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Sample records for abwr quarterly progress

  1. Progress of full MOX core design in ABWR

    International Nuclear Information System (INIS)

    Izutsu, S.; Sasagawa, M.; Aoyama, M.; Maruyama, H.; Suzuki, T.

    2000-01-01

    Full MOX ABWR core design has been made, based on the MOX design concept of 8x8 bundle configuration with a large central water rod, 40 GWd/t maximum bundle exposure, and the compatibility with 9x9 high-burnup UO 2 bundles. Core performance on shutdown margin and thermal margin of the MOX-loaded core is similar to that of UO 2 cores for the range from full UO 2 core to full MOX core. Safety analyses based on its safety parameters and MOX property have shown its conformity to the design criteria in Japan. In order to confirm the applicability of the nuclear design method to full MOX cores, Tank-type Critical Assembly (TCA) experiment data have been analyzed on criticality, power distribution and β eff /l measurements. (author)

  2. Information Science Research Institute. Quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Nartker, T.A.

    1994-06-30

    This is a second quarter 1194 progress report on the UNLV Information Science Research Institute. Included is symposium activity; staff activity; document analysis program; text retrieval program; institute activity; and goals.

  3. 2. Quarterly progress report, 1983

    International Nuclear Information System (INIS)

    1983-08-01

    This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 58 Co, 60 Co, 134 Cs, 137 Cs, 90 Sr, 106 Ru, K, 54 Mn, U and T). A bibliographic selection is also presented [fr

  4. 4. Quarterly progress report, 1982

    International Nuclear Information System (INIS)

    1982-01-01

    This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 58 Co, 60 Co, 134 Cs, 137 Cs, 125 Sb, 90 Sr, 106 Ru, K, 54 Mn, U and T). A bibliographic selection is also presented [fr

  5. 3. Quarterly progress report 1982

    International Nuclear Information System (INIS)

    1982-01-01

    This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 58 Co, 60 Co 134 Cs, