development

  7. Journey to Leadership Certificate Program Application

    Broader source: Energy.gov [DOE]

    Application packet for Journey to Leadership Certificate Program Pilot course, includes description.

  8. MCNP certification package

    SciTech Connect (OSTI)

    Trumble, E.F.

    1992-08-01T23:59:59.000Z

    In response to a Department of Energy (DOE) request, Westinghouse Savannah River Company committed to certify all computer codes used in critical calculations at the site. Since the Monte Carlo Neutron Photon Transport (MCNP) code will be used to perform critical analyses involving criticality and shielding, the code must be certified. Certification as applied to existing computer codes includes the verification and validation process, placing the code in configuration control, and establishing user qualification standards and training requirements. All software intended for use in critical calculations must be certified. This report is intended to fulfill the requirements for the certification of the MCNP code, version 4.2, built June 11, 1992, by J.H. Hightower on the SRS CRAY. This report does not release MCNP for use under production status for any application for which a MCNP validation document does not exist. These validation documents will describe the specific range of applicability, limitations on use, results and biases for a particular MCNP application.

  9. Threshold for dissipative fission

    SciTech Connect (OSTI)

    Thoennessen, M.; Bertsch, G.F. (National Superconducting Cyclotron Laboratory and Department of Physics Astronomy, Michigan State University, East Lansing, Michigan 48824 (United States) Department of Physics, FM-15, University of Washington, Seattle, Washington 98105 (United States))

    1993-12-27T23:59:59.000Z

    We examine the empirical domain of validity of statistical theory, as applied to fission data on prefission neutron, charged particle, and [gamma]-ray multiplicities. Systematics are found in the threshold excitation energy for the appearance of nonstatistical fission. From the data on systems with not too high fissility,, the relevant phenomenological parameter is the ratio of the threshold temperature [ital T][sub thresh] to the (temperature dependent) fission barrier height [ital E][sub bar([ital T])]. The statistical model reproduces the data for [ital T][sub thresh]/[ital E][sub bar([ital T])[lt]0.26][plus minus]0.05 but underpredicts the multiplicities at higher [ital T][sub thresh]/[ital E][sub bar([ital T])] independent of mass and fissility of the systems.

  10. Building Operator Certification: Improving Commercial Building Energy Efficiency Through Operator Training and Certification

    E-Print Network [OSTI]

    Putnam, C.; Mulak, A.

    2001-01-01T23:59:59.000Z

    Building Operator Certification (BOC) is a competency-based certification for building operators designed to improve the energy efficiency of commercial buildings. Operators earn certification by attending training sessions and completing project...

  11. Holocene blanket peat development in south west Scotland : the roles of human activity, climate change and vegetation change 

    E-Print Network [OSTI]

    Flitcroft, Catherine Esther

    2006-11-29T23:59:59.000Z

    This thesis examines the role of autogenic and allogenic forces in determining the timing and development of blanket peat initiation and how the occurrence and growth of blanket peat subsequently constrains human activities. A number of factors...

  12. Overview of US Liquid Metal Blanket R&D ActivitiesR&D Activities

    E-Print Network [OSTI]

    Abdou, Mohamed

    Overview of US Liquid Metal Blanket R&D ActivitiesR&D Activities Mohamed A. Abdou and the US FNST 2324, 2010 Madrid, Spain Thursday, September 23y, p S1I3 Mohamed Abdou: "Overview of US Liquid Metal Transport inCorrosion/Deposition and Tritium Transport in LiquidMetal Blankets" S7I2 C. Wong/M. Abdou

  13. Thermal-Hydraulic Analysis of Seed-Blanket Unit Duplex Fuel Assemblies with VIPRE-01

    E-Print Network [OSTI]

    McDermott, Patrick 1987-

    2012-11-15T23:59:59.000Z

    and blanket unit (SBU) configuration, where the seed region contains standard UO2 fuel, and the blanket region contains an inert matrix (Pu,Np,Am)O2-MgO-ZrO2 fuel. The research efforts of this thesis are first to consider the higher burnup effects on DUPLEX...

  14. Project EARTH-11-SPH1: Impact ejecta blankets characteristics, origins and processes

    E-Print Network [OSTI]

    Henderson, Gideon

    and Chixculub ejecta have been proposed as either double layer ejecta (DLE) or multi-layer (MLE) ejecta blankets. The SFM can also be thought of as a DLE ejecta blanket which has a melt-clast rich lower layer, thought

  15. Page 1 of 3 Blanket and First Wall Science Priority and Funding Requirements,

    E-Print Network [OSTI]

    /photon/plasma transport and material interactions; heat, tritium and corrosion mass transfer; incompressible MHD) - the US has developed a potentially attractive family of blanket concepts based on liquid lead lithium, the socalled Dual Coolant Lead Lithium (DCLL) blanket being a leading example - the development of coupled

  16. MHD Analysis of Dual Coolant Pb-17Li Blanket for ARIES-CS C. Mistrangelo1

    E-Print Network [OSTI]

    Raffray, A. René

    MHD Analysis of Dual Coolant Pb-17Li Blanket for ARIES-CS C. Mistrangelo1 , A. R. Raffray2 of California, San Diego, La Jolla, CA 92093-0438, USA, rraffray@ucsd.edu A dual coolant Pb-17Li (DCLL) blanket of magnetohydrodynamic (MHD) flows in the poloidal channels that distribute the liquid metal in the breeder units has

  17. MHD EFFECTS ON HEAT TRANSFER IN A MOLTEN SALT BLANKET Sergey Smolentsev, Reza Miraghaie, Mohamed Abdou

    E-Print Network [OSTI]

    Abdou, Mohamed

    MHD EFFECTS ON HEAT TRANSFER IN A MOLTEN SALT BLANKET Sergey Smolentsev, Reza Miraghaie, Mohamed-mail (Sergey Smolentsev): Sergey@fusion.ucla.edu Heat transfer in closed channel flows of molten salts (MS), a number of blanket design options with molten salt (FLiBe or FLiNaBe) as the tritium breeder/coolant have

  18. Chapter 11 HELIUM-COOLED REFRACTORY ALLOYS FIRST WALL AND BLANKET EVALUATION

    E-Print Network [OSTI]

    California at Los Angeles, University of

    1 Chapter 11 HELIUM-COOLED REFRACTORY ALLOYS FIRST WALL AND BLANKET EVALUATION 11.1 Introduction performed thermal hydraulics, nuclear, activation and safety designs and analysis. High-pressure helium of the refractory alloy helium-cooled breeder FW/blanket concept developed under the APEX program is presented

  19. Heat-pipe liquid-pool-blanket concept for the Tandem Mirror Reactor

    SciTech Connect (OSTI)

    Hoffman, M.A.; Werner, R.W.; Johnson, G.L.

    1981-10-01T23:59:59.000Z

    The blanket concept for the tandem mirror reactor described in this paper was developed to produce the medium temperature heat (approx. 850 to 950 K) for the General Atomic sulfur-iodine thermochemical process for producing hydrogen. This medium temperature heat from the blanket constitutes about 81% of the total power output of the fusion reactor.

  20. Anaerobic Migrating Blanket Reactor Treatment of Low-Strength Wastewater at

    E-Print Network [OSTI]

    Angenent, Lars T.

    Anaerobic Migrating Blanket Reactor Treatment of Low-Strength Wastewater at Low Temperatures Largus anaerobic migrating blanket reactor (AMBR) was studied for the treatment of low- strength soluble wastewater). KEYWORDS: anaerobic treatment, low-strength wastewater, low-tem- perature conditions, compartmentalized

  1. Proposal for the award of a blanket purchase contract for the supply and maintenance of high-performance Ethernet switches

    E-Print Network [OSTI]

    2014-01-01T23:59:59.000Z

    Proposal for the award of a blanket purchase contract for the supply and maintenance of high-performance Ethernet switches

  2. Proposal for the award of a blanket purchase contract for the supply and maintenance of light vehicles

    E-Print Network [OSTI]

    2014-01-01T23:59:59.000Z

    Proposal for the award of a blanket purchase contract for the supply and maintenance of light vehicles

  3. Renewable Energy Certificate Program

    SciTech Connect (OSTI)

    Gwendolyn S. Andersen

    2012-07-17T23:59:59.000Z

    This project was primarily to develop and implement a curriculum which will train undergraduate and graduate students at the University seeking a degree as well as training for enrollees in a special certification program to prepare individuals to be employed in a broad range of occupations in the field of renewable energy and energy conservation. Curriculum development was by teams of Saint Francis University Faculty in the Business Administration and Science Departments and industry experts. Students seeking undergraduate and graduate degrees are able to enroll in courses offered within these departments which will combine theory and hands-on training in the various elements of wind power development. For example, the business department curriculum areas include economic modeling, finance, contracting, etc. The science areas include meteorology, energy conversion and projection, species identification, habitat protection, field data collection and analysis, etc.

  4. Tritium processing system for the ITER Li/V blanket test module

    SciTech Connect (OSTI)

    Sze, D.K.; Hua, T.Q. [Argonne National Lab., IL (United States); Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Dagher, M.A.; Waganer, L.M.

    1997-04-01T23:59:59.000Z

    The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate blanket concepts under a real fusion environment. To assure fuel self-sufficiency the tritium breeding, recovery and processing have to be demonstrated. The tritium produced in the blanket has to be processed to a purity which can be used for refueling. All these functions need to be accomplished so that the tritium system can be scaled to a commercial fusion power plant from a safety and reliability point of view. This paper summarizes the tritium processing steps, the size of the equipment, power requirements, space requirements, etc. for a self-cooled lithium blanket. This information is needed for the design and layout of the test blanket ancillary system and to assure that the ITER guidelines for remote handling of ancillary equipment can be met.

  5. Effective Thermal Conductivity of Lithium Ceramic Pebble Beds for Fusion Blankets: A Review

    SciTech Connect (OSTI)

    Abou-Sena, A.; Ying, A.; Abdou, M. [University of California, Los Angeles (United States)

    2005-05-15T23:59:59.000Z

    The use of lithium ceramic pebble beds has been considered in many blanket designs for the fusion reactors. Lithium ceramics have received a significant interest as tritium breeders for the fusion blankets during the last three decades. The thermal performance of the lithium ceramic pebble beds plays a key role for the fusion blankets. In order to study the heat transfer in the blanket, the effective thermal conductivity of the lithium ceramics pebble beds has to be well measured and characterized. The data of effective thermal conductivity of lithium ceramic pebble beds is important for the blanket design. Several studies have been dedicated to investigate the effective conductivity of the lithium ceramics pebble beds. The objective of this work is to review and compare the available data, presented by various studies, of effective conductivity of lithium ceramic pebble beds in order to address the current status of these data.

  6. Neutronics and thermal design analyses of US solid breeder blanket for ITER

    SciTech Connect (OSTI)

    Gohar, Y.; Billone, M.; Attaya, H. (Argonne National Lab., IL (USA)); Sawan, M. (Wisconsin Univ., Madison, WI (USA))

    1990-09-01T23:59:59.000Z

    The US Solid Breeder Blanket is designed to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. Safety, low tritium inventory, reliability, flexibility cost, and minimum R D requirements are the other design criteria. To satisfy these criteria, the produced tritium is recovered continuously during operation and the blanket coolant operates at low pressure. Beryllium multiplier material is used to control the solid-breeder temperature. Neutronics and thermal design analyses were performed in an integrated manner to define the blanket configuration. The reference parameters of ITER including the operating scenarios, the neutron wall loading distribution and the copper stabilizer are included in the design analyses. Several analyses were performed to study the impact of the reactor parameters, blanket dimensions, material characteristics, and heat transfer coefficient at the material interfaces on the blanket performance. The design analyses and the results from the different studies are summarized. 6 refs., 3 figs., 3 tabs.

  7. Strategic planning for LEED certification

    E-Print Network [OSTI]

    Capuzzi, Angelo Michael

    2010-01-01T23:59:59.000Z

    Intel Corporation has recently implemented a "green building" policy, which states that Intel will design all new facilities to achieve a minimum LEED-Silver certification. LEED (Leadership in Energy and Environmental ...

  8. Fusion Engineering and Design 81 (2006) 461467 An overview of dual coolant Pb17Li breeder first wall and blanket

    E-Print Network [OSTI]

    Abdou, Mohamed

    2006-01-01T23:59:59.000Z

    . Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb­17Li.V. All rights reserved. Keywords: Blanket; Pb­17Li breeder; Dual-coolant; Helium-cooled; ITER coolant Pb­17Li liquid breeder (DCLL) blanket design, a con- cept that has been explored extensively

  9. THERMOMECHANICAL ANALYSIS OF THE REVISED U.S. ITER DCLL TEST BLANKET MODULE Aaron T. Aoyama1

    E-Print Network [OSTI]

    Ghoniem, Nasr M.

    wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and blanket, and self-cooled Pb-17Li breeder circulated for power conversion and tritium extraction. A midTHERMOMECHANICAL ANALYSIS OF THE REVISED U.S. ITER DCLL TEST BLANKET MODULE Aaron T. Aoyama1

  10. Helium-cooled solid breeder blanket for ITER

    SciTech Connect (OSTI)

    Raffray, A.R.; Abdou, M.A.; Chou, P.; Gorbis, Z.; Tillack, M.; Watanabe, Y.; Ying, A.

    1989-03-01T23:59:59.000Z

    This paper summarizes the latest results of a design study of a helium-cooled solid breeder blanket for ITER. Attractive features of this design include the following: (1) There is a significant design margin since only part of the allowable solid breeder temperature window needs to be used. (2) There is an expanding data base available from solid breeder experiments carried out internationally. (3) The solid breeder can be designed to operate at high reactor-relevant temperature, while the helium is kept at moderate temperature and pressure for safety and reliability. In addition, since helium is a gas, it can be run so as to optimize the structure temperature and accommodate long term power variation without incurring any substantial pressure penalty. (4) The use of helium, an inert gas minimizing any chemical reaction and corrosion, in combination with a low activation solid breeder, is a safety advantage. An extensive list of the blanket operating parameters is provided and key factors are discussed.

  11. Engineering Scaling Requirements for Solid Breeder Blanket Testing

    SciTech Connect (OSTI)

    Ying, A.; Sharafat, S.; Youssef, M.; An, J.; Hunt, R.; Rainsberry, P.; Abdou, M. [University of California, Los Angeles (United States)

    2005-05-15T23:59:59.000Z

    An engineering scaling process is applied to the solid breeder ITER TBM designs in accordance with the testing objectives of validating the design tools and the database, and evaluating blanket performance under prototypical operating conditions. The goal of scaling is to ensure that changes in structural response and performance caused by changes in size and operating conditions do not reduce the usefulness of the tests. Initially, constitutive equations are applied to lay out the basic operating and design parameters that dominate blanket phenomena. The suitability of these similarity criteria for the TBM design is then confirmed by comparing finite element predictions of prototype and scale model responses. The TBM design also takes into account the need to check the codes and data for future design use. Specifically, predictability of tritium production and nuclear heating rates in a complex geometry, tritium release and permeation characteristics under fusion environments belong to this category. We conclude that this engineering scaling design process has maximized the value of ITER testing.

  12. Threshold voltage extraction circuit

    E-Print Network [OSTI]

    Hoon, Siew Kuok

    2000-01-01T23:59:59.000Z

    to that of the saturation method. However, instead of fixing Vos ? Vos, the drain current is measured as a function of Vos while Vns is fixed at a constant low voltage of 100mV to ensure operation in the linear MOSFET region. Neglecting channel length modulation effect... transistors are layout next to the DUT of the NMOS and PMOS Vr extraction circuits respectively for extraction of Vr via graphical means. GRAPHICAL METHOD OF THE THRESHOLD-VOLTAGE MEASUREMENT Using the graphical method, the characteristics of 4n versus Vos...

  13. A European proposal for a ITER water cooled solid breeder blanket

    SciTech Connect (OSTI)

    Lorenzetto, P. [NET, Garching (Germany); Gierszewski, P. [CFFTP, Mississauga, Ontario (Canada); Simbolotti, G. [ENEA, Frascati (Italy)

    1994-12-31T23:59:59.000Z

    The Water Cooled Solid Breeder Blanket concept here proposed is based on a conservative approach, involving well proven technologies and-qualified materials. 316 L type stainless steel has been selected as the structural material. The nominal performances are: 1 MW/m{sup 2} as the average neutron wall load which corresponds to a fusion power of about 1.5 GW, and 1 MWy/m{sup 2} as the average neutron fluence. The power margins of the proposed concept have been estimated. The proposed blanket concept is based on a Breeder Inside Tube (BIT) type blanket with poloidal breeding elements, whose dimensions are compatible with space available in test fission reactor core channels, that makes easier in-pile testing required for the blanket development and qualification. Each breeding element consists of two concentric tubes. 1.2 mm lithium metazirconate (Li{sub 2}ZrO{sub 3}) pebbles are filled into the inner tube, the water coolant flows in the annular channel between the two tubes, and 2 mm Beryllium pebbles are poured into the blanket box outside the outer tube. Lithium metazirconate has been selected as the breeder material because it presents today the best tritium release properties at low temperature. A helium purge gas flows through the breeder pebble bed for tritium recovery. A Shielding Blanket can be derived from the proposed Blanket concept by removing the breeder pebbles from the inner tube. In-situ convertibility issues are addressed.

  14. PREPARING FOR A SUCCESSFUL EVMS CERTIFICATION

    SciTech Connect (OSTI)

    CROWE SL; BASCHE AD

    2011-02-09T23:59:59.000Z

    The client, a government agency, requires its contractor to obtain an Earned Value Management System (EVMS) certification that meets the intent of ANSI/EIA-748-B, Earned Value Management Systems. The contractor has extensive experience with certification preparation, having completed two certifications within two years. Information from a previous EVMS certification and internal system surveillances are used to prepare for client-based EVMS certifications and bi-annual surveillances. The contractor also sent members of its group to assist other companies preparing for surveillances and certifications to perform 'Black Hat Reviews.' This paper is a lessons learned on preparing a team for EVMS certification. The information is also applicable for surveillances, since the contractor prepares its team for the surveillance in the same manner as the initial certification. Some of the areas covered include required documents, tracing the data through the systems, Control Account Manager (CAM) preparation, and system verification.

  15. STATE OF CALIFORNIA REFRIGERATED WAREHOUSE INSTALLATION CERTIFICATE

    E-Print Network [OSTI]

    STATE OF CALIFORNIA REFRIGERATED WAREHOUSE INSTALLATION CERTIFICATE CEC-RWH-INST (Revised 08 # BUILDING TYPE Refrigerated Warehouse PHASE OF CONSTRUCTION New Construction Addition Alteration If more By the Enforcement Agency #12;STATE OF CALIFORNIA REFRIGERATED WAREHOUSE INSTALLATION CERTIFICATE CEC

  16. Policy -Online Business Management Certificate Program

    E-Print Network [OSTI]

    Hanson, Stephen José

    Advisor-Instructor's assignments. Refund Policy (for Online Certificate program only - Lean Six Sigma programs. Grievance Policy If you are a participant in our Online Certificate Program or Lean/Six Sigma

  17. GRADUATE CERTIFICATE PROGRAM GEOGRAPHIC INFORMATION SCIENCES

    E-Print Network [OSTI]

    Doyle, Martin

    GRADUATE CERTIFICATE PROGRAM GEOGRAPHIC INFORMATION SCIENCES Department of Geography University Information Sciences (GIScience) study geospatial phenomena using an integrated set of spatial digital Certificate Program in Geographic Information Sciences offered within the Department of Geography is designed

  18. Community Leadership Certificate Program Program Overview

    E-Print Network [OSTI]

    Saldin, Dilano

    Community Leadership Certificate Program Program Overview The undergraduate Community Leadership Certificate Program is an interdisciplinary program where students from any major can explore leadership in community engagement and leadership. The program is based on a social justice model of leadership

  19. Computational Science and Engineering Certification for Chemistry

    E-Print Network [OSTI]

    Gilbert, Matthew

    Computational Science and Engineering Certification for Chemistry The Computational Science that are distinct from already- required coursework. To receive a certificate in "Computational Science a solid base in problem solving using computation as a major tool for modeling complicated problems

  20. T-706: Microsoft Fraudulent Digital Certificate Issued by DigiNotar

    Broader source: Energy.gov [DOE]

    Fraudulent Digital Certificate Issued by DigiNotar, a Certification Authority Present in the Trusted Root Certification Authorities

  1. ARTS LEADERSHIP Graduate Academic Certificate Program

    E-Print Network [OSTI]

    Mohanty, Saraju P.

    ARTS LEADERSHIP Graduate Academic Certificate Program The Certificate in Arts Leadership leadership. Within a broad definition of leadership as "a process whereby an individual influences a group of individuals to achieve a common goal," the Certificate in Arts Leadership addresses four essential components

  2. Division of Human Resources Payroll Certification Process

    E-Print Network [OSTI]

    Meyers, Steven D.

    Division of Human Resources Payroll Certification Process Questions (813) 974-7955 Payroll/Payroll Processing Rev. 04/2010 Payroll Certification is the process by which departments submit to Payroll the hours to be paid for each employee within each department. This process utilizes the online Certification System

  3. Considerations when applying thresholds to

    E-Print Network [OSTI]

    Wind erosion thresholds are crossed as gap sizes increase due to grass mortality (often, but not always (wind erosion) or property (gap size) Resilience begins to decline ­ increasing probability (wind erosion) or property (gap size) "THRESHOLD" #12;Probabilityofautogenicrecovery Status of key

  4. Resilience, Triggers, Feedbacks and Thresholds

    E-Print Network [OSTI]

    High Low Energy capture efficiency Nutrient retention efficiencyResource flows captured by organic Australia's Rangelands. CSIRO, Australia. Pp. 158. #12;Ecological Thresholds ``Thresholds are boundaries-functional Recovery requires vegetation manipulation Water capture efficiencyHigh Low High Low High Low Moderate High

  5. Polymer material selection and testing of resistive wire arrangement for a transparent infant warming blanket

    E-Print Network [OSTI]

    Salazar, Madeline

    2013-01-01T23:59:59.000Z

    The ThermoCloud was designed as a portable, scalable, transparent electrical blanket to warm and insulate infants, while permitting hassle-free medical transportation and maximum visualization of a patient's thorax and ...

  6. Design, construction and evaluation of a facility for the simulation of fast reactor blankets

    E-Print Network [OSTI]

    Forbes, Ian Alexander

    1970-01-01T23:59:59.000Z

    A facility has been designed and constructed at the MIT Reactor for the experimental investigation of typical LMFBR breeding blankets. A large converter assembly, consisting of a 20-cm-thick layer of graphite followed by ...

  7. Normal Operation (NO) of APT Blanket System and its Components Based on Initial Conceptual Design

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    This report is one of a series of reports documenting accident scenario simulations for the Accelerator Production of Tritium (APT) blanket heat removal systems. The simulations were performed in support of the Preliminary Safety Analysis Report (PSAR) for the APT.

  8. Feasibility study of a fission supressed blanket for a tandem-mirror hybrid reactor

    SciTech Connect (OSTI)

    Moir, R.W.; Lee, J.D.; Barr, W.L.

    1981-10-05T23:59:59.000Z

    A study of fission suppressed blankets for the tandem mirror not only showed such blankets to be feasible but also to be safer than fissioning blankets. Such hybrids could produce enough fissile material to support up to 17 light water reactors of the same nuclear power rating. Beryllium was compared to /sup 7/Li for neutron multiplication; both were considered feasible but the blanket with Li produced 20% less fissile fuel per unit of nuclear power in the reactor. The beryllium resource, while possibly being too small for extensive pure fusion application, would be adequate (with carefully planned industrial expansion) for the hybrid because of the large support ratio, and hence few hybrids required. Radiation damage and coatings for beryllium remain issues to be resolved by further study and experimentation.

  9. The effect of reactor size on the breeding economics of LMFBR blankets

    E-Print Network [OSTI]

    Tagishi, Akinori

    1975-01-01T23:59:59.000Z

    The effect of reactor size on the neutronic and economic performance of LMFBR blankets driven by radially-power-flattened cores has been investigated using both simple models and state-of-the-art computer methods. Reactor ...

  10. Irradiation Testing of Blanket Materials at the HFR Petten with On Line Tritium Monitoring

    SciTech Connect (OSTI)

    Magielsen, A.J.; Laan, J.G. van der; Hegeman, J.B.J.; Stijkel, M.P.; Ooijevaar, M.A.G

    2005-07-15T23:59:59.000Z

    Irradiation experiments are performed in support of fusion blanket technology development. These comprise ceramic solid breeder materials, and a liquid Lithium Lead alloy, as well as blanket subassemblies and components. Experimental facilities at the HFR to study tritium release, permeation characteristics, and neutron irradiation performance, have recently been extended. This paper gives an overview on the tritium breeding materials irradiation programme and describes the facilities required for irradiation testing and on-line tritium measurement.

  11. Application of variational techniques for parametric studies of steady-state controlled thermonuclear reactor blankets 

    E-Print Network [OSTI]

    Pearce, James David

    1975-01-01T23:59:59.000Z

    APPLICATION OF VARIATIONAL TECHNIQUES FOR PARAMETRIC STUDIES OF STEADY-STATE CONTROLLED THERMONUCLEAR REACTOR BLANKETS A Thesis JAMES DAVID PEARCE Submitted to the Graduate College of Texas A6M University in partial fulfillment... of the requirement for the degree of MASTER OP SCIENCE May 1975 Ma)or Subject: Nuclear Engineering APPLICATION OF VARIATIONAL TECHNIQUES FOR PARAMETRIC STUDIES OF STEADY-STATE CONTROLLED THERMONUCLEAR REACTOR BLANKETS A Thesis by JAMES DAVID PEARCE Approved...

  12. Preliminary Failure Modes and Effects Analysis of the US DCLL Test Blanket Module

    SciTech Connect (OSTI)

    Lee C. Cadwallader

    2010-06-01T23:59:59.000Z

    This report presents the results of a preliminary failure modes and effects analysis (FMEA) of a small tritium-breeding test blanket module design for the International Thermonuclear Experimental Reactor. The FMEA was quantified with “generic” component failure rate data, and the failure events are binned into postulated initiating event families and frequency categories for safety assessment. An appendix to this report contains repair time data to support an occupational radiation exposure assessment for test blanket module maintenance.

  13. Application of variational techniques for parametric studies of steady-state controlled thermonuclear reactor blankets

    E-Print Network [OSTI]

    Pearce, James David

    1975-01-01T23:59:59.000Z

    APPLICATION OF VARIATIONAL TECHNIQUES FOR PARAMETRIC STUDIES OF STEADY-STATE CONTROLLED THERMONUCLEAR REACTOR BLANKETS A Thesis JAMES DAVID PEARCE Submitted to the Graduate College of Texas A6M University in partial fulfillment... of the requirement for the degree of MASTER OP SCIENCE May 1975 Ma)or Subject: Nuclear Engineering APPLICATION OF VARIATIONAL TECHNIQUES FOR PARAMETRIC STUDIES OF STEADY-STATE CONTROLLED THERMONUCLEAR REACTOR BLANKETS A Thesis by JAMES DAVID PEARCE Approved...

  14. Advanced methods comparisons of reaction rates in the purdue fast breeder blanket facility

    SciTech Connect (OSTI)

    Hill, R.N. (Argonne National Lab., IL (USA). Engineering Div.); Ott, K.O. (Purdue Univ., Lafayette, IN (USA). School of Nuclear Engineering)

    1989-09-01T23:59:59.000Z

    The authors discuss how experiments in the large uniform Purdue University fast breeder blanket facility blanket yield an accurate quantification of this discrepancy. Using standard production code methods (diffusion theory with 50-group cross sections), a consistent calculated-to-experimental (C/E) drop-off is observed for various reaction rates. A 50% increase in the calculated results at the outer edge of the 51-cm blanket is necessary for agreement with experiments. The usefulness of refined group constant generation, utilizing speciaized weighting spectra, and transport theory methods in correcting this discrepancy is analyzed. Refined group constants reduce the discrepancy to half that observed using the standard method. The result is that transport methods have no effect on the blanket deviations; thus, the present multigroup transport theory does not constitute or even contribute to an explanation of the blanket discrepancies. The residual blanket C/E drop-off (about half the standard drop-off) using advanced methods must be caused by approximations that are applied in all current multigroup methods.

  15. Multiplier, moderator, and reflector materials for lithium-vanadium fusion blankets.

    SciTech Connect (OSTI)

    Gohar, Y.; Smith, D. L.

    1999-10-07T23:59:59.000Z

    The self-cooled lithium-vanadium fusion blanket concept has several attractive operational and environmental features. In this concept, liquid lithium works as the tritium breeder and coolant to alleviate issues of coolant breeder compatibility and reactivity. Vanadium alloy (V-4Cr-4Ti) is used as the structural material because of its superior performance relative to other alloys for this application. However, this concept has poor attenuation characteristics and energy multiplication for the DT neutrons. An advanced self-cooled lithium-vanadium fusion blanket concept has been developed to eliminate these drawbacks while maintaining all the attractive features of the conventional concept. An electrical insulator coating for the coolant channels, spectral shifter (multiplier, and moderator) and reflector were utilized in the blanket design to enhance the blanket performance. In addition, the blanket was designed to have the capability to operate at high loading conditions of 2 MW/m{sup 2} surface heat flux and 10 MW/m{sup 2} neutron wall loading. This paper assesses the spectral shifter and the reflector materials and it defines the technological requirements of this advanced blanket concept.

  16. Certificate Industrial and Systems Engineering

    E-Print Network [OSTI]

    Su, Xiao

    Six Sigma Certificate Industrial and Systems Engineering San José State University September, 2008 #12;1 Lean Enterprise and Six Sigma Lean Enterprise about transforming the old mass production-to-cradle design, incorporating design for manufacturability, reproducibility, product lifecycle, etc. Six Sigma

  17. FINANCIAL RISK MANAGER (FRM ) CERTIFICATION

    E-Print Network [OSTI]

    Chaudhuri, Sanjay

    Dec 2013 (Save 30%) (Save 15%) Module 1 Foundation of Risk Management & Quantitative Analysis 1086FINANCIAL RISK MANAGER (FRM® ) CERTIFICATION TRAINING PROGRAM 2014 JANUARY INTAKE 4 January to 10 1321 1552 Module 2 Financial Markets and Products & Valuation and Risk Models 1637 1985 2333 Module 3

  18. Postgraduate Certificate in Geothermal Energy

    E-Print Network [OSTI]

    Auckland, University of

    Postgraduate Certificate in Geothermal Energy Technology The University of Auckland The University for development of geothermal fields is large and many countries are seeking to move away from fossil fuel power generation for both economic and environmental reasons. Global revenues for geothermal power were estimated

  19. Official Certificate List Level(s)* Academic Administrative

    E-Print Network [OSTI]

    Risk, Uncertainty and Decision Analysis EGRU335 Certificate in Engineering Thermal Energy Systems EGRU International Certificate ALSU198 Certificate for Biology in Engineering for Engineering Majors EGRU135 Level IESG310 Certificate in Engineering for Energy Sustainability EGRU340 Certificate in Engineering

  20. Progress and critical issues for IFE blanket and chamber research

    SciTech Connect (OSTI)

    Abdou, M.; Kulcinski, G.L.; Latkowski, J.F.; Logan, B.G.; Meier, W.R.; Moir, R.W.; Nobile, A.; Peterson, P.F.; Petti, D.; Schultz, K.R.; Tillack, M.S.

    1999-06-23T23:59:59.000Z

    Advances in high gain target designs for Inertial Fusion Energy (IFE), and the initiation of construction of large megajoule-class laser facilities in the U.S. (National Ignition Facility) and France (Laser-Megajoule) capable of testing the requirements for inertial fusion ignition and propagating burn, have improved the prospects for IFE. Accordingly, there have recently been modest increases in the US fusion research program related to the feasibility of IFE. These research areas include heavy-ion accelerators, Krypton-Fluoride (KrF) gas lasers, diode-pumped, solid-state (DPSSL) lasers, IFE target designs for higher gains, feasibility of low cost IFE target fabrication and accurate injection, and long-lasting IFE fusion chambers and final optics. Since several studies of conceptual IFE power plant and driver designs were completed in 1992-1996 [1-5], U.S. research in the IFE blanket, chamber, and target technology areas has focused on the critical issues relating to the feasibility of IFE concepts towards the goal of achieving economically-competitive and environmentally-attractive fusion energy. This paper discusses the critical issues in these areas, and the approaches taken to address these issues. The U.S. research in these areas, called IFE Chamber and Target Technologies, is coordinated through the Virtual Laboratory for Technology (VLT) formed by the Department of Energy in December 1998.

  1. Helium-Cooled Refractory Alloys First Wall and Blanket Evaluation

    SciTech Connect (OSTI)

    Wong, C.P.C.; Nygren, R.E.; Baxi, C.B.; Fogarty, P.; Ghoniem, N.; Khater, H.; McCarthy, K.; Merrill, B.; Nelson, B.; Reis, E.E.; Sharafat, S.; Schleicher, R.; Sze, D.K.; Ulrickson, M.; Willms, S.; Youssef, M.; Zinkel, S.

    1999-08-01T23:59:59.000Z

    Under the APEX program the He-cooled system design task is to evaluate and recommend high power density refractory alloy first wall and blanket designs and to recommend and initiate tests to address critical issues. We completed the preliminary design of a helium-cooled, W-5Re alloy, lithium breeder design and the results are reported in this paper. Many areas of the design were assessed, including material selection, helium impurity control, and mechanical, nuclear and thermal hydraulics design, and waste disposal, tritium and safety design. System study results show that at a closed cycle gas turbine (CCGT) gross thermal efficiency of 57.5%, a superconducting coil tokamak reactor, with an aspect ratio of 4, and an output power of 2 GWe, can be projected to have a cost of electricity at 54.6 mill/kWh. Critical issues were identified and we plan to continue the design on some of the critical issues during the next phase of the APEX design study.

  2. STEPLENGTH THRESHOLDS FOR INVARIANCE PRESERVING ...

    E-Print Network [OSTI]

    2014-06-25T23:59:59.000Z

    ods, i.e., the coefficient matrix of the discrete system is derived from the Taylor expansion of eAc?t, we present an algorithm to derive a valid steplength threshold.

  3. Summing tree graphs at threshold

    SciTech Connect (OSTI)

    Brown, L.S. (Department of Physics, FM-15, University of Washington, Seattle, Washington 98195 (United States))

    1992-11-15T23:59:59.000Z

    The solution of the classical field equation generates the sum of all tree graphs. We show that the classical equation reduces to an easily solved ordinary differential equation for certain multiparticle threshold amplitudes and compute these amplitudes.

  4. A. R. Raffray, et, al., High Performance Blanket for ARIES-AT Power Plant, SOFT 2000 HIGH PERFORMANCE BLANKET FOR ARIES-AT

    E-Print Network [OSTI]

    California at San Diego, University of

    material. This paper describes the results of the design study of this blanket including a discussionCf/SiC composite as structural material. The Pb-17Li operating temperature is optimized to provide high power cycle) = 35 °C · Turbine efficiency = 93%; Compressor efficiency = 90% #12;A. R. Raffray, et, al., High

  5. DCLL TBM Safety Assessment A key objective for ITER includes integrated testing of blanket concepts suitable for demonstrating fusion

    E-Print Network [OSTI]

    prototypical blanket modules into designated ports. Because ITER will be a licensed nuclear facility, occupation radiation exposure (ORE) analyzed, and decommissioning and waste disposal analysis performed

  6. A passively-safe fusion reactor blanket with helium coolant and steel structure

    SciTech Connect (OSTI)

    Crosswait, K.M.

    1994-04-01T23:59:59.000Z

    Helium is attractive for use as a fusion blanket coolant for a number of reasons. It is neutronically and chemically inert, nonmagnetic, and will not change phase during any off-normal or accident condition. A significant disadvantage of helium, however, is its low density and volumetric heat capacity. This disadvantage manifests itself most clearly during undercooling accident conditions such as a loss of coolant accident (LOCA) or a loss of flow accident (LOFA). This thesis describes a new helium-cooled tritium breeding blanket concept which performs significantly better during such accidents than current designs. The proposed blanket uses reduced-activation ferritic steel as a structural material and is designed for neutron wall loads exceeding 4 MW/m{sup 2}. The proposed geometry is based on the nested-shell concept developed by Wong, but some novel features are used to reduce the severity of the first wall temperature excursion. These features include the following: (1) A ``beryllium-joint`` concept is introduced, which allows solid beryllium slabs to be used as a thermal conduction path from the first wall to the cooler portions of the blanket. The joint concept allows for significant swelling of the beryllium (10 percent or more) without developing large stresses in the blanket structure. (2) Natural circulation of the coolant in the water-cooled shield is used to maintain shield temperatures below 100 degrees C, thus maintaining a heat sink close to the blanket during the accident. This ensures the long-term passive safety of the blanket.

  7. UAF Green Department Certification UAF OFFICE OF SUSTAINABILITY

    E-Print Network [OSTI]

    Hartman, Chris

    /Documentation: Computers are set to energy saving modes. Description/Documentation: GREEN DEPARTMENT PLEDGE UAF Green Department Certification UAF OFFICE OF SUSTAINABILITY GREEN DEPARTMENT CERTIFICATION INSTRUCTIONS & FORMS PART I: GETTING STARTED & REQUIRED ACTIONS #12; UAF Green Department Certification

  8. Security Certification & Accreditation of Federal Information Systems A Tutorial

    E-Print Network [OSTI]

    Madisetti, Vijay K.

    Security Certification & Accreditation of Federal Information Systems A Tutorial An Introduction Madisetti, 06/29/2009 Security Certification & Assurance of Federal Information Systems Tutorial Tutorial Outline Objectives & Introduction: C&A Information Security Certification & Accreditation Foundations (as

  9. Computational Science and Engineering Certification for Atmospheric Sciences Undergraduate Students

    E-Print Network [OSTI]

    Gilbert, Matthew

    Computational Science and Engineering Certification for Atmospheric Sciences Undergraduate Students The Computational Science and Engineering certificate program is designed to provide ATMS under- graduate students a certificate in "Computational Science and Engineering," students must complete the required courses listed

  10. Tivoli Professional Certification e-Newsletter Check Out the Latest Tivoli Certifications and News

    E-Print Network [OSTI]

    & Certification Retirement -> Fund. of Enterprise Solutions Using IBM Tivoli Security 2007 Tivoli Storage Manager of the Month -> Shayne Gardener Promotions - Discounted Exams and Assessments -> "Early Bird" Specials & CERTIFICATION RETIREMENT For the latest news in exam withdrawals and certification retirement, go to: http

  11. Tivoli Professional Certification e-Check Out the Latest Tivoli Certifications

    E-Print Network [OSTI]

    Workshops -> IBM Tivoli Storage Manager V6.1 Administration Exam Withdrawal & Certification Retirement Rodriguez Promotions - Discounted Exams and Assessments -> "Early Bird" Specials for Newly Published Exams & CERTIFICATION RETIREMENT For the latest news in exam withdrawals and certification retirement, go to: http

  12. Motor Vehicle Rental Exemption Certificate THIS EXEMPTION CERTIFICATE IS NOT VALID FOR TAX-FREE REGISTRATION.

    E-Print Network [OSTI]

    Behmer, Spencer T.

    Motor Vehicle Rental Exemption Certificate THIS EXEMPTION CERTIFICATE IS NOT VALID FOR TAX-FREE REGISTRATION. THIS EXEMPTION CERTIFICATE MUST BE ATTACHED TO THE RENTAL CONTRACT. Make of Vehicle Motor or Vehicle Identification Number Year Model Body Style License Number The undersigned claims exemption from

  13. Personnel Selection, Training, Qualification, and Certification...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    6.2 Admin Chg 1, Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities by Sam Rosenbloom Functional areas: Administrative Change,...

  14. Personnel Selection, Training, Qualification, and Certification...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    6.2, Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities by Sam Rosenbloom Functional areas: Safety, The order establishes...

  15. FEMA - National Flood Insurance Program Elevation Certificate...

    Open Energy Info (EERE)

    and Instructions Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: FEMA - National Flood Insurance Program Elevation Certificate and Instructions...

  16. Vermont Water Quality Certification Application for Hydroelectric...

    Open Energy Info (EERE)

    Vermont Water Quality Certification Application for Hydroelectric Facilities Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: Vermont Water Quality...

  17. Renewable Energy Specifications, Testing and Certification Terms...

    Open Energy Info (EERE)

    Terms of Reference Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Renewable Energy Specifications, Testing and Certification Terms of Reference Agency...

  18. Arizona Corporation Commission Application for a Certificate...

    Open Energy Info (EERE)

    Application for a Certificate of Convenience and Necessity for Competitive Retail Electricity Services Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal...

  19. CRADA ORGANIZATIONAL CONFLICTS OF INTEREST (OCI) CERTIFICATION

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    CRADA No. CRADA ORGANIZATIONAL CONFLICTS OF INTEREST (OCI) CERTIFICATION In accordance with Clause I.105 - Technology Transfer Mission, (n)(5)i of Contract No....

  20. POLICY GUIDANCE MEMORANDUM #27 Certification Program on Prohibited...

    Office of Environmental Management (EM)

    7 Certification Program on Prohibited Personnel Practices and Whistleblower Protections POLICY GUIDANCE MEMORANDUM 27 Certification Program on Prohibited Personnel Practices and...

  1. Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality Breakout Session 2: Frontiers and Horizons Session 2-B:...

  2. Iowa Water and Wastewater Operators Seek SEP Certification in...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Iowa Water and Wastewater Operators Seek SEP Certification in New Pilot Program Iowa Water and Wastewater Operators Seek SEP Certification in New Pilot Program September 18, 2014 -...

  3. Volvo: Certification of an Integrated ISO 14001 and ISO 50001...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Assistance Superior Energy Performance Volvo: Certification of an Integrated ISO 14001 and ISO 50001SEP System Volvo: Certification of an Integrated ISO 14001 and ISO...

  4. Green Building Certification Systems Requirement for New Federal...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Green Building Certification Systems Requirement for New Federal Buildings and Major Renovations of Federal Buildings OIRA Comparison Document Green Building Certification Systems...

  5. INTEGRATION OF THE MODULAR DUAL COOLANT PB-17LI BLANKET CONCEPT IN THE ARIES-CS POWER PLANT

    E-Print Network [OSTI]

    Raffray, A. René

    , San Diego, CA, 9500 Gilman Drive, La Jolla, CA 92093-0438, USA, xrwang@ucsd.edu 2 Fusion Nuclear blanket became also the reference concept in the US-ITER Test Blanket Module (TBM) program.4 Connected. II. RADIAL BUILD OF THE POWER CORE WITH INTERNAL VACUUM VESSEL The thickness of the different zones

  6. Fusion Engineering and Design 41 (1998) 561567 Combination of a self-cooled liquid metal breeder blanket with

    E-Print Network [OSTI]

    1998-01-01T23:59:59.000Z

    , the cost of electricity. Self-cooled liquid metal breeder blankets have a high potential to meetFusion Engineering and Design 41 (1998) 561­567 Combination of a self-cooled liquid metal breeder blanket with a gas turbine power conversion system S. Malang a, *, H. Schnauder a , M.S. Tillack b

  7. School of Animal, Rural and Environmental Sciences Management of carbon budgets for severely eroded upland blanket peat bogs impacts

    E-Print Network [OSTI]

    Evans, Paul

    upland blanket peat bogs ­ impacts of restoration Blanket bog is an important carbon sink and an Annex 1 Habitat priority under the EU Habitats Directive, but in the Peak District National Park much suffers peat by Natural England as an important site for studies of vegetation history and peat erosion in the Pennines

  8. Annular seed-blanket thorium fuel core concepts for heavy water moderated reactors

    SciTech Connect (OSTI)

    Bromley, B.P.; Hyland, B. [Atomic Energy of Canada Limited, Chalk River Laboratories, 1 Plant Road, Chalk River, Ontario, K0J 1J0 (Canada)

    2013-07-01T23:59:59.000Z

    New reactor concepts to implement thorium-based fuel cycles have been explored to achieve maximum resource utilization. Pressure tube heavy water reactors (PT-HWR) are highly advantageous for implementing the use of thorium-based fuels because of their high neutron economy and on-line re-fuelling capability. The use of heterogeneous seed-blanket core concepts in a PT-HWR where higher-fissile-content seed fuel bundles are physically separate from lower-fissile-content blanket bundles allows more flexibility and control in fuel management to maximize the fissile utilization and conversion of fertile fuel. The lattice concept chosen is a 35-element bundle made with a homogeneous mixture of reactor grade Pu and Th, and with a central zirconia rod to help reduce coolant void reactivity. Several annular heterogeneous seed-blanket core concepts with plutonium-thorium-based fuels in a 700-MWe-class PT-HWR were analyzed, using a once-through thorium (OTT) cycle. Different combinations of seed and blanket fuel were tested to determine the impact on core-average burnup, fissile utilization, power distributions, and other performance parameters. It was found that the various core concepts can achieve a fissile utilization that is up to 30% higher than is currently achieved in a PT-HWR using conventional natural uranium fuel bundles. Up to 67% of the Pu is consumed; up to 43% of the energy is produced from thorium, and up to 363 kg/year of U-233 is produced. Seed-blanket cores with ?50% content of low-power blanket bundles may require power de-rating (?58% to 65%) to avoid exceeding maximum limits for peak channel power, bundle power and linear element ratings. (authors)

  9. Flibe blanket concept for transmuting transuranic elements and long lived fission products.

    SciTech Connect (OSTI)

    Gohar, Y.

    2000-11-15T23:59:59.000Z

    A Molten salt (Flibe) fusion blanket concept has been developed to solve the disposition problems of the spent nuclear fuel and the transuranic elements. This blanket concept can achieve the top rated solution, the complete elimination of the transuranic elements and the long-lived fission products. Small driven fusion devices with low neutron wall loading and low neutron fluence can perform this function. A 344-MW integrated fusion power from D-T plasmas for thirty years with an availability factor of 0.75 can dispose of 70,000 tons of the US inventory of spent nuclear fuel generated up to the year 2015. In addition, the utilization of this blanket concept eliminates the need for a geological repository site, which is a major advantage. This application provides an excellent opportunity to develop and to enhance the public acceptance of the fusion energy for the future. The energy from the transmutation process is utilized to produce revenue. Flibe, lithium-lead eutectic, and liquid lead are possible candidates. The liquid blankets have several features, which are suited for W application. It can operate at constant thermal power without interruption for refueling by adjusting the concentration of the transuranic elements and lithium-6. These liquids operate at low-pressure, which reduces the primary stresses in the structure material. Development and fabrication costs of solid transuranic materials are eliminated. Burnup limit of the transuranic elements due to radiation effects is eliminated. Heat is generated within the liquid, which simplifies the heat removal process without producing thermal stresses. These blanket concepts have large negative temperature coefficient with respect to the blanket reactivity, which enhances the safety performance. These liquids are chemically and thermally stable under irradiation conditions, which minimize the radioactive waste volume. The operational record of the Molten Salt Breeder Reactor with Flibe was very successful, which established the technical bases for this application. This paper provides the technical analyses and the performance of the Flibe blanket concept as an example of this class of blankets.

  10. Thorium oxide slurries as blankets in fissile producing fusion- fission hybrids

    E-Print Network [OSTI]

    Geer, Thomas Charles

    1982-01-01T23:59:59.000Z

    of Advisory Committee: Dr. T. A. Parish An alternative to fixed-fertile and molten salt fissile producing fusion-fission hybrid blankets was developed. The neutronic feasibility of a thorium oxide-heavy water slurry as a blanket was tested for a Catalyzed... of continuous fission product and fissile material removal, thus limiting the in-situ burnup of the product. A natural consideration for such a fluid fuel system is a molten salt. Fluorides of either uranium of thorium can be dissilved in molten flouride...

  11. CERTIFICATE OF REGISTRATION Quality Management Systems

    E-Print Network [OSTI]

    Rodriguez, Carlos

    CERTIFICATE OF REGISTRATION Quality Management Systems INDIAN AGRICULTURAL STATISTICS RESEARCH Certifications Limited Certifies that the Management System of the above mentioned Company has been assessed and meets the requirements established by the following rules: ISO 9001 :2008 The Management System Includes

  12. Learning Lessons to Promote Certification and

    E-Print Network [OSTI]

    Financing and Investment in Companies Engaged in Destructive or Illegal Logging in Indonesia 14 2Learning Lessons to Promote Certification and Combat Illegal Logging in Indonesia September 2003;Learning Lessons to Promote Certification and Combat Illegal Logging in Indonesia September 2003 to June

  13. Insulin Pump Software Certification Yihai Chen1,

    E-Print Network [OSTI]

    Lawford, Mark

    Insulin Pump Software Certification Yihai Chen1, , Mark Lawford2, , Hao Wang2, , and Alan Wassyng2 for Software Certification McMaster University, Hamilton, Ontario, Canada Abstract. The insulin pump. Malfunction of the insulin pump will endanger the user's life. All countries impose some regula- tion

  14. The Graduate Certificate in Management of Technology

    E-Print Network [OSTI]

    Bieber, Michael

    The Graduate Certificate in Management of Technology Entirely Online and In Class New Jersey Institute of Technology School of Management THE EDGE IN KNOWLEDGE May 2012 Rev Use your smartphone to scan://www.njit.edu/continuing/ #12;WHY PURSUE A GRADUATE CERTIFICATE IN MANAGEMENT OF TECHNOLOGY? Developments in science

  15. Modified 2/11/2003 PATENT CERTIFICATION

    E-Print Network [OSTI]

    Pennycook, Steve

    DOE/ORO Modified 2/11/2003 PATENT CERTIFICATION Interim Certification Subcontractor Final and disclosing subject inventions as required by the patent clause of the subcontract have been followed. The completion date of this Subcontract is as follows: . The following period is covered by this patent

  16. Graduate Certificate in Construction Engineering and Management

    E-Print Network [OSTI]

    Gelfond, Michael

    , Sustainable construction methods and materials in buildings and infrastructure systems, Engineering costGraduate Certificate in Construction Engineering and Management WHY DO I NEED THIS GRADUATE The department offers a 12-hour Graduate Certificate in Construction Engineering and Management. The coursework

  17. ITEM #10(a) Proposed Academic Certificate Program

    E-Print Network [OSTI]

    O'Toole, Alice J.

    ITEM #10(a) Proposed Academic Certificate Program Title: Graduate Certificate in Product Lifecycle to an order-centric view in the 90s to product-centric view today. As product lifecycles shrink, innovation. The product lifecycle perspective becomes more important because it provides a holistic view across disparate

  18. Roundtable on Sustainable Biofuels Certification Readiness Study

    E-Print Network [OSTI]

    Roundtable on Sustainable Biofuels Certification Readiness Study: Hawai`i Biofuel Projects Prepared 12.1 Deliverable Bioenergy Analyses Prepared by Hawai`i Biofuel Foundation And NCSI Americas Inc agency thereof. #12;1 RSB Certification Readiness Study: Hawaii Biofuel Projects Prepared For Hawaii

  19. LOW TECHNOLOGY HIGH TRITIUM BREEDING BLANKET CONCEPT* Y. Gohar, C. C. Baker, D. L. Smith, M. C. Billone, Y. S. Cha,

    E-Print Network [OSTI]

    Harilal, S. S.

    of beryllium and 6 cm of solid breeder (LI20, LIA102, or LiASi04) both with a 0.8 density factor. This blanket the chances for water-breeder interaction. This improves the safety and environmental aspects of the blanketLOW TECHNOLOGY HIGH TRITIUM BREEDING BLANKET CONCEPT* Y. Gohar, C. C. Baker, D. L. Smith, M. C

  20. SOLID BREEDER BLANKET OPTION FOR THE ITER CONCEPTUAL DESIGN* Y. Cohar, H. Attaya, M.C. Billone, P. Finn, S. Majumdar, L.R. Turner

    E-Print Network [OSTI]

    Raffray, A. René

    SOLID BREEDER BLANKET OPTION FOR THE ITER CONCEPTUAL DESIGN* Y. Cohar, H. Attaya, M.C. Billone, P in this paper. lntroduction A solid-breeder water-cooled blanket option was developed for ITER based lithium-6 enrichment reduces the solid breeder volume required in the blanket and the total tritium

  1. Fractal Superconductivity near Localization Threshold

    E-Print Network [OSTI]

    Fominov, Yakov

    Fractal Superconductivity near Localization Threshold Mikhail Feigel'man Landau Institute, Moscow-electron states are extended but fractal and populate small fraction of the whole volume How BCS theory should be modified to account for eigenstates fractality ? #12;Mean-Field Eq. for Tc #12;#12;3D Anderson model: = 0

  2. MACHINE MONITORING USING PROBABILITY THRESHOLDS

    E-Print Network [OSTI]

    Pollock, Stephen

    MACHINE MONITORING USING PROBABILITY THRESHOLDS AND SYSTEM OPERATING CHARACTERISTICS Stephen M and Jeffrey M. Alden G.M. R&D Center Warren, MI 48090 IOE Tech Report 95-14 #12;1. Introduction We a discrete-part production machine, with the objective of effectively determining when to shut the machine

  3. Reference material manufacture and certification for the AVNG

    SciTech Connect (OSTI)

    Hauck, Danielle K [Los Alamos National Laboratory; Mac Arthur, Duncan [Los Alamos National Laboratory; Thron, Jonathan L [Los Alamos National Laboratory; Livke, Alexander [VNIIEF; Kondratov, Sergey [VNIIEF; Razinkov, Sergey [VNIIEF

    2010-01-01T23:59:59.000Z

    Testing and demonstration of any radiation measurement system requires the use of appropriate radioactive sources. The AVNG implementation that we describe is an attribute measurement system built by RFNC - VNIIEF in Sarov, Russia. The AVNG detects neutron and gamma radiation signatures and displays the three unclassified attributes of 'plutonium presence,' 'plutonium mass > 2 kg,' and 'plutonium isotopic ratio ({sup 240}Pu to {sup 239}Pu) < 0.1.' The AVNG was tested using a number of reference material (RM) sources with masses and isotopic ratios above and below these thresholds. The AVNG was demonstrated in June 2009 using several of these sources in addition to detector calibration sources. Since the AVNG was designed to measure multi-kg plutonium sources, the RM was manufactured specifically for use with this system. In addition, the RM was used to test the thresholds in the AVNG, so the size and composition of each RM was certified prior to use. In this presentation, we will describe the various steps in the manufacture and certification of these RM sources.

  4. Quick Guide: Renewable Energy Certificates (RECs) (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-07-01T23:59:59.000Z

    Guide for Federal agencies considering renewable energy certificate (REC) purchases to fulfill Federal renewable energy requirements.

  5. Compact Proof Certificates For Linear Logic Kaustuv Chaudhuri

    E-Print Network [OSTI]

    Chaudhuri, Kaustuv

    Compact Proof Certificates For Linear Logic Kaustuv Chaudhuri INRIA, France http://kaustuv.chaudhuri

  6. Fusion Engineering and Design 48 (2000) 371378 Blanket system selection for the ARIES-ST

    E-Print Network [OSTI]

    California at San Diego, University of

    2000-01-01T23:59:59.000Z

    ) is to investigate the attractiveness of a low-aspect-device as the confinement concept for a fusion power plant-ST is investigating the attractive- ness of using an ST configuration as plasma source for a commercial power plant, a 20 cm shield is used. There is no breeding blanket on the in board (IB) of the power plant. Therefore

  7. Fusion Engineering and Design 4950 (2000) 689695 ARIES-ST breeding blanket design and analysis

    E-Print Network [OSTI]

    Pulsifer, John

    2000-01-01T23:59:59.000Z

    -cooled ferritic steel structures. The main features of the blanket design are summarized here together properties, as well as the compatibility with ferritic steels and vanadium alloys for this liquid metal-DEMO design include extension of the power handling capability of the first wall by using an advanced ODS

  8. U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING , M. Sawan4

    E-Print Network [OSTI]

    Abdou, Mohamed

    U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING M. Abdou1 , D. Sze2 , C. Wong3 , M. Sawan4 , A. Ying1 , N. B. Morley1 , S. Malang5 1 UCLA Fusion Engineering Sciences, Los Angeles, CA, abdou

  9. First-wall and blanket engineering development for magnetic-fusion reactors

    SciTech Connect (OSTI)

    Baker, C.; Herman, H.; Maroni, V.; Turner, L.; Clemmer, R.; Finn, P.; Johnson, C.; Abdou, M.

    1981-01-01T23:59:59.000Z

    A number of programs in the USA concerned with materials and engineering development of the first wall and breeder blanket systems for magnetic-fusion power reactors are described. Argonne National Laboratory has the lead or coordinating role, with many major elements of the research and engineering tests carried out by a number of organizations including industry and other national laboratories.

  10. Scientific Framework for Advancing Blanket/FW/Tritium Fuel Cycle Systems

    E-Print Network [OSTI]

    Ying, Sergey Smolentsev, and Neil Morley University of California, Los Angeles 1 (Greenwald Gaps G11, G that blankets designed with current knowledge of phenomena and data will not work ­ The source of this problem instabilities that affect transport phenomena (Heat , T, Corrosion) Base flow strongly altered leading

  11. NEUTRONICS ANALYSIS OF A SELF-COOLED BLANKET FOR A LASER FUSION PLANT WITH MAGNETIC DIVERSION

    E-Print Network [OSTI]

    Raffray, A. René

    NEUTRONICS ANALYSIS OF A SELF-COOLED BLANKET FOR A LASER FUSION PLANT WITH MAGNETIC DIVERSION M. INTRODUCTION The High Average Power Laser (HAPL) program is carrying out a coordinated effort to develop laser accommodate the ion and photon threat spectra from the fusion micro-explosion over its required lifetime

  12. Fusion Engineering and Design 46 (1999) 159175 Engineering design of the ITER blanket and relevant

    E-Print Network [OSTI]

    Raffray, A. René

    levels of nuclear radiation. In combination with the thick vessel, the blanket provides the shielding methods defined the construction path which has been tested in prototypes. The main body is built. Prototypes of the module attachment have been built and are under integrated tests. © 1999 Elsevier Science S

  13. High Performance PbLi Blanket M. S. Tillacka and S. Malangb

    E-Print Network [OSTI]

    Tillack, Mark

    concept based on ferritic steel as structural material using helium to cool the first wall is achievable, allowing either an advanced Rankine steam cycle or a closed-cycle helium gas turbine (Brayton with solid breeder blankets irrespective of the structural material used, because the maximum breeder

  14. June 20-21, 2005 Overview of Chamber/Blanket Work

    E-Print Network [OSTI]

    Raffray, A. René

    . A baseline case with minimum risk in getting there based on present day material development and knowledge of what could be gained with a more ambitious material R&D program. · Three blanket options 1. Self = 0.89 - hturb = 0.93 - Effect.recup = 0.95 I. 3 Compressor stages (with 2 intercoolers) + 1 turbine

  15. March 21-22, 2006 HAPL meeting, ORNL Status of Chamber and Blanket Effort

    E-Print Network [OSTI]

    Raffray, A. René

    Spectra Spectra in a 10.75 m Chamber #12;March 21-22, 2006 HAPL meeting, ORNL 5 Smoothness of Plot of Ion Plates Estimated for Cone-Shaped Chamber · Duck bill configuration assumed for the equatorial ion dumpMarch 21-22, 2006 HAPL meeting, ORNL 1 Status of Chamber and Blanket Effort A. René Raffray UCSD

  16. Passive safety in a helium-cooled tritium breeding blanket with steel structure

    SciTech Connect (OSTI)

    Crosswait, K.M.; Meyer, J.E. (MIT Plasma Fusion Center, Cambrige, MA (United States))

    1993-06-01T23:59:59.000Z

    Helium is attractive for use as a fusion blanket coolant for a number of reasons. It is neutronically and chemically inert, nonmagnetic, and will not change phase during any off-normal or accident condition. A significant disadvantage of helium, however, is its low density and volumetric heat capacity. This disadvantage manifests itself most clearly during undercooling accidents such as a loss of coolant accident (LOCA) or a loss of flow accident (LOFA). This paper proposes a new helium-cooled, tritium breeding blanket concept which uses a metallic structure, and which performs significantly better during such accidents than related designs. The proposed blanket uses modified, reduced-activation HT-9 steel as a structural material and is designed for neutron wall loads exceeding 4 MW/m[sup 2]. This concept uses novel features such as: (1) a [open quotes]beryllium-joint[close quotes] design which allows beryllium to be used to conduct heat away from the first wall, while accomodating swelling of the beryllium, and (2) a shield cooled by naturally circulating water. These features help the blanket passively withstand a worst-case undercooling accident scenario.

  17. European ceramic B.I.T. blanket for DEMO: Recent development for the zirconate version

    SciTech Connect (OSTI)

    Bielak, B.; Eid, M.; Fuetterer, M. [DRN/DMT/SERMA, Gif-sur-Yvette (France)

    1994-12-31T23:59:59.000Z

    Within the framework of the European test-blanket program, CEA and ENEA are jointly developing a DEMO-relevant, helium-cooled, Breeder-Inside-Tube (BIT) ceramic blanket. Two ceramics are possible breeder material candidate: LiAlO{sub 2} and Li{sub 2}ZrO{sub 3}. Despite the design has been originally developed for aluminate, the CEA has recently focused its work on zirconate. This concept blanket segments are made by a directly-cooled vacuum-tight steel box which contains banana-shaped poloidal breeder modules arranged in rows (6 rows in an outboard segment and 4 rows in an inboard one). A breeder module consists of a pressure vessel containing a bundle of breeder rods surrounded by baffles. Each one of the rods is made-up of a steel tube containing a stack of annular pellets of sintered lithium-zirconate, through which flows helium (the tritium purge gas). The thermo-mechanical analysis has shown that the thermal gradient in the ceramics can be kept at acceptable levels despite the poorer out-of-pile thermo-mechanical properties of zirconate compared to aluminate. Moreover, the neutronic analysis has shown that, besides the maintained tritium-breeding self-sufficiency capability of this blanket, the lower lithium burn-up could be an indication that the zirconate characteristics remains more stable after long term irradiation (i.e., close to the end-of-life fluence of 5 MWa/m{sup 2}).

  18. Breeding channel for the ITER blanket with lithium-lead eutectic Li17Pb83

    SciTech Connect (OSTI)

    Danilov, I.; Sidorov, A.; Strebkov, Y. [ENTEK-RDIPE, Moscow (Russian Federation)] [and others

    1994-12-31T23:59:59.000Z

    The report contains some features of using Li{sub 17}Pb{sub 83} eutectic as breeder for ITER fusion reactor. The use of eutectic in the ITER blanket as breeding material has its own advantages. Results of improvements of lithium-lead blanket channels are described in the report. Design analysis, operation conditions of breeding channels, technique of filling up with eutectic and tritium recovery problems are considered. The eutectic detritization is performed outside and also inside the reactor without removing the eutectic from the blanket. The report contains a survey of investigations of eutectic and channel structure thermal-mechanical behavior, that was the cause of the up to date channel design improvement. The first stage of the thermal and mechanical tests results in change of the channel structure to the sectioning one. The comprehensive tests of the channel models including thermo-mechanical effect of eutectic on the channel structure at the different operating conditions of the channel including the accident ones, the techniques for handling with eutectic etc. to justify the design decisions concerning the breeding eutectic blanket. Suggestions for the further development of the channel design are presented.

  19. Study of the effects of corrugated wall structures due to blanket modules around ICRH antennas

    SciTech Connect (OSTI)

    Dumortier, Pierre; Louche, Fabrice; Messiaen, André; Vervier, Michel [LPP-ERM/KMS, EURATOM-Belgian State Association, TEC partner, B-1000 Brussels (Belgium)

    2014-02-12T23:59:59.000Z

    In future fusion reactors, and in ITER, the first wall will be covered by blanket modules. These blanket modules, whose dimensions are of the order of the ICRF wavelengths, together with the clearance gaps between them will constitute a corrugated structure which will interact with the electromagnetic waves launched by ICRF antennas. The conditions in which the grooves constituted by the clearance gaps between the blanket modules can become resonant are studied. Simple analytical models and numerical simulations show that mushroom type structures (with larger gaps at the back than at the front) can bring down the resonance frequencies, which could lead to large voltages in the gaps between the blanket modules and perturb the RF properties of the antenna if they are in the ICRF operating range. The effect on the wave propagation along the wall structure, which is acting as a spatially periodic (toroidally and poloidally) corrugated structure, and hence constitutes a slow wave structure modifying the wall boundary condition, is examined.

  20. Experimental study of the MHD flow in a prototypic inlet manifold section of the DCLL blanket

    E-Print Network [OSTI]

    Abdou, Mohamed

    . The MHD flow patterns and their associated transport properties that result from the interaction between Lithium (DCLL) blanket concept. A series of experiments is carried out in order to understand stacked in the direction the magnetic field lines. For values of the interaction parameter , the flow

  1. M.I.T. LMFBR Blanket Physics Project : final summary report

    E-Print Network [OSTI]

    Driscoll, Michael J.

    1983-01-01T23:59:59.000Z

    This is a final summary report on an experimental and analytical program for the investigation of LMFBR blanket characteristics carried out at M.I. T. in the period 1969-1983. During this span of time, work was carried out ...

  2. Fusion Engineering and Design 4950 (2000) 709717 Helium-cooled refractory alloys first wall and blanket

    E-Print Network [OSTI]

    Ghoniem, Nasr M.

    2000-01-01T23:59:59.000Z

    impurity control, and mechanical, nuclear and thermal hydraulics design, and waste disposal, tritium and safety design. Systems study results show that at a closed cycle gas turbine (CCGT) gross thermal team, we performed the preliminary design of the W-alloy FW/blanket concept. We projected

  3. A high converter concept for fuel management with blanket fuel assemblies in boiling water reactors

    SciTech Connect (OSTI)

    Martinez-Frances, N.; Timm, W.; Rossbach, D. [AREVA, AREVA NP, Erlangen (Germany)

    2012-07-01T23:59:59.000Z

    Studies on the natural Uranium saving and waste reduction potential of a multiple-plant BWR system were performed. The BWR High Converter system should enable a multiple recycling of MOX fuel in current BWR plants by introducing blanket fuel assemblies and burning Uranium and MOX fuel separately. The feasibility of Uranium cores with blankets and full-MOX cores with Plutonium qualities as low as 40% were studied. The power concentration due to blanket insertion is manageable with modern fuel and acceptable values for the thermal limits and reactivity coefficients were obtained. While challenges remain, full-MOX cores also complied with the main design criteria. The combination of Uranium and Plutonium burners in appropriate proportions could enable obtaining as much as 40% more energy out of Uranium ore. Moreover, a proper adjustment of blanket average stay and Plutonium qualities could lead to a system with nearly no Plutonium left for final disposal. The achievement of such goals with current light water technology makes the BWR HC concept an attractive option to improve the fuel cycle until Gen-IV designs are mature. (authors)

  4. TRITIUM ANALYSIS OF A WATER-COOLED SOLID BREEDER BLANKET FOR ITER*

    E-Print Network [OSTI]

    Abdou, Mohamed

    .A. Abdou Mechanical,Aerospace and Nuclear Engineering Department University of California, Los Angeles Los at reduced power level. Key parameters affecting the kinetics of the tritium release and the inventory. The blanket uses beryllium for neutron multiplication and lithium-base ceramic such as oxide or orthosilicate

  5. Guidelines for developing certification programs for newly generated TRU waste

    SciTech Connect (OSTI)

    Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S.; Geoffrion, R.R.

    1983-05-01T23:59:59.000Z

    These guidelines were prepared with direction from the US Department of Energy (DOE) Transuranic (TRU) Waste Management Program in support of the DOE effort to certify that newly generated TRU wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The guidelines provide instructions for generic Certification Program preparation for TRU-waste generators preparing site-specific Certification Programs in response to WIPP requirements. The guidelines address all major aspects of a Certification Program that are necessary to satisfy the WIPP Waste Acceptance Criteria and their associated Compliance Requirements and Certification Quality Assurance Requirements. The details of the major element of a Certification Program, namely, the Certification Plan, are described. The Certification Plan relies on supporting data and control documentation to provide a traceable, auditable account of certification activities. Examples of specific parts of the Certification Plan illustrate the recommended degree of detail. Also, a brief description of generic waste processes related to certification activities is included.

  6. Checkerboard seed-blanket thorium fuel core concepts for heavy water moderated reactors

    SciTech Connect (OSTI)

    Bromley, B.P.; Hyland, B. [Atomic Energy of Canada Limited, Chalk River Laboratories, 1 Plant Road, Chalk River, Ontario, K0J 1J0 (Canada)

    2013-07-01T23:59:59.000Z

    New reactor concepts to implement thorium-based fuel cycles have been explored to achieve maximum resource utilization. Pressure tube heavy water reactors (PT-HWR) are highly advantageous for implementing the use of thorium-based fuels because of their high neutron economy and on-line re-fuelling capability. The use of heterogeneous seed-blanket core concepts in a PT-HWR where higher-fissile-content seed fuel bundles are physically separate from lower-fissile-content blanket bundles allows more flexibility and control in fuel management to maximize the fissile utilization and conversion of fertile fuel. The lattice concept chosen was a 35-element bundle made with a homogeneous mixture of reactor grade Pu (about 67 wt% fissile) and Th, and with a central zirconia rod to help reduce coolant void reactivity. Several checkerboard heterogeneous seed-blanket core concepts with plutonium-thorium-based fuels in a 700-MWe-class PT-HWR were analyzed, using a once-through thorium (OTT) cycle. Different combinations of seed and blanket fuel were tested to determine the impact on core-average burnup, fissile utilization, power distributions, and other performance parameters. It was found that various checkerboard core concepts can achieve a fissile utilization that is up to 26% higher than that achieved in a PT-HWR using more conventional natural uranium fuel bundles. Up to 60% of the Pu is consumed; up to 43% of the energy is produced from thorium, and up to 303 kg/year of Pa-233/U-233/U-235 are produced. Checkerboard cores with about 50% of low-power blanket bundles may require power de-rating (65% to 74%) to avoid exceeding maximum limits for channel and bundle powers and linear element ratings. (authors)

  7. Status of EC solid breeder blanket designs and R&D for DEMO fusion reactors

    SciTech Connect (OSTI)

    Dalle Donne, M. [INR, Karlsruhe (Russian Federation); Anziedi, L.A. [C.R.E., Franscati (Italy); Kwast, H. [ECN, Petten (Netherlands)] [and others

    1994-12-31T23:59:59.000Z

    In the framework of the European Community Fusion Technology Program four blanket concepts for a DEMO reactor are being investigated. DEMO is the next step after ITER. It should ensure tritium self-sufficiency and operate at coolant temperatures high enough to have a reasonable plant efficiency. Further requirements have been specified for the four concepts, namely an average neutron wall load of 2.2 MW/m{sup 2}, a blanket lifetime of 20000 hours and the capability of the blanket segment to withstand the forces caused by a rapid distribution of the plasma current (20 MA to zero in 20 ms), so that after the disruption the segment can still allow a comparison of the various options, in view of reducing this number to two in 1995 and to design and develop modules and articles representative of the chosen blankets to be tested in ITER. The present paper deals with two solid breeder concepts. They have many features in common: both use high pressure helium as coolant and helium to purge the tritium from the breeder material, martensitic steel as structural material and beryllium as neutron multiplier. The configuration of the two blankets are however different: in the B.I.T. (Breeder Inside Tube) concept the breeder material is LiAlO{sub 2} or LiZrO{sub 3} in the form of annular pellets contained in tubes surrounded by beryllium blocks, the coolant helium being outside the tubes, whereas in the B.O.T. (Breeder out of Tube) the breeder and multiplier material are Li{sub 4}SiO{sub 4} and beryllium pebbles forming a mixed bed placed outside the tubes containing the coolant helium.

  8. Reduced lasing threshold from organic dye microcavities

    E-Print Network [OSTI]

    Akselrod, G. M.

    We demonstrate an unexpected tenfold reduction in the lasing threshold of an organic vertical microcavity under subpicosecond optical excitation. In contrast to conventional theory of lasing, we find that the lasing threshold ...

  9. Compositional threshold for Nuclear Waste Glass Durability

    SciTech Connect (OSTI)

    Kruger, Albert A. [Pacific Northwest National Lab., Richland, WA (United States); Farooqi, Rahmatullah [Pohang Univ. of Science and Technology, (Korea, Republic of); Hrma, Pavel R. [Pacific Northwest National Lab., Richland, WA (United States), Pohang Univ. of Science and Technology, (Korea, Republic of)

    2013-04-24T23:59:59.000Z

    Within the composition space of glasses, a distinct threshold appears to exist that separates "good" glasses, i.e., those which are sufficiently durable, from "bad" glasses of a low durability. The objective of our research is to clarify the origin of this threshold by exploring the relationship between glass composition, glass structure and chemical durability around the threshold region.

  10. CERTIFICATE

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItem NotEnergy,ARMForms About Batteries BatteriesCAES Home Home AboutCBFOCERN

  11. Application for SAS Certificate Advanced Statistics

    E-Print Network [OSTI]

    Dahl, David B.

    Application for SAS Certificate Advanced Statistics ___________________________________________________________________________________ Student Signature _________________________________________ Date I am a Statistics Major at Brigham Young of Statistics to access my academic information. Brigham Young University Department of Statistics offers

  12. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-09-09T23:59:59.000Z

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

  13. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-12-14T23:59:59.000Z

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

  14. STATE OF CALIFORNIA CERTIFICATE OF COMPLIANCE

    E-Print Network [OSTI]

    STATE OF CALIFORNIA CERTIFICATE OF COMPLIANCE CEC-RWH-1C (Revised 08/09) CALIFORNIA ENERGY Project Name: Climate Zone: Conditioned Floor Area: Project Address: Date: General Information Building Warehouse space is Efficiency Regulations (Title 20) for walk

  15. Puerto Rico- Solar and Wind Contractor Certification

    Broader source: Energy.gov [DOE]

    In October 2008, the Energy Affairs Administration (EAA) of Puerto Rico adopted regulations for the certification of photovoltaic (PV) systems and installers in response to the passing of Act No....

  16. DOCTORATE & CERTIFICATE of the Graduate Academy

    E-Print Network [OSTI]

    Greifswald, Ernst-Moritz-Arndt-Universität

    DOCTORATE & CERTIFICATE of the Graduate Academy Own presen tations Other presen tations Key quali within the Graduate Academy Graduiertenakademie #12;Name of the Graduate Academy of the Ernst-Moritz-Arndt-University of Greifswald In addition to your own doctoral

  17. Home Energy Professional Certifications (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-11-01T23:59:59.000Z

    As the weatherization and home energy upgrade industries expand and gain recognition, the need for a qualified workforce becomes more apparent. The certification component of the Guidelines project was designed to create meaningful and lasting careers for weatherization workers. Intended for experienced home energy professionals, the four new certifications focus on the most common jobs in the industry: energy auditor, retrofit installer technician, crew leader, and quality control inspector.

  18. Certification plan for reactor analysis computer codes

    SciTech Connect (OSTI)

    Toffer, H.; Crowe, R.D.; Schwinkendorf, K.N. [Westinghouse Hanford Co., Richland, WA (United States); Pevey, R.E. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1990-01-01T23:59:59.000Z

    A certification plan for reactor analysis computer codes used in Technical Specifications development and for other safety and production support calculations has been prepared. An action matrix, checklists, a time schedule, and a resource commitment table have been included in the plan. These items identify what is required to achieve certification of the codes, the time table that this will be accomplished on, and the resources needed to support such an effort.

  19. Breeder-in-tube design for a helium-cooled Li/sub 2/O tokamak blanket

    SciTech Connect (OSTI)

    Billone, M.C.; Jung, J.; Liu, Y.Y.; Smith, D.L.

    1986-01-01T23:59:59.000Z

    Of the solid breeder designs considered in the Blanket Comparison and Selection Study (BCSS), the lithium oxide breeder with helium coolant and ferritic steel (HT-9) structural material received the highest overall ranking for both tokamak and tandem mirror systems in terms of engineering, economics, safety, and R and D requirements. The BCSS blanket surrounding the fusion plasma consists of a number of thin breeder plates externally cooled by flowing helium and internally purged of tritium by a separate helium stream. A detailed review of this design indicated that significant improvements would be realized in the areas of tritium breeding, blanket thickness, blanket energy multiplication, power-conversion efficiency, breeder temperature window, and geometrical integrity of the coolant and purge paths by using a neutron multiplier (beryllium), a higher temperature structural material (vanadium-based alloy), and a tube geometry. The neutronics, thermal-hydraulics, tritium recovery, and structural performance characteristics of this innovative solid breeder design are discussed in this paper.

  20. Certification of the Cessna 152 on 100% ethanol

    SciTech Connect (OSTI)

    Shauck, M.E.; Zanin, M.G.

    1997-12-31T23:59:59.000Z

    In June 1996, the Renewable Aviation Fuels Development Center (RAFDC) at Baylor University in Waco, Texas, received a Supplemental Type Certificate (STC) for the use of 100% ethanol as a fuel for the Cessna 152, the most popular training aircraft in the world. This is the first certification granted by the Federal Aviation Administration (FAA) for a non-petroleum fuel. Certification of an aircraft on a new fuel requires a certification of the engine followed by a certification of the airframe/engine combination. This paper will describe the FAA airframe certification procedure, the tests required and their outcome using ethanol as an aviation fuel in a Cessna 152.

  1. Axially staggered seed-blanket reactor-fuel-module construction. [LWBR

    DOE Patents [OSTI]

    Cowell, G.K.; DiGuiseppe, C.P.

    1982-10-28T23:59:59.000Z

    A heterogeneous nuclear reactor of the seed-blanket type is provided wherein the fissile (seed) and fertile (blanket) nuclear fuels are segregated axially within each fuel element such that fissile and fertile regions occur in an alternating pattern along the length of the fuel element. Further, different axial stacking patterns are used for the fuel elements of at least two module types such that when modules of different types are positioned adjacent to one another, the fertile regions of the modules are offset or staggered. Thus, when a module of one type is surrounded by modules of the second type the fertile regions thereof will be surrounded on all sides by fissile material. This provides enhanced neutron communication both radially and axially, thereby resulting in greater power oscillation stability than other axial arrangements.

  2. Tritium Recovery from Solid Breeder Blanket by Water Vapor Addition to Helium Sweep Gas

    SciTech Connect (OSTI)

    Kawamura, Yoshinori; Iwai, Yasunori; Nakamura, Hirofumi; Hayashi, Takumi; Yamanishi, Toshihiko; Nishi, Masataka [Japan Atomic Energy Research Institute (Japan)

    2005-07-15T23:59:59.000Z

    In the solid breeder blanket of fusion reactor, bred tritium is planned to be extracted from the blanket as HT by passing of H{sub 2}-added sweep gas in general. In that case, tritium leakage by permeation to coolant can not be ignored. So, the application of H{sub 2}O-added sweep gas is discussed, with which tritium leakage to coolant can be much reduced. As the result of discussion, H{sub 2}O-added sweep gas is probable method of tritium recovery. For the further detailed discussion, it is important to enrich the data correlated to the interaction of H{sub 2}, H{sub 2}O, breeder, multiplier and structures.

  3. Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module

    SciTech Connect (OSTI)

    Merrill, Brad; Reyes, Susana; Sawan, Mohamed; Wong, Clement

    2006-07-01T23:59:59.000Z

    The US is proposing a prototype of a dual coolant liquid lead-lithium (DCLL) DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER Test Blanket Module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER International Team (IT) to address specific reactor safety concerns, such as VV pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system, and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.

  4. Two-dimensional TBR calculations for conceptual compact reversed-field pinch reactor blanket

    SciTech Connect (OSTI)

    Davidson, J.W.; Battat, M.E.; Dudziak, D.J.

    1985-01-01T23:59:59.000Z

    A detailed two-dimensional nucleonic analysis was performed for a conceptual first wall, blanket, and shield design for the Compact Reversed-Field Pinch Reactor. The design includes significant two-dimensional aspects presented by the limiter, vacuum ducts, and coolant manifolds; these aspects seriously degrade the tritium-breeding reaction (TBR) predicted by one-dimensional calculations. A range of design change to increase the TBR were investigated within the two-dimensional analysis. The results of this investigation indicated that an adequate TBR could be achieved with a thinner copper first wall, a /sup 6/Li enrichment near 90%, the proper selection of reflector, and a small addition to the blanket thickness, determined by the one-dimensional analysis.

  5. Annular core liquid-salt cooled reactor with multiple fuel and blanket zones

    DOE Patents [OSTI]

    Peterson, Per F.

    2013-05-14T23:59:59.000Z

    A liquid fluoride salt cooled, high temperature reactor having a reactor vessel with a pebble-bed reactor core. The reactor core comprises a pebble injection inlet located at a bottom end of the reactor core and a pebble defueling outlet located at a top end of the reactor core, an inner reflector, outer reflector, and an annular pebble-bed region disposed in between the inner reflector and outer reflector. The annular pebble-bed region comprises an annular channel configured for receiving pebble fuel at the pebble injection inlet, the pebble fuel comprising a combination of seed and blanket pebbles having a density lower than the coolant such that the pebbles have positive buoyancy and migrate upward in said annular pebble-bed region toward the defueling outlet. The annular pebble-bed region comprises alternating radial layers of seed pebbles and blanket pebbles.

  6. Feasibility of recoil enhanced tritium release from fusion blankets containing solid lithium compounds 

    E-Print Network [OSTI]

    Palmrose, Donald Edwin

    1986-01-01T23:59:59.000Z

    FEASIBILITY OF RECOIL ENHANCED TRITIUM RELEASE FROM FUSION BLANXETS CONTAINING SOLID LITHIUM COMPOUNDS A Thesis by DONALD EDWIN PALMROSE Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE May 1986 Major Subject: Nuclear Engineering 1986 DONALD EDIJIi4 PAL;lROSE ALL RIGHTS RESERVED FEASIBILITY OF RECOIL ENHANCED TRITIUM RELEASE FROM FUSION BLANKETS CONTAINING SOLID LITHIUM COMPOUNDS A Thesis...

  7. The petrology and petrography of sediments from the Sigsbee blanket, Yucatan Shelf, Mexico 

    E-Print Network [OSTI]

    Williams, Joseph Delano

    1963-01-01T23:59:59.000Z

    by; {Chairman of Committee (Head of Department May, 1963 858I18 ABSTRACT The Sigsbse blanket 1 ~ ~ lithologically distinct unit of the Holocene to Recent sediment mantle which covers the outer shag and continental elope provinces... of the Yucatan Shelf. A detailed petrographic study has revealed ChaC the unit is composed dominantly of planktonic lutite with varying percentages of calcareous pellets, ooids lithic fragments, non-skeletal aggregates, algal fragment ~, tests of benthonic...

  8. Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

    SciTech Connect (OSTI)

    Ware, A.G.; Longhurst, G.R.

    1981-12-01T23:59:59.000Z

    This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available.

  9. Target/blanket conceptual design for the Los Alamos ATW concept

    SciTech Connect (OSTI)

    Ames, K. [ed.] [ed.; Cappiello, M.; Ireland, J.; Sapir, J.; Farnum, G.

    1992-01-01T23:59:59.000Z

    The Los Alamos Accelerator Transmutation of Waste (ATW) concept has many potential applications that include defense waste transmutation, defense material production (i.e., tritium and {sup 238}Pu), and the transmutation of hazardous nuclear wastes from commercial nuclear reactors (fission products and actinides). A more advanced long-term Los Alamos effort is investigating the potential of an accelerator- driven system to produce fission energy with a minimal nuclear waste stream. All applications employ a high-energy (800- to 1600-MeV), high-current (25--250 mA) proton linear accelerator as the driver. In this report, we discuss only the target/blanket conceptual design for the commercial nuclear waste application. A conceptual design for the target/blanket of the Los Alamos ATW concept has been presented. The neutronics, mechanical design, and heat transfer have been investigated in some detail for the base-case design. Much more work needs to be done, but at this point it appears that the design is feasible and will approach the design goal of supporting two commercial power reactors with each target/blanket module.

  10. Neutronic and thermal calculation of blanket for high power operating condition of fusion reactor

    SciTech Connect (OSTI)

    Sagawa, H.; Shimakawa, S.; Kuroda, T. [Oarai Research Establishement of JAERI, Ibaraki (Japan)] [and others

    1994-12-31T23:59:59.000Z

    Internal (breeding region) structures of ceramic breeder blanket to accommodate high power operating conditions such as a DEMO reactor have been investigated. The conditions considered here are the maximum neutron wall load of 2.8 MW/m{sup 2} at outboard midplane corresponding to a fusion power of 3.0 GW and the coolant temperature of 200{degrees}C. Structure of a blanket is based on the layered pebble bed concept, which has been proposed by Japan since the ITER CDA. Lithium oxide with 50% enriched {sup 6}Li is used in a shape of small spherical pebbles which are filled in a 316SS can avoid its compatibility issue with Be. Beryllium around the breeder can is filled also in a shape of spherical pebbles which works not only as a neutron multiplier but also as a thermal resistant layer to maintain breeder temperature for effective in-situ tritium recovery. Diameters and packing fractions of both pebbles are {<=} 1 mm and 65%, respectively. A layer of block Be between cooling panels is introduced as a neutron multiplier (not as the thermal resistant layer) to enhance tritium breeding performance. Inlet temperature of water coolant is 200{degrees}C to meet the high temperature conditioning requirement to the first wall which is one of walls of the blanket vessel. Neutronics calculations have been carried out by one-dimensional transport code, and thermal calculations have also been carried out by one-dimensional slab code.

  11. Assessment of First Wall and Blanket Options with the Use of Liquid Breeder

    SciTech Connect (OSTI)

    Wong, C.P.C.; Malang, S.; Sawan, M. (and others)

    2005-04-15T23:59:59.000Z

    As candidate blanket concepts for a U.S. advanced reactor power plant design, with consideration of the time frame for ITER development, we assessed first wall and blanket design concepts based on the use of reduced activation ferritic steel as structural material and liquid breeder as the coolant and tritium breeder. The liquid breeder choice includes the conventional molten salt Li{sub 2}BeF{sub 4} and the low melting point molten salts such as LiBeF{sub 3} and LiNaBeF{sub 4} (FLiNaBe). Both self-cooled and dual coolant molten salt options were evaluated. We have also included the dual coolant leadeutectic Pb-17Li design in our assessment. We take advantage of the molten salt low electrical and thermal conductivity to minimize impacts from the MHD effect and the heat losses from the breeder to the actively cooled steel structure. For the Pb-17Li breeder we employ flow channel inserts of SiC{sub f}/SiC composite with low electrical and thermal conductivity to perform respective insulation functions. We performed preliminary assessments of these design options in the areas of neutronics, thermal-hydraulics, safety, and power conversion system. Status of the R and D items of selected high performance blanket concepts is reported. Results from this study will form the technical basis for the formulation of the U.S. ITER test module program and corresponding test plan.

  12. Multirecycling of Plutonium from LMFBR Blanket in Standard PWRs Loaded with MOX Fuel

    SciTech Connect (OSTI)

    Sonat Sen; Gilles Youinou

    2013-02-01T23:59:59.000Z

    It is now well-known that, from a physics standpoint, Pu, or even TRU (i.e. Pu+M.A.), originating from LEU fuel irradiated in PWRs can be multirecycled also in PWRs using MOX fuel. However, the degradation of the isotopic composition during irradiation necessitates using enriched U in conjunction with the MOX fuel either homogeneously or heterogeneously to maintain the Pu (or TRU) content at a level allowing safe operation of the reactor, i.e. below about 10%. The study is related to another possible utilization of the excess Pu produced in the blanket of a LMFBR, namely in a PWR(MOX). In this case the more Pu is bred in the LMFBR, the more PWR(MOX) it can sustain. The important difference between the Pu coming from the blanket of a LMFBR and that coming from a PWR(LEU) is its isotopic composition. The first one contains about 95% of fissile isotopes whereas the second one contains only about 65% of fissile isotopes. As it will be shown later, this difference allows the PWR fed by Pu from the LMFBR blanket to operate with natural U instead of enriched U when it is fed by Pu from PWR(LEU)

  13. Computational Science and Engineering Certification for Computer Science

    E-Print Network [OSTI]

    Gilbert, Matthew

    Computational Science and Engineering Certification for Computer Science The Computational Science credential only available to students currently enrolled in the Computer Science undergraduate degree program that are distinct from already-required coursework. To receive a certificate in "Computational Science

  14. Computational Science and Engineering Certification for General Engineering

    E-Print Network [OSTI]

    Gilbert, Matthew

    Computational Science and Engineering Certification for General Engineering The Computational that are distinct from already- required coursework. To receive a certificate in "Computational Science on the Computational Science and Engineering website: http://cse.illinois.edu/directory/faculty-affiliates. *** List

  15. Paper achieves forest certification An Independent Paper plc product story

    E-Print Network [OSTI]

    Paper achieves forest certification An Independent Paper plc product story Edited certification: News from Independent Paper plc http://www.printingtalk.com/news/inp/inp119.html 1 of 1 11

  16. Grant County PUD- EnergyStar New Home Certification Program

    Broader source: Energy.gov [DOE]

    Grant County PUD offers incentives to qualifying customers through the Energy Star Home Certification Program. The Energy Star certification is available for both new site-built homes and new...

  17. Optimization Online - Sequential Threshold Control in Descent ...

    E-Print Network [OSTI]

    Igor Konnov

    2014-11-21T23:59:59.000Z

    Nov 21, 2014 ... Sequential Threshold Control in Descent Splitting Methods for Decomposable Optimization Problems. Igor Konnov(konn-igor ***at*** ya.ru).

  18. Molecular dynamics simulation of threshold displacement energies...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    experimental estimates in ceramics. Citation: Moreira PA, R Devanathan, J Yu, and WJ Weber.2009."Molecular dynamics simulation of threshold displacement energies in...

  19. Test Strategy for the European HCPB Test Blanket Module in ITER

    SciTech Connect (OSTI)

    Boccaccini, L.V.; Meyder, R.; Fischer, U. [Forschungszentrum Karlsruhe (Germany)

    2005-05-15T23:59:59.000Z

    According to the European Blanket Programme two blanket concepts, the Helium Cooled Pebble Bed (HCPB) and a Helium Cooled Lithium Lead (HCLL) will be tested in ITER. During 2004 the test blanket modules (TBM) of both concepts were redesigned with the goal to use as much as possible similar design options and fabrication techniques for both types in order to reduce the European effort for TBM development. The result is a robust TBM box being able to withstand 8 MPa internal pressure in case of in-box LOCA; the TBM box consists of First wall (FW), caps, stiffening grid and manifolds. The box is filled with typically 18 and 24 breeding units (BU), for HCPB and HCLL respectively. A breeding unit has about 200 mm in poloidal and toroidal direction and about 400 mm in radial direction; the design is adapted to contain and cooling ceramic breeder/beryllium pebble beds for the HCPB and eutectic Lithium-Lead for the HCLL.The use of a new material, EUROFER, and the innovative design of these Helium Cooled components call for a large qualification programme before the installation in ITER; availability and safety of ITER should not be jeopardised by a failure of these components. Fabrication technologies especially in the welding processes (diffusion welding, EB, TIG, LASER) need to be tested in the manufacturing of large mock-ups; an extensive out-of-pile programme in Helium facility should be foreseen for the verification of the concept from basic helium cooling functions (uniformity of flow in parallel channels, heat transfer coefficient in FW, etc.) up to the verification of large portions of the TBM design under relevant ITER loading.In ITER the TBM will have the main objective to collect information that will contribute to the final design of DEMO blankets. A strategy has been proposed in 2001 that leads to the tests in ITER 4 different Test Blanket Modules (TBM's) type during the first 10 years of ITER operation. For the new HCPB design this strategy is confirmed with some additional possibilities taking into account the modular design of the breeding zone.

  20. Conflict of Interest Review CRADA Principal Investigator's Certification

    E-Print Network [OSTI]

    Baker, Chris I.

    Conflict of Interest Review CRADA Principal Investigator's Certification CRADA Principal Investigator: ______________________________ IC: ___________________________ CRADA ID Number: _________________ Collaborating Organization: ________________________________________________ CRADA Title

  1. Graduate Certificate in Communication and New Media The Graduate Certificate in Communication and New Media emphasizes theory, production,

    E-Print Network [OSTI]

    Berdichevsky, Victor

    Graduate Certificate in Communication and New Media The Graduate Certificate in Communication and New Media emphasizes theory, production, and application of new media: COM 5280: New Media Practices (3 cr) COM 6270: New Media Theory (3 cr

  2. The Drafting Technology Program offers a certificate or associate of applied science in drafting technology. The certificate program

    E-Print Network [OSTI]

    Ickert-Bond, Steffi

    DRAFTING TECHNOLOGY The Drafting Technology Program offers a certificate or associate of applied science in drafting technology. The certificate program offers a choice of six areas of emphasis: architectural drafting; civil drafting; information technology; mechanical and electrical drafting; process

  3. UNIVERSITY OF TORONTO Policy on Diploma and Certificate Programs

    E-Print Network [OSTI]

    Boonstra, Rudy

    UNIVERSITY OF TORONTO Policy on Diploma and Certificate Programs 1. Objective: a) to ensure consistency in the use of the terms "diploma program" and "certificate program" across the divisions) to ensure appropriate standards of quality in diploma and certificate programs c) to ensure

  4. 151 SDSU Curriculum Guide 2010 Professional Certificate Programs

    E-Print Network [OSTI]

    Ponce, V. Miguel

    151 SDSU Curriculum Guide 2010 Professional Certificate Programs Definition Professional certificate programs do not carry academic credit from SDSU. However, some carry X-level pro- fessional development credit; these programs use course numbers X001 ­ X075. All professional certificate programs

  5. Declaration of Intent Certificate in Engineering for Energy Sustainability

    E-Print Network [OSTI]

    Wisconsin at Madison, University of

    Declaration of Intent Certificate in Engineering for Energy Sustainability College of Engineering that I meet all requirements to apply for the Certificate in Engineering for Energy Sustainability. I am:________________________ #12;Tentative Study Plan Certificate in Engineering for Energy Sustainability College of Engineering

  6. Browser Interfaces and Extended Validation SSL Certificates: An Empirical Study

    E-Print Network [OSTI]

    Van Oorschot, Paul

    Browser Interfaces and Extended Validation SSL Certificates: An Empirical Study Robert Biddle provided by SSL certificates and browser interfaces in the face of var- ious attacks. As one response, basic SSL server certificates are being demoted to second-class status in conjunction

  7. www.pcs.udel.edu Career-oriented certificate programs

    E-Print Network [OSTI]

    Firestone, Jeremy

    Management Professional® Examination Prep 9 Lean Six Sigma Green Belt Certificate 9 Social Media Marketing Certificate graduate. Visit www.pcs.udel.edu/students to read her story. #12;Jeff Garvey Lean Six Sigma Green victim to it. So, I enrolled in UD's Lean Six Sigma Certificate and learned how to take a problem, break

  8. Proposal for the award of a blanket purchase contract for the replacement and maintenance of lifts giving access to the LHC underground areas

    E-Print Network [OSTI]

    2015-01-01T23:59:59.000Z

    Proposal for the award of a blanket purchase contract for the replacement and maintenance of lifts giving access to the LHC underground areas

  9. Proposal for the award of a blanket contract for the supply, commissioning and maintenance of water-and air-cooled chillers

    E-Print Network [OSTI]

    2011-01-01T23:59:59.000Z

    Proposal for the award of a blanket contract for the supply, commissioning and maintenance of water-and air-cooled chillers

  10. Proposal to negotiate an amendment to a blanket purchase contract for the supply and installation of water-cooled bus bars and cables for the LHC

    E-Print Network [OSTI]

    2014-01-01T23:59:59.000Z

    Proposal to negotiate an amendment to a blanket purchase contract for the supply and installation of water-cooled bus bars and cables for the LHC

  11. Proposal for the award of a blanket purchase contract for the supply of numerical relays for the protection of electrical power systems

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    Proposal for the award of a blanket purchase contract for the supply of numerical relays for the protection of electrical power systems

  12. Proposal to negotiate the renewal of a blanket purchase contract for the supply of high-power RF grid-tubes for the CERN accelerators

    E-Print Network [OSTI]

    2014-01-01T23:59:59.000Z

    Proposal to negotiate the renewal of a blanket purchase contract for the supply of high-power RF grid-tubes for the CERN accelerators

  13. Proposal for the award of blanket purchase contracts for the supply and maintenance of light petrol and light bi-fuel vehicles

    E-Print Network [OSTI]

    2010-01-01T23:59:59.000Z

    Proposal for the award of blanket purchase contracts for the supply and maintenance of light petrol and light bi-fuel vehicles

  14. Certificate in Geospatial Technology The School of Earth, Environment, and Society offers a graduate certificate in Geospatial

    E-Print Network [OSTI]

    Moore, Paul A.

    Certificate in Geospatial Technology The School of Earth, Environment, and Society offers a graduate certificate in Geospatial Technology. The purpose of the certificate program is to provide graduate students with training in geospatial theory, research design, and its application in fields

  15. Wind-Blown Sand: Threshold of Motion

    E-Print Network [OSTI]

    Swann, Christy Michelle

    2014-11-12T23:59:59.000Z

    ....................................................................................... 43 13 Bedload trap designed for this study .................................................................................. 45 14 Schematic of internal adjustable chimney adjusted to the height of the surface... predicting the threshold for wind-blown sand in natural environments are rooted in the original wind tunnel work of Bagnold (1936). He introduced an empirically-calibrated model of the threshold using shear velocity, 𝑢?: a height independent variable...

  16. Hierarchical Threshold Secret Sharing Tamir Tassa

    E-Print Network [OSTI]

    Beimel, Amos

    Hierarchical Threshold Secret Sharing Tamir Tassa Abstract We consider the problem of threshold secret sharing in groups with hierarchical structure. In such settings, the secret is shared among and the presence of higher level participants is imperative to allow the recovery of the common secret. Even though

  17. Hierarchical Threshold Secret Sharing Tamir Tassa #

    E-Print Network [OSTI]

    Tassa, Tamir

    Hierarchical Threshold Secret Sharing Tamir Tassa # December 6, 2006 Abstract We consider the problem of threshold secret sharing in groups with hierarchical structure. In such settings, the secret of the common secret. Even though secret sharing in hierarchical groups has been studied extensively in the past

  18. Hierarchical Threshold Secret Sharing Tamir Tassa

    E-Print Network [OSTI]

    Tassa, Tamir

    Hierarchical Threshold Secret Sharing Tamir Tassa Division of Computer Science, The Open University tassa@yahoo.com Abstract. We consider the problem of threshold secret sharing in groups with hierarchical structure. In such settings, the secret is shared among a group of participants

  19. Hierarchical Threshold Secret Sharing Tamir Tassa

    E-Print Network [OSTI]

    Tassa, Tamir

    Hierarchical Threshold Secret Sharing Tamir Tassa December 6, 2006 Abstract We consider the problem of threshold secret sharing in groups with hierarchical structure. In such settings, the secret is shared among and the presence of higher level participants is imperative to allow the recovery of the common secret. Even though

  20. Simulating Threshold Circuits by Majority Circuits \\Lambda

    E-Print Network [OSTI]

    Karpinski, Marek

    Simulating Threshold Circuits by Majority Circuits \\Lambda Mikael Goldmann y Numerical Analysis, and Kailath proved super­linear lower bounds on the number of wires in constant­depth majority circuits­size depth 2 majority circuit. In general we show that a polynomial­size, depth­ d threshold circuit can

  1. DER Certification Laboratory Pilot, Accreditation Plan, and Interconnection Agreement Handbook

    SciTech Connect (OSTI)

    Key, T.; Sitzlar, H. E.; Ferraro, R.

    2003-11-01T23:59:59.000Z

    This report describes the first steps toward creating the organization, procedures, plans and tools for distributed energy resources (DER) equipment certification, test laboratory accreditation, and interconnection agreements. It covers the activities and accomplishments during the first period of a multiyear effort. It summarizes steps taken to outline a certification plan to assist in the future development of an interim plan for certification and accreditation activities. It also summarizes work toward a draft plan for certification, a beta Web site to support communications and materials, and preliminary draft certification criteria.

  2. SMART GRID TECHNOLOGIES (CERTIFICATE) www.ee.washington.edu/admissions/pmp/certificates

    E-Print Network [OSTI]

    Washington at Seattle, University of

    , and biomass Integration of renewable systems Renewable energy integration solutions #12;In addition delivery renewable energy integration and operation The certificate program consists of 12 graduate level Spring Course: "Renewable Energy Integration and Operation" Renewable energy landscape Wind energy

  3. Certifications http://OperationsExcellence.utk.edu

    E-Print Network [OSTI]

    Grissino-Mayer, Henri D.

    Certifications http://OperationsExcellence.utk.edu Green, Black, Lean Six Sigma, and Master Black) Lean (one week of coursework) 2) Lean Six Sigma (two weeks of coursework) 3) Six Sigma (two weeks) lean Six Sigma Green Belt coursework: Location: Knoxville, Tennessee Tuition: $4,500 (5 days) or $3

  4. APPLICATION -doctoral or licentiate degree certificate

    E-Print Network [OSTI]

    Lagergren, Jens

    APPLICATION - doctoral or licentiate degree certificate Submit to the administration at the deans of Philosophy/Teknologie doktorsexamen FD Doctor of Philosophy/Filosofie doktorsexamen TL Licentiate of Engineering/Teknologie licentiatexamen FL Licentiate of Philosophy/Filosofie licentiatexamen The degree

  5. By Rebecca Barnard, Forest Certification Coordinator

    E-Print Network [OSTI]

    - administered land. Third party and annual surveillance audits maintain or improve the DNR's forest management that their products Continued on page 4 Chain of Custody Market Outlook 2 Certification Web sites 5 Stumpage Prices 6 percent long-run trend level by mid-2009. However, energy and fuel prices have increased to levels well

  6. Postgraduate Certificate in Safety and Risk Management

    E-Print Network [OSTI]

    Mottram, Nigel

    Postgraduate Certificate in Safety and Risk Management #12;Programme Structure The Postgraduate and risk management 15 credits This module takes account of the needs of participants coming from diverse academic and professional backgrounds. It provides a context for safety and risk management practice

  7. Is Stewardship Certification? Richard P. Vlosky

    E-Print Network [OSTI]

    Wu, Qinglin

    organizations, retailers, and forest products companies are encouraging consumers to purchase wood and wood and forestland management, many groups have a stake in forest certification, including the timber industry, miscellaneous individuals, and non-forest industry corporations, such as banks, insurance companies and the like

  8. Forest Certification in Brazil Peter H. May

    E-Print Network [OSTI]

    Forest Certification in Brazil Peter H. May Executive Secretary, Brazilian Agroforestry Network Studies New Haven, Connecticut, USA June 10 & 11, 2004 http://www.yale.edu/forestcertification/symposium/pdfs/brazil, Economic, and Ecological Effects Brazil DRAFT PAPERS ­ PLEASE DO NOT CITE 2 ABSTRACT This paper reviews

  9. NO.: 1369792 PATENT CERTIFICATE FOR INVENTION

    E-Print Network [OSTI]

    Peleg, Shmuel

    NO.: 1369792 PATENT CERTIFICATE FOR INVENTION TITLE OF INVENTION: METHOD AND SYSTEM FOR VIDEO PATENT NO.: ZL 2007800506100 FILING DATE OF APPLICATION: December 9, 2007 PROPRIETOR OF PATENT RIGHT: March 26, 2014 After the examination was performed according to the Patent Law, the present Office

  10. Emerging Markets for Renewable Energy Certificates

    E-Print Network [OSTI]

    .nrel.gov Operated for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy by Midwest.S. Department of Energy Office of Energy Efficiency and Renewable Energy by Midwest Research InstituteEmerging Markets for Renewable Energy Certificates: Opportunities and Challenges January 2005

  11. Philip Mouser Graduate, Risk Management Certificate

    E-Print Network [OSTI]

    Sokolowski, Marla

    for International Professionals (Advanced) Please see page 31. · Business Information Technology Management Please 45. · Mobile Business Technologies and Applications Please see page 40. #12;L E A R N . U T O R O NPhilip Mouser Graduate, Risk Management Certificate "All of the instructors are industry experts

  12. DDT Certification Status Last Name First Name

    E-Print Network [OSTI]

    DDT Certification Status Last Name First Name DDT Expire Date Abdelsamad Ramy 6-Jan-2016 16-Nov-2013 #12;Last Name First Name DDT Expire Date Arica Aimee Mintu 8-Apr-2015 Armstrong Gretchen #12;Last Name First Name DDT Expire Date Beckman Paul Allan 26-Apr-2015 Bejar Matthew Philip 22-Sep

  13. Roundtable on Sustainable Biofuels Certification Readiness Study

    E-Print Network [OSTI]

    Roundtable on Sustainable Biofuels Certification Readiness Study: Hawai`i Biofuel Projects Prepared 12.1 Deliverable (item 2) Bioenergy Analyses Prepared by Hawai`i Biofuel Foundation And NCSI Americas: Hawaii Biofuel Projects Prepared For Hawaii Natural Energy Institute School of Ocean Earth Sciences

  14. Certification plan for safety and PRA codes

    SciTech Connect (OSTI)

    Toffer, H.; Crowe, R.D. (Westinghouse Hanford Co., Richland, WA (United States)); Ades, M.J. (Westinghouse Savannah River Co., Aiken, SC (United States))

    1990-05-01T23:59:59.000Z

    A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan's objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations.

  15. Certification plan for safety and PRA codes

    SciTech Connect (OSTI)

    Toffer, H.; Crowe, R.D. [Westinghouse Hanford Co., Richland, WA (United States); Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1990-05-01T23:59:59.000Z

    A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA&PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan`s objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations.

  16. A helium-cooled blanket design of the low aspect ratio reactor

    SciTech Connect (OSTI)

    Wong, C.P.; Baxi, C.B.; Reis, E.E. [General Atomics, San Diego, CA (United States); Cerbone, R.; Cheng, E.T. [TSI Research, Solana Beach, CA (United States)

    1998-03-01T23:59:59.000Z

    An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can have a major radius as small as 2.9 m resulting in a device with competitive cost of electricity at 49 mill/kWh. One of the technology requirements of this design is a high performance high power density first wall and blanket system. A 15 MPa helium-cooled, V-alloy and stagnant LiPb breeder first wall and blanket design was utilized. Due to the low solubility of tritium in LiPb, there is the concern of tritium migration and the formation of V-hydride. To address these issues, a lithium breeder system with high solubility of tritium has been evaluated. Due to the reduction of blanket energy multiplication to 1.2, to maintain a plant Q of > 4, the major radius of the reactor has to be increased to 3.05 m. The inlet helium coolant temperature is raised to 436 C in order to meet the minimum V-alloy temperature limit everywhere in the first wall and blanket system. To enhance the first wall heat transfer, a swirl tape coolant channel design is used. The corresponding increase in friction factor is also taken into consideration. To reduce the coolant system pressure drop, the helium pressure is increased from 15 to 18 MPa. Thermal structural analysis is performed for a simple tube design. With an inside tube diameter of 1 cm and a wall thickness of 1.5 mm, the lithium breeder can remove an average heat flux and neutron wall loading of 2 and 8 MW/m(2), respectively. This reference design can meet all the temperature and material structural design limits, as well as the coolant velocity limits. Maintaining an outlet coolant temperature of 650 C, one can expect a gross closed cycle gas turbine thermal efficiency of 45%. This study further supports the use of helium coolant for high power density reactor design. When used with the low aspect ratio reactor concept a competitive fusion reactor can be projected at 51.9 mill/kWh.

  17. Summary of benchmark experiments for simulation of fusion reactors using an annular blanket with a line deuterium-tritium source

    SciTech Connect (OSTI)

    Maekawa, H.; Abdou, M.A.; Oyama, Y. [Japan Atomic Energy Research Inst., Ibaraki (Japan)] [and others

    1995-09-01T23:59:59.000Z

    The Japan Atomic Energy Research lnstitute (JAERI)/U.S. Department of Energy collaborative program was performed using the Fusion Neutronics Source facility at JAERI. In Phase III of this program, tritium breeding measurements were conducted in prototypical blankets driven by a simulated deuterium-tritium neutron line source. This phase differed from the earlier two phases in respect to the spatial distribution of the source as the earlier experiments were done with a point neutron source. This series basically consisted of an annular test blanket and a pseudoline source to investigate the effect of source spread on the neutronic performance. A concise description is on the outlines of the simulated line source, the test blanket systems for Phases-IIIA, -IIIB, and -IIIC, measured items, experimental results, and their analyses. 23 refs., 8 figs., 3 tabs.

  18. Normal operation and maintenance safety lessons from the ITER US PbLi test blanket module program for a US FNSF and DEMO

    SciTech Connect (OSTI)

    L. C. Cadwallader; C. P. C. Wong; M. Abdou; B. B. Morely; B.J Merrill

    2014-10-01T23:59:59.000Z

    A leading power reactor breeding blanket candidate for a fusion demonstration power plant (DEMO) being pursued by the US Fusion Community is the Dual Coolant Lead Lithium (DCLL) concept. The safety hazards associated with the DCLL concept as a reactor blanket have been examined in several US design studies. These studies identify the largest radiological hazards as those associated with the dust generation by plasma erosion of plasma blanket module first walls, oxidation of blanket structures at high temperature in air or steam, inventories of tritium bred in or permeating through the ferritic steel structures of the blanket module and blanket support systems, and the 210Po and 203Hg produced in the PbLi breeder/coolant. What these studies lack is the scrutiny associated with a licensing review of the DCLL concept. An insight into this process was gained during the US participation in the International Thermonuclear Experimental Reactor (ITER) Test Blanket Module (TBM) Program. In this paper we discuss the lessons learned during this activity and make safety proposals for the design of a Fusion Nuclear Science Facility (FNSF) or a DEMO that employs a lead lithium breeding blanket.

  19. Engineering Scaling Requirements for Solid Breeder Blanket Testing A. Ying, S. Sharafat, M. Youssef, J. An, R. Hunt, P. Rainsberry, M. Abdou

    E-Print Network [OSTI]

    Abdou, Mohamed

    Engineering Scaling Requirements for Solid Breeder Blanket Testing A. Ying, S. Sharafat, M. Youssef@fusion.ucla.edu An engineering scaling process is applied to the solid breeder ITER TBM designs in accordance with the testing objectives of validating the design tools and the database, and evaluating blanket performance under

  20. Certificates and Diplomas-1 last saved on 5/2/2013

    E-Print Network [OSTI]

    Guenther, Frank

    MET G 9054 Certificate Criminal Justice MET G 9091 Certificate Cyber Security MET I 9026 Graduate Certificate Database Management and Business Intelligence MET I 9027 Graduate Certificate Database Security/2/2013 Geographically Distributed Software Development MET I 9098 Graduate Certificate Gerontological Social Work SSW I

  1. Effective Thermal Conductivity of a Li{sub 2}TiO{sub 3} Pebble Bed for a DEMO Blanket

    SciTech Connect (OSTI)

    Hatano, T.; Enoeda, M.; Suzuki, S.; Kosaku, Y.; Akiba, M. [Japan Atomic Energy Research Institute (Japan)

    2003-07-15T23:59:59.000Z

    In development of the ceramic breeder blanket, the effective thermal conductivity of pebble beds is an important design parameter. For thermo-mechanical design of blanket, pebble beds were investigated used for Li{sub 2}TiO{sub 3} that was a candidate for tritium breeder. Li{sub 2}TiO{sub 3} pebble beds, whose size was 0.28-1.91 mm diameter, were measured on load under no neutron irradiation. The effective thermal conductivity was increased with load increasing was obtained.

  2. APT Blanket System Loss-of-Coolant Accident (LOCA) Based on Initial Conceptual Design - Case 2: with Beam Shutdown Only

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    This report is one of a series of reports that document normal operation and accident simulations for the Accelerator Production of Tritium (APT) blanket heat removal system. These simulations were performed for the Preliminary Safety Analysis Report. This report documents the results of simulations of a Loss-of-Flow Accident (LOFA) where power is lost to all of the pumps that circulate water in the blanket region, the accelerator beam is shut off and neither the residual heat removal nor cavity flood systems operate.

  3. Beyond Kennicott : perceptions of threshold, conceptions of distance

    E-Print Network [OSTI]

    Bull, Steven Keith

    1997-01-01T23:59:59.000Z

    Threshold: The thesis explores descriptions of threshold. Threshold is not an ordinary space. It relates to the here and the there and the understanding of distance. It is the phenomena of distance, no matter how close ...

  4. Natural Circulation in the Blanket Heat Removal System During a Loss-of-Pumping Accident (LOFA) Based on Initial Conceptual Design

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    A transient natural convection model of the APT blanket primary heat removal (HR) system was developed to demonstrate that the blanket could be cooled for a sufficient period of time for long term cooling to be established following a loss-of-flow accident (LOFA). The particular case of interest in this report is a complete loss-of-pumping accident. For the accident scenario in which pumps are lost in both the target and blanket HR systems, natural convection provides effective cooling of the blanket for approximately 68 hours, and, if only the blanket HR systems are involved, natural convection is effective for approximately 210 hours. The heat sink for both of these accident scenarios is the assumed stagnant fluid and metal on the secondary sides of the heat exchangers.

  5. Threshold Effects Beyond the Standard Model

    E-Print Network [OSTI]

    Tomasz R. Taylor

    2006-12-12T23:59:59.000Z

    In this contribution to the Festschrift celebrating Gabriele Veneziano on his 65th birthday, I discuss the threshold effects of extra dimensions and their applications to physics beyond the standard model, focusing on superstring theory.

  6. Summary of experiments and analysis from the JAERI/USDOE collaborative program on fusion blanket neutronics

    SciTech Connect (OSTI)

    Maekawa, H. [Japan Atomic Energy Research Inst., Ibaraki-ken (Japan); Abdou, M.A. [Univ. of California, Los Angeles, CA (United States)

    1994-12-31T23:59:59.000Z

    The JAERI/USDOE Collaborative program on Fusion Blanket Neutronics was started officially on Oct. 23, 1984 using the intense D-T neutron generator FNS and terminated in 1993. The objectives of the program are: (1) to validate neutronics methods, codes and nuclear data, (2) to provide estimates of uncertainties in satisfying tritium self-sufficiency in fusion reactors, (3) to provide integral data on nuclear heating, induced radioactivity and afterheat, and (4) to develop the neutronics technology for the design and testing of the next fusion devices. The program was divided into three phases depending on the ideas of the source and test blanket arrangements. Useful and reliable benchmark data have been accumulated through this collaboration experiments. They are tritium production rates (TPR) of Li-6, Li-7 and Li-natural, various reaction rates measured by activation foils, neutron spectra, gamma-ray spectra, gamma-ray heating rates and so on. Both Japan and US analyzed these benchmark experiments using latest and/or newly developed data and methods, e.g., GMVP, MCNP, JENDL-3, etc. A novel methodology has been developed to estimate design safety factors and the associated confidence levels. These safety factors are based on the prediction uncertainties of TPR as derived from the numerous calculational and experimental data accumulated during the program.

  7. Nuclear-radiation-actuated valve. [Patent application; for increasing coolant flow to blanket

    DOE Patents [OSTI]

    Christiansen, D.W.; Schively, D.P.

    1982-01-19T23:59:59.000Z

    The present invention relates to a breeder reactor blanket fuel assembly coolant system valve which increases coolant flow to the blanket fuel assembly to minimize long-term temperature increases caused by fission of fissile fuel created from fertile fuel through operation of the breeder reactor. The valve has a valve first part (such as a valve rod with piston) and a valve second part (such as a valve tube surrounding the valve rod, with the valve tube having side slots surrounding the piston). Both valve parts have known nuclear radiation swelling characteristics. The valve's first part is positioned to receive nuclear radiation from the nuclear reactor's fuel region. The valve's second part is positioned so that its nuclear radiation induced swelling is different from that of the valve's first part. The valve's second part also is positioned so that the valve's first and second parts create a valve orifice which changes in size due to the different nuclear radiation caused swelling of the valve's first part compared to the valve's second part. The valve may be used in a nuclear reactor's core coolant system.

  8. A threshold type Cerenkov radiation detector

    E-Print Network [OSTI]

    Winningham, John David

    1965-01-01T23:59:59.000Z

    A THRESHOLD TYPE CERENKOV RADIATION DETECTOR A Thesis By JOHN DAVID WINNINGHAN Submitted to the Graduate College of the Texas A&M University in partial fulfillment of the requirements for the degree of NASTER OF SCIENCE May, 1965 Ha/or Sub...)ect: Physics A THRESHOLD TYPE CERENKOV RADIATION DETECTOR A Thesis By JOHN DAVID WINNINGHAM Approved as to style and content by: 3 v (Chairman of Committee) j' ) Heqd of Department) (Member) (Member) May, 1965 i. '. 11648 ACKNOWLEDGEIKNTS I wish...

  9. Three-dimensional neutronics optimization of helium-cooled blanket for multi-functional experimental fusion-fission hybrid reactor (FDS-MFX)

    SciTech Connect (OSTI)

    Jiang, J.; Yuan, B.; Jin, M.; Wang, M.; Long, P.; Hu, L. [Inst. of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Univ. of Science and Technology of China, Hefei, Anhui, 230031 (China); School of Nuclear Science and Technology, Univ. of Science and Technology of China, No.350 Shushanhu Road, Shushan District, Hefei, Anhui, 230031 (China)

    2012-07-01T23:59:59.000Z

    Three-dimensional neutronics optimization calculations were performed to analyse the parameters of Tritium Breeding Ratio (TBR) and maximum average Power Density (PDmax) in a helium-cooled multi-functional experimental fusion-fission hybrid reactor named FDS (Fusion-Driven hybrid System)-MFX (Multi-Functional experimental) blanket. Three-stage tests will be carried out successively, in which the tritium breeding blanket, uranium-fueled blanket and spent-fuel-fueled blanket will be utilized respectively. In this contribution, the most significant and main goal of the FDS-MFX blanket is to achieve the PDmax of about 100 MW/m3 with self-sustaining tritium (TBR {>=} 1.05) based on the second-stage test with uranium-fueled blanket to check and validate the demonstrator reactor blanket relevant technologies based on the viable fusion and fission technologies. Four different enriched uranium materials were taken into account to evaluate PDmax in subcritical blanket: (i) natural uranium, (ii) 3.2% enriched uranium, (iii) 19.75% enriched uranium, and (iv) 64.4% enriched uranium carbide. These calculations and analyses were performed using a home-developed code VisualBUS and Hybrid Evaluated Nuclear Data Library (HENDL). The results showed that the performance of the blanket loaded with 64.4% enriched uranium was the most attractive and it could be promising to effectively obtain tritium self-sufficiency (TBR-1.05) and a high maximum average power density ({approx}100 MW/m{sup 3}) when the blanket was loaded with the mass of {sup 235}U about 1 ton. (authors)

  10. Maintenance of certification and the financial status of the medical boards

    E-Print Network [OSTI]

    Lieberman, Miriam R.; Siegel, Daniel M.

    2015-01-01T23:59:59.000Z

    H, Phy M, Nugent K. Maintenance of certification in Internalpdf/f990.pdf . ) 7. "ABMS Maintenance of Certification®."ABMS Maintenance of Certification®. N.p. , n.d. Web. (

  11. Computational Science and Engineering Certification for Nuclear, Plasma, and Radiological Engineering

    E-Print Network [OSTI]

    Gilbert, Matthew

    Computational Science and Engineering Certification for Nuclear, Plasma, and Radiological Engineering The Computational Science and Engineering certificate program is designed to provide NPRE a certificate in "Computational Science and Engineering", students must complete the required courses listed

  12. Overview of the Michigan DNR Forest Certification Program By Dennis Nezich

    E-Print Network [OSTI]

    1 Overview of the Michigan DNR Forest Certification Program By Dennis Nezich January 27, 2011 OF CERTIFICATION: The scope of certification includes 3.9 million acres of state land within the Michigan State

  13. Security Equipment and Systems Certification Program (SESCP)

    SciTech Connect (OSTI)

    Steele, B.J. [Sandia National Labs., Albuquerque, NM (United States); Papier, I.I. [Underwriters Labs., Inc., Northbrook, IL (United States)

    1996-06-20T23:59:59.000Z

    Sandia National Laboratories (SNL) and Underwriters Laboratories, Inc., (UL) have jointly established the Security Equipment and Systems Certification Program (SESCP). The goal of this program is to enhance industrial and national security by providing a nationally recognized method for making informed selection and use decisions when buying security equipment and systems. The SESCP will provide a coordinated structure for private and governmental security standardization review. Members will participate in meetings to identify security problems, develop ad-hoc subcommittees (as needed) to address these identified problems, and to maintain a communications network that encourages a meaningful exchange of ideas. This program will enhance national security by providing improved security equipment and security systems based on consistent, reliable standards and certification programs.

  14. AMPX-77 Phase 1 certification package

    SciTech Connect (OSTI)

    Niemer, K.A.

    1994-03-01T23:59:59.000Z

    The AMPX-77 Phase 1 modules have been certified. AMPX-77 is a modular code system for generating coupled multigroup neutron-gamma cross section libraries from Evaluated Nuclear Data Files (ENDF/B). All basic cross-section data are input from the formats used by the ENDF/B, and output can be obtained from a variety of formats, included in its own internal and very general formats, along with a variety of other useful formats used by major transport, diffusion theory, and Monte Carlo codes. Processing is provided for both neutron and gamma-ray data. The AMPX-77 code system will be used at SRS to perform critical calculations related to nuclear criticality safety. The AMPX-77 modular codes system contains forty-seven separate modules. For the certification process, the 47 modules have been divided into three groups or phases. This Certification Package is for the Phase 1 modules: BONAMI, LAPHNGAS, MALOCS, NITAWL, ROLAIDS, SMUG, and XSDRNPM.

  15. The Leadership Certificate The administration of the Leadership Certificate is moving from the Dietrich School of Arts and Sciences to the

    E-Print Network [OSTI]

    Jiang, Huiqiang

    The Leadership Certificate The administration of the Leadership Certificate is moving from the Dietrich School curriculum must declare the Leadership Certificate no later than April 25, 2014. Students Leadership Certificate is a program open to any University of Pittsburgh students interested in further

  16. MISSION INTGRE -CERTIFICATION Pulpe & Papier Plus inc. (PPP)

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    MISSION INT�GR�E - CERTIFICATION Pulpe & Papier Plus inc. (PPP) Papier proposé par : Richard WILSON, Strasbourg : France (2009)" #12;Pulpe & Papier Plus inc.(PPP) 1. Introduction à la mission intégrée de certification PPP 1.1 Mise en contexte Cette mission intégrée de certification découle de la volonté des membres

  17. CERTIFICATE OF AUTHENTICITY | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative FuelsNovember 13, 2014 Building America Update -CompositesCEMI 2015SpeakersCERTIFICATE

  18. September 11, 2000 A. R. Raffray, et al., High Performance Blanket for ARIES-AT Power Plant, SOFT 2000

    E-Print Network [OSTI]

    Raffray, A. René

    and coolant and SiCf/SiC composite as structural material. This paper describes the results of the design and material choice yielding acceptable TBR · Low activation material with no serious consequences on blanket · Turbine efficiency = 0.93 · Compressor efficiency = 0.88 · Recuperator effectiveness (advanced design) = 0

  19. Activation analysis and characteristics of the European community water cooled ceramic breeder blanket design proposal for ITER

    SciTech Connect (OSTI)

    Petrizzi, L.; Rado, V. [ENEA-ERG-FUS, Frascati (Italy); Cepraga, D.G. [ENEA-INN-FIS, Bologna (Italy)

    1994-12-31T23:59:59.000Z

    The European Community (EC) Home Team has proposed various alternative blanket designs to the basic concept (essentially integrated first wall, cooled by liquid metal, with structures made by vanadium alloys). One of the EC proposal is the Water Cooled Ceramic Blanket developed on the basis of a common action between NET and ENEA. It is based on a more conservative approach, but involving well proven technologies and qualified materials: SS-316L as structural material, Li{sub 2}ZrO{sub 3} as first breeder material choice (50% Li{sup 6} enrichment) and low temperature water coolant (160/200{degrees}C). Beryllium has been chosen as multiplying material. The nominal performance are: 1 MW/m{sup 2} as average neutron wall load, corresponding to 1.5 GW fusion power, 1 MW-y/m{sup 2} beneath it has been proved to withstand power excursion till 5 GW. The proposed blanket concept is based on a Breeder Inside Tube (BIT) type technology, with poloidal breeding elements, each one consisting of two concentric tubes. Breeder pebbles are filled into the inner tube, the water coolant flows in the annular channel between the two tubes. Beryllium pebbles fill the space of the blanket box outside the outer tube. A helium purge gas flows through the breeder pebbles bed for tritium recovery. Alternative operating water temperature and pressure are proposed, considering also batch tritium recovery.

  20. Bl k t T h l F l C l dBlanket Technology, Fuel Cycle and Tritium Self Sufficiency

    E-Print Network [OSTI]

    Abdou, Mohamed

    and TechnologyNuclear Science and Technology (FNST). 4 #12;FNST is the science, engineering, technology and materials Fusion Nuclear Science & Technology (FNST) FNST is the science, engineering, technologyBl k t T h l F l C l dBlanket Technology, Fuel Cycle and Tritium Self Sufficiency M h d Abd

  1. Investigation of Neutron Characteristics for Salt Blanket Models; Integral Fission Cross Section Measurements of Neptunium, Plutonium, Americium and Curium Isotopes

    E-Print Network [OSTI]

    E. Fomushkin

    2002-08-30T23:59:59.000Z

    Neutron characteristics of salt blanket micromodels containing mixtures of sodium, zirconium and uranium sulphides were measured on FKBN-2M, BIGR and MAKET installations. The effective fission cross sections of neptunium, plutonium, americium and curium isotopes were measured on the neutron spectra formed by micromodels.

  2. Case studies of the application of the Certification Framework to two geologic carbon sequestration sites

    SciTech Connect (OSTI)

    Oldenburg, Curtis M.; Nicot, J.-P.; Bryant, S.L.

    2008-11-01T23:59:59.000Z

    We have developed a certification framework (CF) for certifying that the risks of geologic carbon sequestration (GCS) sites are below agreed-upon thresholds. The CF is based on effective trapping of CO2, the proposed concept that takes into account both the probability and impact of CO2 leakage. The CF uses probability estimates of the intersection of conductive faults and wells with the CO2 plume along with modeled fluxes or concentrations of CO2 as proxies for impacts to compartments (such as potable groundwater) to calculate CO2 leakage risk. In order to test and refine the approach, we applied the CF to (1) a hypothetical large-scale GCS project in the Texas Gulf Coast, and (2) WESTCARB's Phase III GCS pilot in the southern San Joaquin Valley, California.

  3. Green Building Certification Systems Requirement for New Federal...

    Energy Savers [EERE]

    greenblgcert.docx More Documents & Publications EA-1991: Final Environmental Assessment Green Building Certification Systems Requirement for New Federal Buildings and Major...

  4. New Year, New Certification Opportunities for Home Energy Workers...

    Broader source: Energy.gov (indexed) [DOE]

    today to find out how to get certified as a BPI home energy professional. Addthis Related Articles New Year, New Certification Opportunities for Home Energy Workers Accredited...

  5. Energy Performance Certification of Buildings: A Policy Tool...

    Open Energy Info (EERE)

    Buildings: A Policy Tool to Improve Energy Efficiency Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Energy Performance Certification of Buildings: A Policy Tool to...

  6. Texas General Land Office Construction Certificate and Dune Protection...

    Open Energy Info (EERE)

    Texas General Land Office Construction Certificate and Dune Protection Permit Requirements Checklist Jump to: navigation, search OpenEI Reference LibraryAdd to library Permitting...

  7. DOE/Mitsubishi Enter Consent Decree Dismissing Claims of Certification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    May 7, 2010, DOE entered into a Consent Decree with Mitsubishi Electric & Electronics, USA Inc. dismissing alleged energy efficiency certification violations in return for a...

  8. Hawaii Clean Energy Initiative Certificate of Public Convenience...

    Open Energy Info (EERE)

    Reference LibraryAdd to library PermittingRegulatory Guidance - Instructions: Hawaii Clean Energy Initiative Certificate of Public Convenience and Necessity Permit...

  9. JAPAN GOING TOWARD FOREST CERTIFICATION September 24, 2004

    E-Print Network [OSTI]

    IN JAPAN ............................... 3 ISO14001 (International Organization for Standardization customers are becoming aware of forest certification. In addition to the widespread of international

  10. DOE Resolves Nearly All of its September 2010 Certification Enforcemen...

    Office of Environmental Management (EM)

    one case based on tangible evidence that the company, Aero-Tech, sells a type of bulb that qualifies for an exemption from the certification requirement. Four proposed...

  11. DOE Convening Report on Certification of Commercial HVAC and...

    Broader source: Energy.gov (indexed) [DOE]

    of a negotiated rulemaking to revise the certification program for commercial HVAC and CRE products published on October 2, 2012. conveningreporthvaccre1.pdf More...

  12. Considerations for Emerging Markets for Energy Savings Certificates

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    for Energy Savings Certificates Barry Friedman and Lori Bird National Renewable Energy Laboratory Galen Barbose Lawrence Berkeley National Laboratory Considerations for...

  13. Energy Supplier Obligations and White Certificate Schemes: Comparative...

    Open Energy Info (EERE)

    Results in the European Union Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Energy Supplier Obligations and White Certificate Schemes: Comparative Analysis of Results...

  14. Accredited Certifications Bring a Higher Level of Quality to...

    Energy Savers [EERE]

    - are the only home performance credentials supported by DOE and accredited by ANSI.ANSI ISO 17024 accreditation is the global benchmark for personnel certifications across all...

  15. ap600 design certification: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    for the future The Green Building and Sustainable Design Certificate Program addresses Energy Storage, Conversion and Utilization Websites Summary: Building for the future The...

  16. Application Form for Replacement Diploma/Program Certificate (Form must be notarized)

    E-Print Network [OSTI]

    Application Form for Replacement Diploma/Program Certificate (Form must be notarized) Complete to Princeton University as follows: Replacement Diploma - $75 Replacement Program Certificate - $30 Please

  17. Who Owns Renewable Energy Certificates? An Exploration of Policy Options and Practice

    E-Print Network [OSTI]

    Holt, Edward A.; Wiser, Ryan; Bolinger, Mark

    2006-01-01T23:59:59.000Z

    2005. Emerging Markets for Renewable Energy Certificates:Challenges. National Renewable Energy Laboratory, January.law (Olson Who Owns Renewable Energy Certificates? On May

  18. Proposal for the award of two blanket contracts for the supply of high-grade helium

    E-Print Network [OSTI]

    2003-01-01T23:59:59.000Z

    This document concerns the supply of up to 280 000 kg of high-grade helium. Following a call for tenders (IT-3235/AT) sent on 4 July 2003 to seven firms, in four Member States, CERN had, by the closing date, received six tenders from six firms in four Member States. The Finance Committee is invited to agree to the negotiation of two blanket contracts for the supply of up to 280 000 kg of high-grade helium with AIR PRODUCTS (FR) and CARBAGAS (CH) for a total maximum amount for both contracts of 5 577 800 US dollars (7 736 400 Swiss francs), not subject to revision, for a period of four years starting 1 January 2004. The rates of exchange used are those stipulated in the tenders. The firms have indicated the following distribution by country of the contract value covered by this adjudication proposal: AIR PRODUCTS : PL - 100%; CARBAGAS : PL - 100%.

  19. Modeling Tritium Transport in PbLi Breeder Blankets Under Steady State

    SciTech Connect (OSTI)

    H. Zhang; A. Ying; M. Abdou; B. Merrill

    2011-08-01T23:59:59.000Z

    Tritium behavior in the breeder/coolant plays a crucial role in keeping the tritium loss under an allowable limit and realizing high tritium recovery efficiency. In this paper, progress toward the development of a comprehensive 3D predictive capability is discussed and presented. The sequence of transport processes leading to tritium release includes diffusion and convection through the PbLi, transfer across the liquid/solid interface, diffusion of atomic tritium through the structure, and dissolution-recombination at the solid/gas interface. Numerical simulation of the coupled individual physics phenomena of tritium transport is performed for DCLL/HCLL type breeder blankets under realistic reactor-like conditions in this paper. Tritium concentration and permeation are presented and the MHD effects are evaluated. Preliminary results shows that the MHD velocity profile has the significant effect in preventing tritium permeation due to the higher convection effects near the wall.

  20. Neutronics Experiments Using Small Partial Mockups of the ITER Test Blanket Module with a Solid Breeder

    SciTech Connect (OSTI)

    Sato, Satoshi; Verzilov, Yury; Nakao, Makoto; Ochiai, Kentaro; Wada, Masayuki; Nishitani, Takeo [Japan Atomic Energy Research Institute (Japan)

    2005-05-15T23:59:59.000Z

    In order to evaluate the impacts of the incident neutron spectrum and the tungsten armor on the tritium production, integral experiments have been performed with small partial mockups relevant to the ITER test blanket module using DT neutrons at FNS of JAERI. The Monte Carlo calculation results for the integrated tritium productions agree well with the experimental data within 2 and 11 % for the mockups without the armor in the experiments without and with the neutron reflector, respectively. It is clarified that the tritium production can be very accurately predicted in the experiment without the reflector. In the mockups with the 12.6 and 25.2 mm thick tungsten armors, it is experimentally clarified that the integrated tritium productions are reduced by 3 and 6 % relative to the case without the armor, respectively.

  1. APEX ADVANCED FERRITIC STEEL, FLIBE SELF-COOLED FIRST WALL AND BLANKET DESIGN

    SciTech Connect (OSTI)

    WONG,CPC; MALANG,S; SAWAN,M; SVIATOSLAVSKY,I; MOGAHED,E; SMOLENTSEV,S; MAJUMDAR,S; MERRILL,B; MATTAS,R; FRIEND,M; BOLIN,J; SHARAFAT,S

    2003-11-01T23:59:59.000Z

    OAK-B135 As an element in the US Advanced Power Extraction (APEX) program, they evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the structural material and Flibe as the tritium breeder and coolant. They selected the recirculating flow configuration as the reference design. Based on the material properties of AFS, they found that the reference design can handle a maximum surface heat flux of 1 MW/m{sup 2}, and a maximum neutron wall loading of 5.4 MW/m{sup 2}, with a gross thermal efficiency of 47%, while meeting all the tritium breeding and structural design requirements. This paper covers the results of the following areas of evaluation: materials selection, first wall and blanket design configuration, materials compatibility, components fabrication, neutronics analysis, thermal hydraulics analysis including MHD effects, structural analysis, molten salt and helium closed cycle power conversion system, and safety and waste disposal of the recirculating coolant design.

  2. A Grid of NLTE Line-Blanketed Model Atmospheres of Early B-type Stars

    E-Print Network [OSTI]

    Thierry Lanz; Ivan Hubeny

    2006-11-29T23:59:59.000Z

    We have constructed a comprehensive grid of 1540 metal line-blanketed, NLTE, plane-parallel, hydrostatic model atmospheres for the basic parameters appropriate to early B-type stars. The BSTAR2006 grid considers 16 values of effective temperatures, 15,000 K grid complements our earlier OSTAR2002 grid of O-type stars (Lanz & Hubeny, 2003, ApJS, 146, 417). The paper contains a description of the BSTAR2006 grid and some illustrative examples and comparisons. NLTE ionization fractions, bolometric corrections, radiative accelerations, and effective gravities are obtained over the parameter range covered by the grid. By extrapolating radiative accelerations, we have determined an improved estimate of the Eddington limit in absence of rotation between 55,000 and 15,000 K. The complete BSTAR2006 grid is available at the TLUSTY website (http://nova.astro.umd.edu).

  3. Methods for threshold determination in multiplexed assays

    DOE Patents [OSTI]

    Tammero, Lance F. Bentley; Dzenitis, John M; Hindson, Benjamin J

    2014-06-24T23:59:59.000Z

    Methods for determination of threshold values of signatures comprised in an assay are described. Each signature enables detection of a target. The methods determine a probability density function of negative samples and a corresponding false positive rate curve. A false positive criterion is established and a threshold for that signature is determined as a point at which the false positive rate curve intersects the false positive criterion. A method for quantitative analysis and interpretation of assay results together with a method for determination of a desired limit of detection of a signature in an assay are also described.

  4. Training Certification Form (10-04) OFFICE OF RESEARCH SAFETY

    E-Print Network [OSTI]

    Kim, Duck O.

    Training Certification Form (10-04) OFFICE OF RESEARCH SAFETY TRAINING CERTIFICATION FORM Office-3826 The purpose of this form is to document training for those individuals who opt to use electronic media for required safety training. Prior to using this form and viewing a specific safety training module contact

  5. DARS Authorization Form Certificate in Engineering for Energy Sustainability

    E-Print Network [OSTI]

    Wisconsin at Madison, University of

    DARS Authorization Form Certificate in Engineering for Energy Sustainability College of Engineering and capstone projects must address energy sustainability in some manner and will be reviewed by the certificate the capstone requirement: Briefly describe your project and how it relates to energy sustainability (attach any

  6. Declaration of Intent Certificate in Engineering for Energy Sustainability

    E-Print Network [OSTI]

    Wisconsin at Madison, University of

    Declaration of Intent Certificate in Engineering for Energy Sustainability College of Engineering for Energy Sustainability. I am a degree-seeking undergraduate student with at least a 2.5 GPA. I have met:________________________ #12;Tentative Study Plan Certificate in Engineering for Energy Sustainability College of Engineering

  7. FROM NATIONAL APPROVAL SCHEME TO INTERNATIONAL CERTIFICATION SCHEME

    E-Print Network [OSTI]

    turbines has been performed since 1979. In January 2005 a certification scheme was introduced based on IEC certification standard "IEC WT 01" [5] and the load and safety standard "IEC 61400-1" [6] and "IEC 61400-2" [7 Turbines has been developed (IEC WT01) · Some procedures and requirements in the old system did not meet

  8. REEP-CERT 1 Renewable Energy Engineering and Policy Certificate

    E-Print Network [OSTI]

    Firestone, Jeremy

    REEP-CERT 1 Renewable Energy Engineering and Policy Certificate (REEP-CERT) Purpose This interdisciplinary Graduate Certificate in Renewable Energy Engineering and Policy (REEP- CERT) is offered-CERT will recognize the graduate student's interest and academic accomplishments in the field of renewable energy

  9. Plan for graduating with an Undergraduate Certificate in

    E-Print Network [OSTI]

    Zhou, Pei

    (ISIS) Name: Email Address: Declared Major: Minor or other Certificate Program: Anticipated Graduation ISIS 100 ISIS 140 / EGR 150/ COMPSCI 196 ISIS 200 Elective 1 Elective 2 Elective 3 The ISIS Certificate requires six courses: A. ISIS 100: Perspectives on Information Science and Information Studies B. For non

  10. Computational Science and Engineering Certification for Civil Engineering

    E-Print Network [OSTI]

    Gilbert, Matthew

    Computational Science and Engineering Certification for Civil Engineering The Computational Science that are distinct from already- required coursework. To receive a certificate in "Computational Science on the Computational Science and Engineering website: http://cse.illinois.edu/directory/faculty-affiliates. *** List

  11. Process and Product Certification Arguments -Getting the Balance Right

    E-Print Network [OSTI]

    Kelly, Tim

    that should be adopted by the development and assessment lifecycle. Product-based certification reliesProcess and Product Certification Arguments - Getting the Balance Right Ibrahim Habli Tim Kelly on the generation and assurance of product-specific evidence that meets safety requirements derived from hazard

  12. GUIDELINES FOR CERTIFICATION OF COMBINED HEAT AND POWER SYSTEMS

    E-Print Network [OSTI]

    CALIFORNIA ENERGY COMMISSION GUIDELINES FOR CERTIFICATION OF COMBINED HEAT AND POWER SYSTEMS for Certification of Combined Heat and Power Systems Pursuant to the Waste Heat and Carbon Emissions Reduction Act Heat and Power System Pursuant to the Waste Heat and Carbon Emissions Reduction Act, Public Utilities

  13. 2012-2013 Handbook Trinity College London Certificate in Teaching

    E-Print Network [OSTI]

    Mumby, Peter J.

    1 2012-2013 Handbook Trinity College London Certificate in Teaching English to Speakers of Other information 37 #12;3 Dear Student Welcome to your Trinity Certificate course in Teaching English to Speakers chosen field ­ but with a professional qualification as well. The Trinity Cert TESOL is well recognised

  14. Fractal Threshold Behavior in Vacuum Gravitational Collapse

    E-Print Network [OSTI]

    Sebastian J. Szybka; Tadeusz Chmaj

    2008-04-02T23:59:59.000Z

    We present the numerical evidence for fractal threshold behavior in the five dimensional vacuum Einstein equations satisfying the cohomogeneity-two triaxial Bianchi type-IX ansatz. In other words, we show that a flip of the wings of a butterfly may influence the process of the black hole formation.

  15. Hard Thresholding Pursuit Algorithms: Number of Iterations

    E-Print Network [OSTI]

    Hitczenko, Pawel

    algorithms do provide alternative methods. We consider here the hard thresholding pursuit (HTP) algorithm [6 us now recall that (HTP) consists in constructing a sequence (xn) of s-sparse vectors, starting absolute entries of xn-1 + A (y - Axn-1 ),(HTP1) xn := argmin{ y - Az 2, supp(z) Sn },(HTP2) until

  16. Multiple Sclerosis Luminance Threshold and Measurements

    E-Print Network [OSTI]

    Foster, David H.

    Multiple Sclerosis Luminance Threshold and Measurements of Temporal Characteristics of Vision Definite MS + 6/9 - + + 7/50/F Recurrent ON + 6/6 + - + 8/47/F Definite MS + 6/6 + + + · Luminance to te t the temporal properties of vi Ion were equalized with respect to Individual luminance thresh

  17. Reliability of underwater hearing thresholds in pinnipeds

    E-Print Network [OSTI]

    Reichmuth, Colleen

    Reliability of underwater hearing thresholds in pinnipeds Brandon L. Southall Long Marine and certain testing parameters (e.g., equipment and research personnel), measured underwater hearing (0.2­6.4 kHz). These data address the reliability of acoustic signal detection measurements over time

  18. Certificate Program Application | Photosynthetic Antenna Research Center

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting the TWPSuccessAlamos Laboratory NastasiPASTCentralCertificate Program

  19. Certificate in Environmental Monitoring Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting the TWPSuccessAlamos Laboratory NastasiPASTCentralCertificate

  20. Certifications and Professional Development | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov. Are you sure you want toworldPower 2010 1AAcquisitionDevelopment Certifications and

  1. Certificate of Current Cost and Pricing Data

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041clothAdvanced Materials Advanced. C o w l i t z C oCNMSStaffCerium Oxide Coating forCERTIFICATE OF

  2. Equipment Certification Requirements | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model,DOEHazel Crest,EnergySerranopolisEnviroMissionEquipment Certification

  3. L4 Certificate Leadership and Management Candidate Pack 2012-13[1].docx Level 4 Certificate in

    E-Print Network [OSTI]

    Mumby, Peter J.

    for establishing, maintaining and improving systems (eg quality, marketing, sales, energy, health and safety, etcL4 Certificate Leadership and Management Candidate Pack 2012-13[1].docx Page 1 Level 4 Certificate in Leadership and Management Candidate and Assessment Pack 2012/13 Clive Betts Centre Co-ordinator #12;L4

  4. Certification activities are the inevitable result of rapid industry growth. But what opportunities do certification programs afford and who benefits?

    E-Print Network [OSTI]

    Kurapov, Alexander

    education, and experience requirements based on a set of tasks identified through job analysis. To earn Certification Nov 1, 2004 By: Rebecca Somers Geospatial Solutions Page 1 of 4Geospatial Solutions - Demystifying Certification 11/8/04http://www.geospatial

  5. GIT Certificate Dr. Laurence W. Carstensen August 22, 2011 1 Graduate Level Geospatial Information Technology Certification Program

    E-Print Network [OSTI]

    Virginia Tech

    the College of Natural Resources has developed a PhD. in Geospatial and Environmental Analysis that beganGIT Certificate Dr. Laurence W. Carstensen August 22, 2011 1 Graduate Level Geospatial Information Technology Certification Program 1. Rationale and need: Geospatial information technology (GIT) includes

  6. Freeport LNG Development, L.P. (Freeport LNG)- Blanket Authorization to Export Previously Imported LNG- FE Dkt. No. 15-103-NG

    Broader source: Energy.gov [DOE]

    The Office of Fossil Energy gives notice of receipt of an Application filed June 25, 2015 by Freeport LNG Development, L.P. (Freeport LNG), requesting blanket authorization to export liquefied...

  7. APT Blanket System Loss-of-Coolant Accident Based on Initial Conceptual Design - Case 5: External RHR Break Near Inlet Header

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    This report is one of a series of reports that document normal operation and accident simulations for the Accelerator Production of Tritium (APT) blanket heat removal system. These simulations were performed for the Preliminary Safety Analysis Report.

  8. APT Blanket System Loss-of-Coolant Accident (LOCA) Based on Initial Conceptual Design - Case 4: External Pressurizer Surge Line Break Near Inlet Header

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    This report is one of a series of reports documenting accident scenario simulations for the Accelerator Production of Tritium (APT) blanket heat removal systems. The simulations were performed in support of the Preliminary Safety Analysis Report (PSAR) for the APT.

  9. Compliance, Certification and Enforcement for US Appliance and Equipment Energy Efficiency Programs by US DOE

    Office of Energy Efficiency and Renewable Energy (EERE)

    Information about energy and water conservation standards, ENERGY STAR, and compliance and certification enforcement.

  10. Proposal for the Award of a Blanket Contract for the Supply and Installation of Optical Fibre Cabling Systems

    E-Print Network [OSTI]

    2003-01-01T23:59:59.000Z

    This document concerns the award of a blanket contract for the supply and installation of optical fibre cabling systems. Following a market survey carried out among 41 firms in thirteen Member States, a call for tenders (IT-3120/ST/LHC) was sent on 26 February 2003 to three firms and two consortia each consisting of two firms, in six Member States. By the closing date, CERN had received five tenders from the three firms and two consortia in six Member States. The Finance Committee is invited to agree to the negotiation of a blanket contract with DRAKA (NL), the lowest bidder, for the supply and installation of optical fibre cabling systems for a total estimated amount not exceeding 12 150 000 Swiss francs, subject to revision for inflation from 1 January 2006. The firm has indicated the following distribution by country of the contract value covered by this adjudication proposal: NL - 38%; CH - 37%; DE - 12%; FR - 8%; GB - 5%.

  11. Lithium Ceramic Blankets for Russian Fusion Reactors and Influence of Breeding Operation Mode on Parameters of Reactor Tritium Systems

    SciTech Connect (OSTI)

    Kapyshev, Victor K.; Chernetsov, Mikhail Yu.; Zhevotov, Sergej I.; Kersnovskij, Alexandr Yu.; Kolbasov, Boris N.; Kovalenko, Victor G.; Paltusov, Nikolaj P.; Sernyaev, Georgeij A.; Sterebkov, Juri S.; Zyryanov, Alexej P. [A.A. Bochvar Institute of Inorganic Materials (Russian Federation)

    2005-07-15T23:59:59.000Z

    Russian controlled fusion program supposes development of a DEMO reactor design and participation in ITER Project. A solid breeder blanket of DEMO contains a ceramic lithium orthosilicate breeder and a beryllium multiplier. Test modules of the blanket are developed within the scope of ITER activities. Experimental models of module tritium breeding zones (TBZ), materials and fabrication technology of the TBZ, tritium reactor systems to analyse and process gas released from lithium ceramics are being developed. Two models of tritium breeding and neutron multiplying elements of the TBZ have been designed, manufactured and tested in IVV-2M nuclear reactor. Initial results of the in-pile experiments and outcome of lithium ceramics irradiation in a water-graphite nuclear reactor are considered to be a data base for development of the test modules and initial requirements for DEMO tritium system design. Influence of the tritium release parameters and hydrogen concentration in a purge gas on parameters of reactor system are discussed.

  12. Certification Plan, low-level waste Hazardous Waste Handling Facility

    SciTech Connect (OSTI)

    Albert, R.

    1992-06-30T23:59:59.000Z

    The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

  13. Results of an international study on a high-volume plasma-based neutron source for fusion blanket development

    SciTech Connect (OSTI)

    Abdou, M.A.; Ying, A. [Univ. of California, Los Angeles, CA (United States); Berk, S.E. [Department of Energy, Washington, DC (United States)] [and others

    1996-01-01T23:59:59.000Z

    A number of scenarios for fusion facilities were evaluated using a cost/benefit/risk analysis approach. Blanket tests in the International Thermonuclear Experimental Reactor (ITER) alone with a fluence of 1 MW.yr/m{sup 2} can address most of the needs for concept verification, but it cannot adequately address the blanket component reliability growth/demonstration testing requirements. An effective path to fusion DEMO is suggested. It involves two parallel facilities: (a) ITER to provide data on plasma performance, plasma support technology, and system integration and (b) a high-volume plasma-based neutron source (HVPNS) dedicated to testing, developing, and qualifying fusion nuclear components and material combinations for DEMO. For HVPNS to be attractive and cost effective, its capital cost must be significantly lower than ITER, and it should have low fusion power (nearly 150 MW). Exploratory studies indicate the presence of a design window with a highly driven plasma. A testing and development strategy that includes HVPNS would decisively reduce the high risk of initial DEMO operation with a poor blanket system availability and would make it possible - if operated parallel to the ITER basic performance phase - to meet the goal of DEMO operation by the year 2025. Such a scenario with HVPNS parallel to ITER provides substantial savings in the overall R&D cost toward DEMO compared with an ITER-alone strategy. 75 refs., 13 figs., 31 tabs.

  14. Threshold photodetachment spectroscopy of negative ions

    SciTech Connect (OSTI)

    Kitsopoulos, T.N.

    1991-12-01T23:59:59.000Z

    This thesis is concerned with the development and application of high resolution threshold photodetachment spectroscopy of negative ions. Chapter I deals with the principles of our photodetachment technique, and in chapter II a detailed description of the apparatus is presented. The threshold photodetachment spectra of I{sup {minus}}, and SH{sup {minus}}, presented in the last sections of chapter II, indicated that a resolution of 3 cm{sup {minus}1} can be achieved using our technique. In chapter III the threshold photodetachment spectroscopy study of the transition state region of I + HI and I + Di reactions is discussed. Our technique probes the transition state region directly, and the results of our study are the first unambiguous observations of reactive resonances in a chemical reaction. Chapters IV, V and VI are concerned with the spectroscopy of small silicon and carbon clusters. From our spectra we were able to assign electronic state energies and vibrational frequencies for the low lying electronics states of Si{sub n} (n=2,3,4), C{sub 5} and their corresponding anions.

  15. The Value of a dynamic Environmental Building Certification

    E-Print Network [OSTI]

    Sutton, H. M.

    2013-01-01T23:59:59.000Z

    dynamic certification program (ICEBO 2013) SCOTIA?CENTRE,?St.?John?s East?Port?Properties? 1.Scoping 2.Benchmarking 3.Low?hanging?fruit?? management 4.Low?hanging?fruit?? performance 5.Capital?investments The BOMA BESt Certification Process can...?meaning?to?tenant?efforts ? Personal?connection?to?the?community?around?the? building ? Tenants?will?be?more?compelled?to?help?building? management?in?a?host?of?other?areas. long?lasting?change! BOMA BESt ? a dynamic certification program (ICEBO 2013) ? Conservation...

  16. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-01T23:59:59.000Z

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In addition, a TRU waste is eligible for disposal at WIPP only if it has been generated in whole or in part by one or more of the activities listed in Section 10101(3) of the Nuclear Waste Policy Act. DOE sites must determine that each waste stream to be disposed of at WIPP is ''defense'' TRU waste. (See also the definition of ''defense'' TRU waste.). Only CH TRU wastes meeting the requirements of the QAPjP, WIPP-WAP, WPP-WAC, and other requirements documents described above will be accepted for transportation and disposal at WIPP.

  17. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-06T23:59:59.000Z

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In addition, a TRU waste is eligible for disposal at WIPP only if it has been generated in whole or in part by one or more of the activities listed in Section 10101(3) of the Nuclear Waste Policy Act. DOE sites must determine that each waste stream to be disposed of at WIPP is ''defense'' TRU waste. (See also the definition of ''defense'' TRU waste.). Only CH TRU wastes meeting the requirements of the QAPjP, WIPP-WAP, WPP-WAC, and other requirements documents described above will be accepted for transportation and disposal at WIPP.

  18. Optimization Online - A Counterexample to “Threshold Boolean form ...

    E-Print Network [OSTI]

    James Luedtke

    2015-01-02T23:59:59.000Z

    Jan 2, 2015 ... ... to “Threshold Boolean form for joint probabilistic constraints with random technology matrix” ... the Mathematical Optmization Society.

  19. Fault-Tolerant Thresholds for Encoded Ancillae with Homogeneous Errors

    E-Print Network [OSTI]

    Bryan Eastin

    2006-11-14T23:59:59.000Z

    I describe a procedure for calculating thresholds for quantum computation as a function of error model given the availability of ancillae prepared in logical states with independent, identically distributed errors. The thresholds are determined via a simple counting argument performed on a single qubit of an infinitely large CSS code. I give concrete examples of thresholds thus achievable for both Steane and Knill style fault-tolerant implementations and investigate their relation to threshold estimates in the literature.

  20. Fast Ion Effects During Test Blanket Module Simulation Experiments in DIII-D

    SciTech Connect (OSTI)

    Kramer, G J; Ellis, R; Gorelenkova, M; Heidbrink, W W; Kurki-Suonio, T; Nazikian, R; Salmi, A; Schaffer, M J; Shinohara, K; Snipes, J A; Spong, D A; Koskela, T

    2011-06-03T23:59:59.000Z

    Fast beam-ion losses were studied in DIII-D in the presence of a scaled mockup of two Test Blanket Modules (TBM) for ITER. Heating of the protective tiles on the front of the TBM surface was found when neutral beams were injected and the TBM fields were engaged. The fast-ion core confinement was not significantly affected. Different orbit-following codes predict the formation of a hot spot on the TBM surface arising from beam-ions deposited near the edge of the plasma. The codes are in good agreement with each other on the total power deposited at the hot spot predicting an increase in power with decreasing separation between the plasma edge and the TBM surface. A thermal analysis of the heat flow through the tiles shows that the simulated power can account for the measured tile temperature rise. The thermal analysis, however, is very sensitive to the details of the localization of the hot spot which is predicted to be different among the various codes.

  1. Physical Model Development and Benchmarking for MHD Flows in Blanket Design

    SciTech Connect (OSTI)

    Ramakanth Munipalli; P.-Y.Huang; C.Chandler; C.Rowell; M.-J.Ni; N.Morley; S.Smolentsev; M.Abdou

    2008-06-05T23:59:59.000Z

    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. A sequence of theoretical and experimental results was used to verify and validate the results obtained. The code was applied to a complete DCLL module simulation study with promising results.

  2. Non-destructive assay of EBR-II blanket elements using resonance transmission analysis.

    SciTech Connect (OSTI)

    Klann, R.T.; Poenitz, W.P.

    1998-09-11T23:59:59.000Z

    Resonance transmission analysis utilizing a faltered reactor beam was examined as a means of determining the {sup 239}Pu content in Experimental Breeder Reactor-II depleted uranium blanket elements. The technique uses cadmium and gadolinium falters along with a {sup 239}Pu fission chamber to isolate the 0.3 eV resonance in {sup 239}Pu. In the energy range of this resonance (0.1 eV to 0.5 ev), the total microscopic cross-section of {sup 239}Pu is significantly greater than the cross-sections of {sup 238}U and {sup 235}U. This large difference allows small changes in the {sup 239}Pu content of a sample to result in large changes in the mass signal response. Tests with small stacks of depleted uranium and {sup 239}Pu foils indicate a significant change in response based on the {sup 239}Pu content of the foil stack. In addition, the tests indicate good agreement between the measured and predicted values of {sup 239}Pu up to approximately two weight percent.

  3. Analysis of the separation of protium from blanket tritium-product streams

    SciTech Connect (OSTI)

    Misra, B.; Maroni, V.A.

    1981-07-01T23:59:59.000Z

    The case is considered in which the blanket product stream has been purified to the point where only protium, tritium, and a small quantity of deuterium remain. A cryogenic distillation cascade concept developed specifically to handle this enrichment problem is shown. The concept is based on a series of distillation columns and equilibrators capable of producing a protium-rich stream containing less than 1000 appm T and a tritium-rich stream containing less than 2000 appm H. It is envisioned that both of these streams could be blended with streams of comparable composition in the mainstream position of the fuel cycle without further processing. The computational analysis of the cascade was based on a fixed arrangement of columns and equilibrators and a fixed number of theoretical plates per columns, since these features are less easily varied in an actual system than reflux ratios and flow rates. In order to test the flexibility of this conceptual enruchment system to adjust to variations of the H/T ratio in the feed, H/T values of 0.333, 1.00, and 3.00 were investigated.

  4. A Thermal Discrete Element Analysis of EU Solid Breeder Blanket subjected to Neutron Irradiation

    E-Print Network [OSTI]

    Yixiang Gan; Francisco Hernandez; Dorian Hanaor; Ratna Annabattula; Marc Kamlah; Pavel Pereslavtsev

    2014-06-17T23:59:59.000Z

    Due to neutron irradiation, solid breeder blankets are subjected to complex thermo-mechanical conditions. Within one breeder unit, the ceramic breeder bed is composed of spherical-shaped lithium orthosilicate pebbles, and as a type of granular material, it exhibits strong coupling between temperature and stress fields. In this paper, we study these thermo-mechanical problems by developing a thermal discrete element method (Thermal-DEM). This proposed simulation tool models each individual ceramic pebble as one element and considers grain-scale thermo-mechanical interactions between elements. A small section of solid breeder pebble bed in HCPB is modelled using thousands of individual pebbles and subjected to volumetric heating profiles calculated from neutronics under ITER-relevant conditions. We consider heat transfer at the grain-scale between pebbles through both solid-to-solid contacts and the interstitial gas phase, and we calculate stresses arising from thermal expansion of pebbles. The overall effective conductivity of the bed depends on the resulting compressive stress state during the neutronic heating. The thermal-DEM method proposed in this study provides the access to the grain-scale information, which is beneficial for HCPB design and breeder material optimization, and a better understanding of overall thermo-mechanical responses of the breeder units under fusion-relevant conditions.

  5. Applications for Certificates for Electric Generation Facilities (Ohio)

    Broader source: Energy.gov [DOE]

    An applicant for a certificate to site an electric power generating facility shall provide a project summary and overview of the proposed project. In general, the summary should be suitable as a...

  6. Clean Water Act Section 401 Water Quality Certification: A Water...

    Open Energy Info (EERE)

    Clean Water Act Section 401 Water Quality Certification: A Water Quality Protection Tool for States and Tribes Jump to: navigation, search OpenEI Reference LibraryAdd to library...

  7. ADVANCED BUSINESS CERTIFICATE (ABC) HEALTH CARE FINANCE AND INSURANCE

    E-Print Network [OSTI]

    Alpay, S. Pamir

    Management (HSMG 5686) Global Healthcare Systems (HSMG 5687) Risk Management and Quality Across Borders (HSMG Management & Insurance Studies offers an Advanced Business Certificate for business professionals who, hospitals, health plans, pharmaceutical companies, long-term care facilities, physician practice management

  8. Waste certification program plan for Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Kornegay, F.C.

    1996-09-01T23:59:59.000Z

    This document defines the waste certification program being developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in U.S. Department of Energy (DOE) Order 5820.2A, Radioactive Waste Management, and ensures that 40 CFR documentation requirements for waste characterization are met for mixed (both radioactive and hazardous) and hazardous (including polychlorinated biphenyls) waste. Program activities will be conducted according to ORNL Level 1 document requirements.

  9. Gainful Employment Program Information Certificate Name Global Health 1

    E-Print Network [OSTI]

    Scharfstein, Daniel

    Credential Level PostBaccalaureate Certificate Occupations and SOC Codes View O*Net occupational profiles countries and interested in expanding their global health skills and knowledge. It is also offered

  10. The effect of teacher certification on student achievement

    E-Print Network [OSTI]

    Sparks, Karin

    2005-08-29T23:59:59.000Z

    The purpose of this study was to review the empirical research evidence on the effect of teacher certification on student achievement. An exploratory meta-analysis was conducted on studies that examined the effect of fully certified and less...

  11. Professional, Applied & Continuing Education INFORMATION ASSURANCE & SECURITY CERTIFICATE

    E-Print Network [OSTI]

    Martin, Jeff

    Professional, Applied & Continuing Education INFORMATION ASSURANCE & SECURITY CERTIFICATE Demand for technical security and information assurance professionals has risen dramatically in recent years OPPORTUNITIES: TUITION: Required Courses (78 Hours): · Information Assurance and Security Level 1: Information

  12. Development of Conceptual Framework Renewable Energy Certificate Mechanism for India

    E-Print Network [OSTI]

    Columbia University

    Delhi Electricity Regulatory Commission DMRPS Dynamic Minimum Renewable Purchase Standard EA 2003 Renewable Obligation Certificate RPS Renewable Purchase Specification RPO Renewable Purchase Obligation RPC Regional Power Committee Rs Rupees SERC State Electricity Regulatory Commission SLDC State Load Despatch

  13. EPRI PEAC Corp.: Certification Model Program and Interconnection Agreement Tools

    SciTech Connect (OSTI)

    Not Available

    2003-10-01T23:59:59.000Z

    Summarizes the work of EPRI PEAC Corp., under contract to DOE's Distribution and Interconnection R&D, to develop a certification model program and interconnection agreement tools to support the interconnection of distributed energy resources.

  14. University of Oklahoma Receipt of FMLA Information Certification

    E-Print Network [OSTI]

    Oklahoma, University of

    University of Oklahoma Receipt of FMLA Information Certification This original document is to be returned to the Office of Human Resources / Employee Relations - NEL 259 - Norman, Oklahoma 73019. If you

  15. Rules Governing Water and Wastewater Operator Certification (Tennessee)

    Broader source: Energy.gov [DOE]

    The Rules Governing Water and Wastewater Operator Certification are applicable to all projects that will require a water treatment site. Everyone who plans to operate a wastewater or water...

  16. NANOTECHNOLOGY CERTIFICATE PROGRAM PRE-SURVEY What is Nanotechnology?

    E-Print Network [OSTI]

    Bennett, Gisele

    NANOTECHNOLOGY CERTIFICATE PROGRAM PRE-SURVEY What is Nanotechnology? Nanotechnology is the engineering of functional systems at length scales spanning 1 ­ 100 nm.nano.gatech.edu Why should I study Nanotechnology? Nanotechnology education will prepare you for exciting career

  17. HPE Fitness and Wellness Certificate Completion Form Instructions As you are nearing completion of (or have already completed) your Fitness and Wellness Credit Certificate, this is the

    E-Print Network [OSTI]

    Alabama in Huntsville, University of

    HPE Fitness and Wellness Certificate Completion Form Instructions As you are nearing completion of (or have already completed) your Fitness and Wellness Credit Certificate, this is the final step met, individuals must submit a completed HPE Fitness and Wellness Credit Certificate Completion Form

  18. On the measurement of laser-induced plasma breakdown thresholds

    SciTech Connect (OSTI)

    Brieschenk, Stefan [Centre for Hypersonics, The University of Queensland, Brisbane 4072 (Australia)] [Centre for Hypersonics, The University of Queensland, Brisbane 4072 (Australia); Kleine, Harald; O'Byrne, Sean [The University of New South Wales Canberra, The Australian Defence Force Academy, Canberra 2600 (Australia)] [The University of New South Wales Canberra, The Australian Defence Force Academy, Canberra 2600 (Australia)

    2013-09-07T23:59:59.000Z

    The breakdown threshold of a gas exposed to intense laser-radiation is a function of gas and laser properties. Breakdown thresholds reported in the literature often vary greatly and these differences can partially be traced back to the method that is typically used to determine breakdown thresholds. This paper discusses the traditional method used to determine breakdown thresholds and the potential errors that can arise using this approach, and presents an alternative method which can yield more accurate data especially when determining breakdown thresholds as functions of gas pressure.

  19. The AMS-01 Aerogel Threshold Cherenkov counter

    E-Print Network [OSTI]

    D. Barancourt; F. Barao; G. Barbier; G. Barreira; M. Buenerd; G. Castellini; E. Choumilov; J. Favier; N. Fouque; A. Gougas; V. Hermel; R. Kossakowski; G. Laborie; G. Laurenti; S. -C. Lee; F. Mayet; B. Meillon; Y. -T. Oyang; V. Plyaskin; V. Pojidaev; C. Rossin; D. Santos; F. Vezzu; J. P. Vialle

    2000-10-12T23:59:59.000Z

    The Alpha Magnetic Spectrometer in a precursor version (AMS-01), was flown in June 1998 on a 51.6 degrees orbit and at altitudes ranging between 320 and 390 km, on board of the space shuttle Discovery (flight STS-91). AMS-01 included an Aerogel Threshold Cherenkov counter (ATC) to separate antiprotons from electrons and positrons from protons, for momenta below 3.5 GeV/c. This paper presents a description of the ATC counter and reports on its performances during the flight STS-91.

  20. Quark mass thresholds in QCD thermodynamics

    E-Print Network [OSTI]

    M. Laine; Y. Schroder

    2006-05-05T23:59:59.000Z

    We discuss radiative corrections to how quark mass thresholds are crossed, as a function of the temperature, in basic thermodynamic observables such as the pressure, the energy and entropy densities, and the heat capacity of high temperature QCD. The indication from leading order that the charm quark plays a visible role at surprisingly low temperatures, is confirmed. We also sketch a way to obtain phenomenological estimates relevant for generic expansion rate computations at temperatures between the QCD and electroweak scales, pointing out where improvements over the current knowledge are particularly welcome.

  1. Threshold 21 Model | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro Industries PvtStratosolarTharaldson Ethanol LLCEnergyoThornwood, NewThreshold 21 Model Jump

  2. Threshold shift and above-threshold multiphoton ionization of atomic hydrogen in intense laser fields

    E-Print Network [OSTI]

    Chu, Shih-I; Cooper, J.

    1985-11-01T23:59:59.000Z

    , while hE, =e F /4m co~ = e F s/2m' is the continuum threshold upshift. 1 e 2@2 4 Itt CO and the threshold shift as (3) 0.28 0.01 0.025 0.05 0.075 —1.185(—2) —6.732( —2) —2.036( —1) —3.306( —1) 1.735{—2) 1.085( —1) 4.339(—1) 9.762( —1) 2.92( —2) 1.76( —1...

  3. Certificate in Geographic Information Science The Environmental Science programs and the Departments of Earth Sciences and Biology offer

    E-Print Network [OSTI]

    Adl, Sina

    Certificate in Geographic Information Science The Environmental Science programs and the Departments of Earth Sciences and Biology offer a Certificate in Geographic Information Science information science. This Certificate can be completed by a student in a BSc program, in addition

  4. Uranium Transport in a High-Throughput Electrorefiner for EBR-II Blanket Fuel

    SciTech Connect (OSTI)

    Ahluwalia, Rajesh K.; Hua, Thanh Q.; Vaden, DeeEarl [Argonne National Laboratory (United States)

    2004-01-15T23:59:59.000Z

    A unique high-throughput Mk-V electrorefiner is being used in the electrometallurgical treatment of the metallic sodium-bonded blanket fuel from the Experimental Breeder Reactor II. Over many cycles, it transports uranium back and forth between the anodic fuel dissolution baskets and the cathode tubes until, because of imperfect adherence of the dendrites, it all ends up in the product collector at the bottom. The transport behavior of uranium in the high-throughput electrorefiner can be understood in terms of the sticking coefficients for uranium adherence to the cathode tubes in the forward direction and to the dissolution baskets in the reverse direction. The sticking coefficients are inferred from the experimental voltage and current traces and are correlated in terms of a single parameter representing the ratio of the cell current to the limiting current at the surface acting as the cathode. The correlations are incorporated into an engineering model that calculates the transport of uranium in the different modes of operation. The model also uses the experimentally derived electrorefiner operating maps that describe the relationship between the cell voltage and the cell current for the three principal transport modes. It is shown that the model correctly simulates the cycle-to-cycle variation of the voltage and current profiles. The model is used to conduct a parametric study of electrorefiner throughput rate as a function of the principal operating parameters. The throughput rate is found to improve with lowering of the basket rotation speed, reduction of UCl{sub 3} concentration in salt, and increasing the maximum cell current or cut-off voltage. Operating conditions are identified that can improve the throughput rate by 60 to 70% over that achieved at present.

  5. Superlinear threshold detectors in quantum cryptography

    SciTech Connect (OSTI)

    Lydersen, Lars; Maroey, Oystein; Skaar, Johannes; Makarov, Vadim [Department of Electronics and Telecommunications, Norwegian University of Science and Technology, NO-7491 Trondheim (Norway); University Graduate Center, NO-2027 Kjeller (Norway); Jain, Nitin; Wittmann, Christoffer; Marquardt, Christoph; Leuchs, Gerd [Max Planck Institute for the Science of Light, Guenther-Scharowsky-Strasse 1/Bau 24, DE-91058 Erlangen (Germany); Institut fuer Optik, Information und Photonik, University of Erlangen-Nuremberg, Staudtstrasse 7/B2, DE-91058 Erlangen (Germany)

    2011-09-15T23:59:59.000Z

    We introduce the concept of a superlinear threshold detector, a detector that has a higher probability to detect multiple photons if it receives them simultaneously rather than at separate times. Highly superlinear threshold detectors in quantum key distribution systems allow eavesdropping the full secret key without being revealed. Here, we generalize the detector control attack, and analyze how it performs against quantum key distribution systems with moderately superlinear detectors. We quantify the superlinearity in superconducting single-photon detectors based on earlier published data, and gated avalanche photodiode detectors based on our own measurements. The analysis shows that quantum key distribution systems using detector(s) of either type can be vulnerable to eavesdropping. The avalanche photodiode detector becomes superlinear toward the end of the gate. For systems expecting substantial loss, or for systems not monitoring loss, this would allow eavesdropping using trigger pulses containing less than 120 photons per pulse. Such an attack would be virtually impossible to catch with an optical power meter at the receiver entrance.

  6. Directory of Certificates of Compliance for radioactive materials packages: Certificates of Compliance. Volume 2, Revision 18

    SciTech Connect (OSTI)

    NONE

    1995-10-01T23:59:59.000Z

    The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 of approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date.

  7. Neutronics Design of a Thorium-Fueled Fission Blanket for LIFE (Laser Inertial Fusion-based Energy)

    SciTech Connect (OSTI)

    Powers, J; Abbott, R; Fratoni, M; Kramer, K; Latkowski, J; Seifried, J; Taylor, J

    2010-03-08T23:59:59.000Z

    The Laser Inertial Fusion-based Energy (LIFE) project at LLNL includes development of hybrid fusion-fission systems for energy generation. These hybrid LIFE engines use high-energy neutrons from laser-based inertial confinement fusion to drive a subcritical blanket of fission fuel that surrounds the fusion chamber. The fission blanket contains TRISO fuel particles packed into pebbles in a flowing bed geometry cooled by a molten salt (flibe). LIFE engines using a thorium fuel cycle provide potential improvements in overall fuel cycle performance and resource utilization compared to using depleted uranium (DU) and may minimize waste repository and proliferation concerns. A preliminary engine design with an initial loading of 40 metric tons of thorium can maintain a power level of 2000 MW{sub th} for about 55 years, at which point the fuel reaches an average burnup level of about 75% FIMA. Acceptable performance was achieved without using any zero-flux environment 'cooling periods' to allow {sup 233}Pa to decay to {sup 233}U; thorium undergoes constant irradiation in this LIFE engine design to minimize proliferation risks and fuel inventory. Vast reductions in end-of-life (EOL) transuranic (TRU) inventories compared to those produced by a similar uranium system suggest reduced proliferation risks. Decay heat generation in discharge fuel appears lower for a thorium LIFE engine than a DU engine but differences in radioactive ingestion hazard are less conclusive. Future efforts on development of thorium-fueled LIFE fission blankets engine development will include design optimization, fuel performance analysis work, and further waste disposal and nonproliferation analyses.

  8. U-217: Red Hat Certificate System Bugs Let Remote Users Conduct Cross-Site Scripting and Denial of Service Attacks

    Broader source: Energy.gov [DOE]

    Two vulnerabilities were reported in Red Hat Certificate System. A remote user can conduct cross-site scripting attacks. A remote authenticated user can revoke the CA certificate.

  9. The Treatment of Renewable Energy Certificates, Emissions Allowances, and Green Power Programs in State Renewables Portfolio Standards

    E-Print Network [OSTI]

    Holt, Edward A.; Wiser, Ryan H.

    2007-01-01T23:59:59.000Z

    Design Guide for Renewable Energy Certificate Tracking2005. “Emerging Markets for Renewable Energy Certificates:Golden, CO: National Renewable Energy Laboratory. http://

  10. Removal plan for Shippingport pressurized water reactor core 2 blanket fuel assemblies form T plant to the canister storage building

    SciTech Connect (OSTI)

    Lata

    1996-09-26T23:59:59.000Z

    This document presents the current strategy and path forward for removal of the Shippingport Pressurized Water Reactor Core 2 blanket fuel assemblies from their existing storage configuration (wet storage within the T Plant canyon) and transport to the Canister Storage Building (designed and managed by the Spent Nuclear Fuel. Division). The removal plan identifies all processes, equipment, facility interfaces, and documentation (safety, permitting, procedures, etc.) required to facilitate the PWR Core 2 assembly removal (from T Plant), transport (to the Canister storage Building), and storage to the Canister Storage Building. The plan also provides schedules, associated milestones, and cost estimates for all handling activities.

  11. SOLVING THE STAND-OFF PROBLEM FOR MAGNETIZED TARGET FUSION: PLASMA STREAMS AS DISPOSABLE ELECTRODES, PLUS A LOCAL SPHERICAL BLANKET

    SciTech Connect (OSTI)

    Ryutov, D D; Thio, Y F

    2006-03-21T23:59:59.000Z

    In a fusion reactor based on the Magnetized Target Fusion approach, the permanent power supply has to deliver currents up to a few mega-amperes to the target dropped into the reaction chamber. All the structures situated around the target will be destroyed after every pulse and have to be replaced at a frequency of 1 to 10 Hz. In this paper, an approach based on the use of spherical blanket surrounding the target, and pulsed plasma electrodes connecting the target to the power supply, is discussed. A brief physic analysis of the processes associated with creation of plasma electrodes is discussed.

  12. Trace Fission Product Ratios for Nuclear Forensics Attribution of Weapons-Grade Plutonium from Fast Breeder Reactor Blankets

    E-Print Network [OSTI]

    Osborn, Jeremy

    2014-08-13T23:59:59.000Z

    ), whereas that used in an FBR blanket fuel is depleted uranium (0.25 atom percent 235U). The energy production in the FBR core is from the seed fuel subassemblies containing mixed oxides (MOX) of PuO2 and UO2. A plot of fast and thermal neutron energy... of the program involves a fleet of fast breeder reactors. The stage two fast breeder reactors, beginning with the PFBR, will be fueled with reactor-grade plutonium and depleted uranium from the reprocessed spent fuel of stage one reactors and will breed more...

  13. Hanford site transuranic waste certification plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-05-12T23:59:59.000Z

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP).

  14. The (Unstable) Threshold of Black Hole Formation

    E-Print Network [OSTI]

    M. W. Choptuik

    1998-03-23T23:59:59.000Z

    In recent years it has become apparent that intriguing phenomenology exists at the threshold of black hole formation in a large class of general relativistic collapse models. This phenomenology, which includes scaling, self-similarity and universality, is largely analogous to statistical mechanical critical behaviour, a fact which was first noted empirically, and subsequently clarified by perturbative calculations which borrow on ideas and techniques from dynamical systems theory and renormalization group theory. This contribution, which closely parallels my talk at the conference, consists of an overview of the considerable ``zoo''' of critical solutions which have been discovered thus far, along with a brief discussion of how we currently understand the nature of these solutions from the point of view of perturbation theory.

  15. Optical ranked-order filtering using threshold decomposition

    DOE Patents [OSTI]

    Allebach, J.P.; Ochoa, E.; Sweeney, D.W.

    1987-10-09T23:59:59.000Z

    A hybrid optical/electronic system performs median filtering and related ranked-order operations using threshold decomposition to encode the image. Threshold decomposition transforms the nonlinear neighborhood ranking operation into a linear space-invariant filtering step followed by a point-to-point threshold comparison step. Spatial multiplexing allows parallel processing of all the threshold components as well as recombination by a second linear, space-invariant filtering step. An incoherent optical correlation system performs the linear filtering, using a magneto-optic spatial light modulator as the input device and a computer-generated hologram in the filter plane. Thresholding is done electronically. By adjusting the value of the threshold, the same architecture is used to perform median, minimum, and maximum filtering of images. A totally optical system is also disclosed. 3 figs.

  16. Optical ranked-order filtering using threshold decomposition

    DOE Patents [OSTI]

    Allebach, Jan P. (West Lafayette, IN); Ochoa, Ellen (Pleasanton, CA); Sweeney, Donald W. (Alamo, CA)

    1990-01-01T23:59:59.000Z

    A hybrid optical/electronic system performs median filtering and related ranked-order operations using threshold decomposition to encode the image. Threshold decomposition transforms the nonlinear neighborhood ranking operation into a linear space-invariant filtering step followed by a point-to-point threshold comparison step. Spatial multiplexing allows parallel processing of all the threshold components as well as recombination by a second linear, space-invariant filtering step. An incoherent optical correlation system performs the linear filtering, using a magneto-optic spatial light modulator as the input device and a computer-generated hologram in the filter plane. Thresholding is done electronically. By adjusting the value of the threshold, the same architecture is used to perform median, minimum, and maximum filtering of images. A totally optical system is also disclosed.

  17. EPA ENERGY STAR Webinar: How to Apply for the ENERGY STAR Certification

    Broader source: Energy.gov [DOE]

    Join us to learn about applying for ENERGY STAR Certification in Portfolio Manager. Understand the value of the ENERGY STAR certification, see the step-by-step process of applying, and gain tips to...

  18. Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog technology; successfully completed the certification exam for the American Registry of Radiologic Technology

  19. European Aviation Safety Agency announces acceptance of NCAMP material certification process

    E-Print Network [OSTI]

    developed through the FAA process described in Federal Aviation Administration Memorandum AIR100European Aviation Safety Agency announces acceptance of NCAMP material certification process Wichita, KS, January 30, 2014 ­ The European Aviation Safety Agency (EASA) recently released Certification

  20. CASE STUDY 95-04: Operator Certification: A Case Study in Operator Self-Inspection

    E-Print Network [OSTI]

    Cowap, Stacey

    1996-02-22T23:59:59.000Z

    Operator certification is the process where production workers are trained, authorized, and given the necessary resources to inspect their own work. This case study evaluated operator certification systems in the manufacturing ...

  1. An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design

    SciTech Connect (OSTI)

    Wong, Clement; Malang, S.; Sawan, M.; Dagher, Mohamad; Smolentsev, S.; Merrill, Brad; Youssef, M.; Reyes, Susanna; Sze, Dai Kai; Morley, Neil B.; Sharafat, Shahran; Calderoni, P.; Sviatoslavsky, G.; Kurtz, Richard J.; Fogarty, Paul J.; Zinkle, Steven J.; Abdou, Mohamed A.

    2006-02-01T23:59:59.000Z

    An attractive blanket concept for the fusion reactor is the dual coolant Pb-17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb-17LI is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetohydrodynamic (MHD) insulation to reduce the impact from the MHD pressure drop of the circulating Ph-17Li and as the thermal insulator to separate the high temperature Pb-17Li from the helium cooled RAFS structure.

  2. Method and system to directly produce electrical power within the lithium blanket region of a magnetically confined, deuterium-tritium (DT) fueled, thermonuclear fusion reactor

    DOE Patents [OSTI]

    Woolley, Robert D. (Belle Mead, NJ)

    1999-01-01T23:59:59.000Z

    A method for integrating liquid metal magnetohydrodynamic power generation with fusion blanket technology to produce electrical power from a thermonuclear fusion reactor located within a confining magnetic field and within a toroidal structure. A hot liquid metal flows from a liquid metal blanket region into a pump duct of an electromagnetic pump which moves the liquid metal to a mixer where a gas of predetermined pressure is mixed with the pressurized liquid metal to form a Froth mixture. Electrical power is generated by flowing the Froth mixture between electrodes in a generator duct. When the Froth mixture exits the generator the gas is separated from the liquid metal and both are recycled.

  3. TRISO-Fuel Element Performance Modeling for the Hybrid LIFE Engine with Pu Fuel Blanket

    SciTech Connect (OSTI)

    DeMange, P; Marian, J; Caro, M; Caro, A

    2010-02-18T23:59:59.000Z

    A TRISO-coated fuel thermo-mechanical performance study is performed for the hybrid LIFE engine to test the viability of TRISO particles to achieve ultra-high burnup of a weapons-grade Pu blanket. Our methodology includes full elastic anisotropy, time and temperature varying material properties for all TRISO layers, and a procedure to remap the elastic solutions in order to achieve fast fluences up to 30 x 10{sup 25} n {center_dot} m{sup -2} (E > 0.18 MeV). In order to model fast fluences in the range of {approx} 7 {approx} 30 x 10{sup 25} n {center_dot} m{sup -2}, for which no data exist, careful scalings and extrapolations of the known TRISO material properties are carried out under a number of potential scenarios. A number of findings can be extracted from our study. First, failure of the internal pyrolytic carbon (PyC) layer occurs within the first two months of operation. Then, the particles behave as BISO-coated particles, with the internal pressure being withstood directly by the SiC layer. Later, after 1.6 years, the remaining PyC crumbles due to void swelling and the fuel particle becomes a single-SiC-layer particle. Unrestrained by the PyC layers, and at the temperatures and fluences in the LIFE engine, the SiC layer maintains reasonably-low tensile stresses until the end-of-life. Second, the PyC creep constant, K, has a striking influence on the fuel performance of TRISO-coated particles, whose stresses scale almost inversely proportional to K. Obtaining more reliable measurements, especially at higher fluences, is an imperative for the fidelity of our models. Finally, varying the geometry of the TRISO-coated fuel particles results in little differences in the scope of fuel performance. The mechanical integrity of 2-cm graphite pebbles that act as fuel matrix has also been studied and it is concluded that they can reliable serve the entire LIFE burnup cycle without failure.

  4. anisotropy instability thresholds: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    these fluctuations are enhanced along the temperature anisotropy thresholds of the mirror, proton oblique firehose, and ion cyclotron instabilities. In addition, the measured...

  5. Sequential Threshold Control in Descent Splitting Methods for ...

    E-Print Network [OSTI]

    2014-11-21T23:59:59.000Z

    Nov 5, 2014 ... coordinate-wise steps together with a special threshold control. ... the computational process and leads to the (forward-backward) splitting ...

  6. ASSESSMENT OF FIRST WALL AND BLANKET OPTIONS WITH THE USE OF LIQUID BREEDER C.P.C. Wong, S. Malang,1 M. Sawan,2 S. Smolentsev,3 S. Majumdar,4 B. Merrill,5 D.K. Sze,6 N. Morley,3

    E-Print Network [OSTI]

    Abdou, Mohamed

    ASSESSMENT OF FIRST WALL AND BLANKET OPTIONS WITH THE USE OF LIQUID BREEDER C.P.C. Wong, S. Malang.S. blanket design team has proposed to focus on the self-cooled (SC) and dual- coolant (DC) liquid breeder of liquid breeder blanket options for an advanced reactor design. These options include self-cooled (SC

  7. Please cite this article in press as: G. Prez, et al., Optimized mass flow rate distribution analysis for cooling the ITER Blanket System, Fusion Eng. Des. (2014), http://dx.doi.org/10.1016/j.fusengdes.2014.03.002

    E-Print Network [OSTI]

    Raffray, A. René

    2014-01-01T23:59:59.000Z

    analysis for cooling the ITER Blanket System, Fusion Eng. Des. (2014), http://dx.doi.org/10.1016/j.elsevier.com/locate/fusengdes Optimized mass flow rate distribution analysis for cooling the ITER Blanket System Germán Pérez , Raphaël: ITER Blanket System Mass flow rate Critical heat flux a b s t r a c t This paper presents the rationale

  8. Activation Analysis for Two Molten Salt Dual-Coolant Blanket Concepts for the U.S. Demo Reactor

    SciTech Connect (OSTI)

    Youssef, M.Z. [University of California-Los Angeles (United States); Sawan, M.E. [University of Wisconsin-Madison (United States)

    2005-04-15T23:59:59.000Z

    The US has considered, among other options, two blanket concepts for Demo reactor in which helium is primarily used to cool the first wall (FW) and structure whereas molten salt (MS) is used as both coolant and breeder. Conventional reduced activation ferritic steel (RAFS, F82H) is used as the structural material in both blanket concepts. The low melting point Flibe ({approx}380 deg. C) is used in the first option while the Flinabe ({approx}305 deg. C) is used in the second option. In this paper, we present the results for assessing the radioactivity and decay heat. This assessment is performed separately for the structural material, the Be multiplier and the breeder (Flibe/Flinabe). The Class C waste disposal rating (WDR) was estimated for each material. For Flibe, Flinabe and Be the WDR is much lower than unity. However, the WDR for F82H is {approx}0.6-1.3. They are attributed to reactions with Mo and Nb present in F82H with levels of 70 wppm and 4 wppm, respectively. To ensure that F82H qualifies for shallow land burial, it is suggested to reduce these two impurities to {approx}50 and {approx}3 wppm, respectively.

  9. Training and Certification of Lock Operators IMTS Heads-up Paper Heads-up Paper

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Training and Certification of Lock Operators IMTS Heads-up Paper 1 Heads-up Paper Training called "Training and Certification of Lock and Dam Operators." Interested individuals can send ideas of the Training and Certification program. Examples of what will be in those draft documents are as follows

  10. Browser Interfaces and EV-SSL Certificates: Confusion, Inconsistencies and HCI Challenges

    E-Print Network [OSTI]

    Van Oorschot, Paul

    Browser Interfaces and EV-SSL Certificates: Confusion, Inconsistencies and HCI Challenges Jennifer (EV) SSL certificates has caused web browser manufacturers to take a new look at how they design SSL certificates rather than in- creasing trust. We perform a systematic walkthrough involving

  11. Translation of a Patent Certificate Translated by AFD China IP Our Ref. No.:080801507-E

    E-Print Network [OSTI]

    Peleg, Shmuel

    #12;Translation of a Patent Certificate Translated by AFD China IP Our Ref. No.:080801507-E Certificate No. 1156871 Certificate of Invention Patent Title: Method and System for Producing a Video Synopsis Inventors: Shmuel Peleg; Alexander Rav-Acha Patent No.: ZL 2006 8 0048754.8 Date of Filing

  12. The Future of Forest Certification in A Roundtable Discussion by Forest Stakeholders

    E-Print Network [OSTI]

    , minimize energy wastes, follow local laws, and respect people's rights. · Multiple forest certification upon them. One strategy is forest certification. Certification of forests and forest products is touted as a strategy for sustaining forests and the life support services they provide. Rather than remain mired in win

  13. Oak Ridge National Laboratory Transuranic Waste Certification Program

    SciTech Connect (OSTI)

    Smith, J.H.; Bates, L.D.; Box, W.D.; Aaron, W.S.; Setaro, J.A.

    1988-08-01T23:59:59.000Z

    The US Department of Energy (DOE) has requested that all DOE facilities handling defense transuranic (TRU) waste develop and implement a program whereby all TRU waste will be contained, stored, and shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in the DOE certification documents WIPP-DOE-069, 114, 120, 137, 157, and 158. The program described in this report describes how Oak Ridge National Laboratory (ORNL) intends to comply with these requirements and the techniques and procedures used to ensure that ORNL TRU wastes are certifiable for shipment to WIPP. This document describes the program for certification of newly generated (NG) contact-handled transuranic (CH-TRU) waste. Previsions have been made for addenda, which will extend the coverage of this document to include certification of stored CH-TRU and NG and stored remote-handled transuranic (RH-TRU) waste, as necessary. 24 refs., 11 figs., 4 tabs.

  14. A Threshold Autoregressive Model for Wholesale Electricity Prices

    E-Print Network [OSTI]

    A Threshold Autoregressive Model for Wholesale Electricity Prices B. Ricky Rambharat, Department the price of wholesale electricity soared to an unprecedented level of $7,500 per MwH (see [14-order threshold autoregressive model (TAR(1)) for wholesale electricity prices. (For discussion of TAR models, see

  15. Wavelet thresholding using generalized cross Maarten Jansen, Adhemar Bultheel

    E-Print Network [OSTI]

    Jansen, Maarten

    Wavelet thresholding using generalized cross validation Maarten Jansen, Adhemar Bultheel October 1997 Abstract De­noising algorithms based on wavelet thresholding replace small wavelet coefficients,this method assumes uncorrelated noise and or­ thogonal wavelet transforms. It turns out that extension

  16. Characterizing Ideal Weighted Threshold Secret Amos Beimel1

    E-Print Network [OSTI]

    Beimel, Amos

    Characterizing Ideal Weighted Threshold Secret Sharing Amos Beimel1 , Tamir Tassa1,2 , and Enav Science, The Open University, Ra'anana, Israel. Abstract. Weighted threshold secret sharing was introduced by Shamir in his seminal work on secret sharing. In such settings, there is a set of users where each user

  17. A threshold Cherenkov detector for K separation using silica aerogel

    E-Print Network [OSTI]

    Magiera, Andrzej

    A threshold Cherenkov detector for Kþ =pþ separation using silica aerogel R. Siudak a,b , A August 2008 Keywords: Threshold Cherenkov detector Silica aerogel Reaction pp ! Kþ ðLp� Kþ =pþ separation in the focal plane of a magnetic spectrograph. Silica aerogel with refractive index of n ¼ 1:05 is applied

  18. d Original Contribution IDENTIFYING THE INERTIAL CAVITATION THRESHOLD AND SKULL

    E-Print Network [OSTI]

    Konofagou, Elisa E.

    d Original Contribution IDENTIFYING THE INERTIAL CAVITATION THRESHOLD AND SKULL EFFECTS IN AVESSEL unknown. To investigate the pressure threshold for inertial cavitation of pre- formed microbubbles during sonication, passive cavitation detection in conjunction with B-mode imaging was used. A cerebral vessel

  19. educAtionAl leAderShip certificAte of AdvAnced StudieS (cAS)

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    educAtionAl leAderShip certificAte of AdvAnced StudieS (cAS) School of Education tAke the le New York state administrative leadership certifications our cAS progrAm prepAreS leAderS for A wide v for summer sessions) fAll educ 606: Curriculum Leadership (required) educ 675: Planning and Policy

  20. An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design

    SciTech Connect (OSTI)

    Wong, C C; Malang, S; Sawan, M; Dagher, M; Smolentsev, S; Merrill, B; Youssef, M; Reyes, S; Sze, D D; Morley, N B; Sharafat, S; Calderoni, P; Sviatoslavsky, G; Kurtz, R; Fogarty, P; Zinkle, S; Abdou, M

    2005-05-13T23:59:59.000Z

    An attractive blanket concept for the fusion reactor is the dual coolant Pb-17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb-17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetohydrodynamic (MHD) insulation to reduce the impact from the MHD pressure drop of the circulating Pb-17Li and as the thermal insulator to separate the high temperature Pb-17Li from the helium cooled RAFS structure. For the reference tokamak power reactor design, this blanket concept has the potential of satisfying the design limits of RAFS while allowing the feasibility of having a high Pb-17Li outlet temperature of 700 C. We have identified critical issues for the concept, some of which include the first wall design, the assessment of MHD effects with the SiC-composite flow coolant insert, and the extraction and control of the bred tritium from the Pb-17Li breeder. R&D programs have been proposed to address these issues. At the same time we have proposed a test plan for the DCLL ITER-Test Blanket Module program.

  1. An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design

    SciTech Connect (OSTI)

    Wong, Clement; Malang, S.; Sawan, M.; Dagher, Mohamad; Smolentsev, S.; Merrill, Brad; Youssef, M.; Reyes, Susanna; Sze, Dai Kai; Morley, Neil B.; Sharafat, Shahran; Calderoni, P.; Sviatoslavsky, G.; Kurtz, Richard J.; Fogarty, Paul J.; Zinkle, Steven J.; Abdou, Mohamed A.

    2006-07-05T23:59:59.000Z

    An attractive blanket concept for the fusion reactor is the dual coolant Pb-17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb-17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetohydrodynamic (MHD) insulation to reduce the impact from the MHD pressure drop of the circulating Pb-17Li and as the thermal insulator to separate the high temperature Pb-17Li from the helium cooled RAFS structure. For the reference tokamak power reactor design, this blanket concept has the potential of satisfying the design limits of RAFS while allowing the feasibility of having a high Pb-17Li outlet temperture of 700C. We have identified critical issues for the concept, some of which inlude the first wall design, the assessment of MHD effectrs with the SiC-composite flow coolant insert, and the extraction and control of the bred tritium from the Pb-17Li breeder. R&D programs have been proposed to address these issues. At the same time, we have proposed a test plan for the DCLL ITER-Test Blanket Module program.

  2. October 16-19, 2000 A. R. Raffray, et al., ARIES-AT Blanket and Divertor, ANS Top. Meet. On TOFE 2000 1

    E-Print Network [OSTI]

    Raffray, A. René

    Cycle · Material · ARIES-AT Reactor · Blanket Design and Analysis · Divertor Design and Analysis High-Temperature Pb-17Li as Breeder and Coolant and SiCf/SiC Composite as Structural Material #12°C · 3-stage compression with 2 inter-coolers · Turbine efficiency = 0.93 · Compressor efficiency = 0

  3. Software Certification: Is There a Case against Safety Cases?

    E-Print Network [OSTI]

    Lawford, Mark

    claims. We believe that the safety case methodology is useful for the soft- ware certification domain in domains like aviation, military applications, and the nuclear industry. Argument based methodologies by the developments above, we have become interested in pro- moting the concept of licensing for software and systems

  4. CERTIFICATE OF APPROVAL Thisisto certifythat the Quality Management System of

    E-Print Network [OSTI]

    Chapman, Clark R.

    CERTIFICATE OF APPROVAL Thisisto certifythat the Quality Management System of: Southwest Research been approved by Lloyd's Register Quality Assurance to the following Quality Management System Standards: ISO 9001 :2008 ANSIIISO/ ASQ Q9001-2008 The Quality Management System is applicable to: Research

  5. FOREST CERTIFICATION IN BRAZIL: TRADE AND ENVIRONMENTAL ENHANCEMENT 1

    E-Print Network [OSTI]

    of traded goods is evident from Brazil's experience with forest certification by both businesses of appropriate logging practices, further deflating prices and quality. Much of Brazil's tropical timber originates from deforestation: about 2.3 million hectares of forests are cut annually for agricultural

  6. California's Renewables Portfolio Standard (RPS) List of Facilities Certification Status

    E-Print Network [OSTI]

    Geothermal Energy Center #1 Siskiyou County CA Siskiyou 12/1/2010 65 Geothermal 7/14/2004 Dennis Gilles Geothermal Energy Center #2 Siskiyou County CA Siskiyou 12/1/2011 65 Geothermal 7/14/2004 Dennis Gilles Calpine Siskiyou Geothermal Partners, L.P. 707-431-6058 Approved 60001C Pre-Certification Glass Mountain

  7. Department of Humanities Certificate in Modern Language and

    E-Print Network [OSTI]

    Department of Humanities Certificate in Modern Language and Area Study CFR-French, CGE-German, CSP-Spanish French, German or Spanish must complete two years of the same modern language (12 credits) and three area (12 credits) Note: 6 credits must be from 3000 level French German Spanish __HU2271 Level I-A French

  8. CERTIFICATION OF HEALTH CARE PROVIDER FOR EMPLOYEE'S PREGNANCY DISABILITY

    E-Print Network [OSTI]

    Eirinaki, Magdalini

    CERTIFICATION OF HEALTH CARE PROVIDER FOR EMPLOYEE'S PREGNANCY DISABILITY HUMAN RESOURCES Employee this form to your medical provider. Section II must be fully completed by the health care provider Department/College name: Campus Phone: I authorize my health care provider to complete this form and provide

  9. A Certificate-Based Approach to Marketing Green Power and

    E-Print Network [OSTI]

    , Colorado 80401-3393 NREL is a U.S. Department of Energy Laboratory Operated by Midwest Research InstituteA Certificate-Based Approach to Marketing Green Power and Constructing New Wind Energy Facilities Preprint May 2002 · NREL/CP-620-32430 E. Blank Community Energy, Inc. L. Bird and B. Swezey National

  10. TECHNICAL CERTIFICATE -MARINE DIESEL MECHANICS Lewisporte -April 16, 2012

    E-Print Network [OSTI]

    deYoung, Brad

    TECHNICAL CERTIFICATE - MARINE DIESEL MECHANICS Lewisporte - April 16, 2012 March 19, 2012 Monday - Lewisporte April 30, 2012 Monday Last date for Marine Diesel Mechanics students to register or add courses Last date for Marine Diesel Mechanics students to drop courses and receive 100% refund of tuition fees

  11. Leadership in Professional Contexts PG Certificate/Diploma/MSc

    E-Print Network [OSTI]

    Levi, Ran

    Leadership in Professional Contexts PG Certificate/Diploma/MSc The University of Aberdeen in developing their leadership and management skills. Central to the programme is a menu of University based modules. Participants will also be encouraged to engage with leadership development opportunities provided

  12. NFLP EMPLOYMENT CERTIFICATION FORM *FA877* Please recycle.

    E-Print Network [OSTI]

    Amin, S. Massoud

    NFLP EMPLOYMENT CERTIFICATION FORM *FA877* Please recycle. DIRECTIONS--By signing this document you Faculty Loan Program (NFLP). This program requires you to be employed full-time as nurse faculty in the School of Nursing for a complete year. Section 3 must be completed by your employer. Keep a copy

  13. Certification of an agricultural spray aircraft on ethanol fuel

    SciTech Connect (OSTI)

    Shauck, M.E.; Zanin, M.G. [Baylor Univ., Waco, TX (United States)

    1994-12-31T23:59:59.000Z

    A Piper Pawnee, one of the most common agricultural spray aircraft, is currently undergoing Federal Aviation Administration (FAA) certification to allow the use of denatured ethanol as its fuel. This certification is part of a broader effort to introduce ethanol as a replacement for aviation gasoline. Various reasons brought about the choice of an agricultural spray aircraft to be certified on ethanol. One is the minimization of initial fuel distribution problems. Agricultural aviation often requires only single fuel storage since most of the flying is local. Additionally, corn-produced ethanol is the natural fuel of choice for farming operations. The increased power developed on ethanol compared to aviation gasoline (avgas) is very important when operating heavily loaded spray aircraft at very low altitudes. The power-plant, a Lycoming IO-540, is already certified. The aircraft is currently flying on ethanol in order to satisfy the airframe requirements. The effort is being supported by a consortium of organizations of corn-producing states. Upon completion of certification, the aircraft will be demonstrated around the mid-western states. Certification will allow the use of the aircraft in the commercial arena. Many mid-western agricultural spray operations and ag-pilots have already expressed interest in converting their aircraft to ethanol fuel.

  14. STATE OF CALIFORNIA CERTIFICATE OF COMPLIANCE, SIGN LIGHTING

    E-Print Network [OSTI]

    STATE OF CALIFORNIA CERTIFICATE OF COMPLIANCE, SIGN LIGHTING CEC-SLTG-1C (Revised 10/10) CALIFORNIA Lighting) (Page 1 of 4) SLTG-1C Project Name: Date: Project Address: Location of Sign Phase of Sign Construction Type of Lighting Control Outdoor Signs New Signs New Lighting Controls Indoor Signs Sign

  15. Certification of Health Care Provider for Employee's Serious Health Condition

    E-Print Network [OSTI]

    Subramanian, Venkat

    of Health Care Provider for Employee's Serious Health Condition (Family and Medical Leave Act) SECTION I health condition to submit a medical certification issued by the employee's health care provider. Please: __________________________________________________________________________________ First Middle Last SECTION III: For Completion by the HEALTH CARE PROVIDER INSTRUCTIONS to the HEALTH

  16. English Language Centre Certificate in Academic English and Law

    E-Print Network [OSTI]

    Applebaum, David

    -class Reading Assessment READING WEEK 8 Evaluating academic articles Commenting on a text / Critiquing skills (1English Language Centre Certificate in Academic English and Law Appendix 1 ­ Provisional Syllabus test / Diagnostic grammar test 2 Intro to academic writing / Academic style Review of diagnostic tests

  17. The University of Oklahoma (Norman Campus) Tuberculosis Testing and Certification

    E-Print Network [OSTI]

    Oklahoma, University of

    The University of Oklahoma (Norman Campus) Tuberculosis Testing and Certification As part of the University of Oklahoma has adopted a Tuberculosis Testing Policy, effective August 16, 2007. All staff if this documentation is not provided I will be unable to work at the University of Oklahoma. I do not meet any

  18. What to consider when choosing a well control certification program

    SciTech Connect (OSTI)

    McCauley, F.R. [F.R. McCauley and Associates, Houston, TX (United States); Schneider, M. [Baker Hughes Solutions, Houston, TX (United States)

    1997-04-01T23:59:59.000Z

    Qualified well control personnel can be extremely important to successful well operations. Losses from personnel injury, damaged equipment and interruption of product revenue can affect all parties concerned--operator, service company, rig contractor and specialty provider. With more operators becoming players in the international market and with service contractors assuming project management responsibilities, well control certification programs are becoming increasingly important. There are four primary organizations that provide recognized well control certification requirements for the industry. These organizations operate primarily in different areas of the world and under different criteria. They generally qualify personnel through different certification programs available for the following regions: IADC (International Association of Drilling Contractors)--worldwide; IWCF (International Well Control Forum)--worldwide; MMS (Minerals Management Service, US Department of Interior)--US Outer Continental Shelf; and PITS (Petroleum Industry Training Service of Canada)--Canada, federal and provincial. Through training and testing, these agencies make certain that well control personnel have sufficient understanding of the principles, practices and equipment required for well control. A summary of programs available for certification is given.

  19. Certificate of Specialization in Energy and Clean Technology Law (LLM)

    E-Print Network [OSTI]

    Kammen, Daniel M.

    Certificate of Specialization in Energy and Clean Technology Law (LLM) Requirements on a topic related to energy or clean technology law through one of the courses listed below that requires of the first week of classes. C t Environmental Law & Energy Policy IP, Entrepreneurship & Energy

  20. Third-Party Forest Certification in British Columbia

    E-Print Network [OSTI]

    Principles and Criteria) is an international non-profit organization that supports environmentally developed an international reputation for delivering a stable supply of quality wood and paper products from certification standards worldwide, reflecting the diversity of forest types, ecosystems and tenures. While

  1. The Graduate Certificate in Emergency Management and Business Continuity

    E-Print Network [OSTI]

    Bieber, Michael

    company. A customized Graduate Certificate can also be offered to match your compa- ny's area such as intentional bombing or the result of a positive event such as an unexpected demand for a company's product, evaluation, and improvement WHAT COURSES ARE OFFERED? Select two from: IS 613 Design of Emergency Management

  2. CONTINUING AND PROFESSIONAL EDUCATION extension.ucdavis.edu/certificates

    E-Print Network [OSTI]

    Ferrara, Katherine W.

    and Construction Professionals Fall 2011 n Construction Management n Construction Estimating n Green Building and Sustainable Design O N LI N E n Sustainability and the Built Environment n Renewable Energy n Solar Energy.ucdavis.edu/business Green Building and Sustainable Design Certificate Program Stay on the forefront of the design, planning

  3. Isotopic Tailoring to Improve the Breeding Capability of the Sn-Li Eutectic in Liquid First Wall Fusion Blanket Concepts

    SciTech Connect (OSTI)

    Youssef, Mahmoud Z. [University of California-Los Angeles (United States)

    2003-09-15T23:59:59.000Z

    Due to its low vapor pressure, the Sn-Li eutectic has been identified as a potential breeder for deployment in the liquid first wall (FW)/Blanket concepts under investigation in the APEX study for high power density fusion reactors. However, its breeding capability is limited. This drawback is rather improved due to the neutron multiplication via Sn(n,2n) reactions. However, the 'local' tritium breeding ratio (TBR) was found to be still on the marginal side (even with 90%Li-6 enrichment). Aside from using a beryllium multiplier, other means to improve the capability of Sn-Li for breeding are explored. In this paper, we show that by isotopic tailoring of Tin in the Sn-Li breeder, one can achieve substantial improvement in TBR in addition to attaining significant reduction in the activation level in this material.

  4. Waste certification review program at the Savannah River Site

    SciTech Connect (OSTI)

    Faulk, G.W.; Kinney, J.C. [Westinghouse Savannah River Co., Aiken, SC (United States); Knapp, D.C. [Bechtel Savannah River Inc., Aiken, SC (United States); Burdette, T.E. [Science Applications International Corp., Oak Ridge, TN (United States)

    1996-02-01T23:59:59.000Z

    After approving the waste certification programs for 45 generators of low-level radioactive and mixed waste, Westinghouse Savannah River Company (WSRC) moved forward to implement a performance-based approach for assuring that approved waste generators maintain their waste certification programs. WSRC implemented the Waste Certification Review Program, which is comprised of two sitewide programs, waste generator self-assessments and Facility Evaluation Board reviews, integrated with the WSRC Solid Waste Management Department Waste Verification Program Evaluations. The waste generator self-assessments ensure compliance with waste certification requirements, and Facility Evaluation Board reviews provide independent oversight of generators` waste certification programs. Waste verification evaluations by the TSD facilities serve as the foundation of the program by confirming that waste contents and generator performance continue to meet waste acceptance criteria (WSRC 1994) prior to shipment to treatment, storage, and disposal facilities. Construction of the Savannah River Site (SRS) was started by the US Government in 1950. The site covers approximately 300 square miles located along the Savannah River near Aiken, South Carolina. It is operated by the US Department of Energy (DOE). Operations are conducted by managing and operating contractors, including the Westinghouse Savannah River Company (WSRC). Historically, the primary purpose of the SRS was to produce special nuclear materials, primarily plutonium and tritium. In general, low-level radioactive and mixed waste is generated through activities in operations. Presently, 47 SRS facilities generate low-level radioactive and mixed waste. The policies, guidelines, and requirements for managing these wastes are determined by DOE and are reflected in DOE Order 5820.2A (US DOE 1988).

  5. On the Behavior of the Threshold Operator for Bandlimited Functions

    E-Print Network [OSTI]

    Boche, Holger

    One interesting question is how the good local approximation behavior of the Shannon sampling series for the Paley–Wiener space PW[1 over ?] is affected if the samples are disturbed by the non-linear threshold operator. ...

  6. A Threshold Autoregressive Model for Wholesale Electricity Prices

    E-Print Network [OSTI]

    A Threshold Autoregressive Model for Wholesale Electricity Prices B. Ricky Rambharat Carnegie of wholesale electricity soared to an unprecedented $7,500 per megawatt-hour (MwH) (see FERC, 1998). Models

  7. Applying thresholds to forecast potential biodiversity loss from human development

    E-Print Network [OSTI]

    Hilderbrand, Robert H.

    thresholds to projected increases in residential development in the Middle Patuxent River watershed by 2030 in the Potapsco River watershed of Maryland could result in the loss of nearly 60% of the benthic

  8. Essays on Voluntary Contribution with Private Information and Threshold Uncertainty

    E-Print Network [OSTI]

    Peng, Hui-Chun

    2014-07-08T23:59:59.000Z

    This dissertation concerns individual voluntary contributions in the subscription game with three important model considerations: private information on public good valuations, threshold uncertainty and the timing of the contribution — simultaneous...

  9. Minimum patch size thresholds of reproductive success of songbirds

    E-Print Network [OSTI]

    Butcher, Jerrod Anthony

    2009-05-15T23:59:59.000Z

    1 MINIMUM PATCH SIZE THRESHOLDS OF REPRODUCTIVE SUCCESS OF SONGBIRDS A Dissertation by JERROD ANTHONY BUTCHER Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements... for the degree of DOCTOR OF PHILOSOPHY May 2008 Major Subject: Wildlife and Fisheries Sciences 2 MINIMUM PATCH SIZE THRESHOLDS OF REPRODUCTIVE SUCCESS OF SONGBIRDS A Dissertation by JERROD ANTHONY BUTCHER Submitted to the Office...

  10. Effect of shrink fits on threshold speeds of rotordynamic instability

    E-Print Network [OSTI]

    Mir, MD. Mofazzal Hossain

    2001-01-01T23:59:59.000Z

    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 CHAPTER IV TEST APPARATUS . . . . 13 CHAPTER V RESULTS AND DISCUSSION . . . 17 17 30 42 42 47 5. 1 Rap Test. . 5. 2 Running Test 5. 3 Modeling and the Prcdiction of Threshold Speed of Instability.... . . . . . . . . . . . , . . . . . . . . . . . 5. 3. 1 Matching the Base Case. 5. 3. 2 Gunter's Prediction Using C, q 5. 3. 3 Modeling and Prediction of the Threshold Speed Using the XLTRC Code. . . . 51 5. 4 Prediction of the Onset Speed of Instability for a Tight Inteiference Fit...

  11. Proposal for the award of a blanket purchase contract for the supply, installation, commissioning and maintenance of electrical switchgear operating at 18kV and 3.3 kV

    E-Print Network [OSTI]

    2015-01-01T23:59:59.000Z

    Proposal for the award of a blanket purchase contract for the supply, installation, commissioning and maintenance of electrical switchgear operating at 18kV and 3.3 kV

  12. Low-energy structure of above-threshold-ionization electron spectra: Role of the Coulomb threshold effect

    E-Print Network [OSTI]

    Telnov, Dmitry A.; Chu, Shih-I

    2011-06-10T23:59:59.000Z

    Recent experimental observations of above-threshold ionization of rare gas atoms and diatomic molecules by midinfrared laser fields [C. I. Blaga et al., Nat. Phys. 5, 335 (2009); W. Quan et al., Phys. Rev. Lett. 103, 093001 ...

  13. Certification process of safety analysis and risk management computer codes at the Savannah River Site

    SciTech Connect (OSTI)

    Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Toffer, H.; Lewis, C.J.; Crowe, R.D. [Westinghouse Hanford Co., Richland, WA (United States)

    1992-05-01T23:59:59.000Z

    The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

  14. Certification process of safety analysis and risk management computer codes at the Savannah River Site

    SciTech Connect (OSTI)

    Ades, M.J. (Westinghouse Savannah River Co., Aiken, SC (United States)); Toffer, H.; Lewis, C.J.; Crowe, R.D. (Westinghouse Hanford Co., Richland, WA (United States))

    1992-01-01T23:59:59.000Z

    The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

  15. Seismic Analysis Issues in Design Certification Applications for New Reactors

    SciTech Connect (OSTI)

    Miranda, M.; Morante, R.; Xu, J.

    2011-07-17T23:59:59.000Z

    The licensing framework established by the U.S. Nuclear Regulatory Commission under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides requirements for standard design certifications (DCs) and combined license (COL) applications. The intent of this process is the early reso- lution of safety issues at the DC application stage. Subsequent COL applications may incorporate a DC by reference. Thus, the COL review will not reconsider safety issues resolved during the DC process. However, a COL application that incorporates a DC by reference must demonstrate that relevant site-specific de- sign parameters are within the bounds postulated by the DC, and any departures from the DC need to be justified. This paper provides an overview of several seismic analysis issues encountered during a review of recent DC applications under the 10 CFR Part 52 process, in which the authors have participated as part of the safety review effort.

  16. Structural Design Challenges in Design Certification Applications for New Reactors

    SciTech Connect (OSTI)

    Miranda, M.; Braverman, J.; Wei, X.; Hofmayer, C.; Xu, J.

    2011-07-17T23:59:59.000Z

    The licensing framework established by the U.S. Nuclear Regulatory Commission under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides requirements for standard design certifications (DCs) and combined license (COL) applications. The intent of this process is the early reso- lution of safety issues at the DC application stage. Subsequent COL applications may incorporate a DC by reference. Thus, the COL review will not reconsider safety issues resolved during the DC process. However, a COL application that incorporates a DC by reference must demonstrate that relevant site-specific de- sign parameters are confined within the bounds postulated by the DC, and any departures from the DC need to be justified. This paper provides an overview of structural design chal- lenges encountered in recent DC applications under the 10 CFR Part 52 process, in which the authors have participated as part of the safety review effort.

  17. Energy Savings Certificate Markets: Opportunities and Implementation Barriers

    SciTech Connect (OSTI)

    Friedman, B.; Bird, L.; Barbose, G.

    2009-07-01T23:59:59.000Z

    Early experiences with energy savings certificates (ESCs) have revealed their merits and the challenges associated with them. While in the United States ESC markets have yet to gain significant traction, lessons can be drawn from early experiences in the states of Connecticut and New York, as well as from established markets in Italy, France, and elsewhere. The staying power of European examples demonstrates that ESCs can help initiate more efficiency projects. This article compares ESCs with renewable energy certificates (RECs), looks at the unique opportunities and challenges they present, and reviews solutions and best practices demonstrated by early ESC markets. Three major potential ESC market types are also reviewed: compliance, voluntary, and carbon. Additionally, factors that will benefit ESC markets in the United States are examined: new state EEPS policies, public interest in tools to mitigate climate change, and the growing interest in a voluntary market for ESCs.

  18. Considerations for Emerging Markets for Energy Savings Certificates

    SciTech Connect (OSTI)

    Friedman, B.; Bird, L.; Barbose, G.

    2008-10-01T23:59:59.000Z

    Early experiences with energy savings certificates (ESCs) have revealed both their merit and the challenges associated with them. In the United States, there has been little activity to date, so any lessons must be drawn from experiences in Italy, the United Kingdom (UK), France, and elsewhere. The staying power of European examples, particularly in Italy, demonstrates that ESCs can help initiate more efficiency projects. Although a robust market for renewable energy certificates (RECs) has emerged in both the voluntary and policy compliance contexts in the United States, ESCs have yet to gain significant traction. This report looks at the opportunity presented by ESCs, the unique challenges they bring, a comparison with RECs that can inform expectations about ESC market development, and the solutions and best practices early ESC market experience have demonstrated. It also examines whether there are real market barriers that have kept ESCs from being adopted and what structural features are necessary to develop effective trading programs.

  19. Building performance evaluation and certification in the UK

    E-Print Network [OSTI]

    Kelly, Scott; Pollitt, Michael G.; Crawford Brown, Doug

    2012-10-04T23:59:59.000Z

    Certificates EST Energy Saving Trust EU European Union FES Fuel and Energy Survey FIT Feed In Tariff GDP Gross Domestic Product PV Photovoltaic RdSAP Reduced Data Standard Assessment Procedure RHI Renewable Heat Incentive SAP Standard... ). This is only exacerbated by the forecasted increase to energy prices (DECC 2011b). Without detailed information about the performance of buildings classified as being in fuel poverty, it is difficult to determine what strategies may alleviate these pressures...

  20. Better than Average? - Green Building Certification in International Projects

    E-Print Network [OSTI]

    Baumann, O.

    2008-01-01T23:59:59.000Z

    . An Enterprise of the Ebert-Consulting Group 1004 Pennsylvania Avenue, SE Washington, D.C. 20003, USA 00 12 02/ 6 08 - 13 34 o.baumann@eb-engineers.com Better than Average? - Green Building Certification in International Projects Green Building..., green building rating systems focus on sustainability for the entire life-cycle of buildings and therefore offer great opportunities for enhancing building operation, when applied and used appropriately. This presentation gives an overview...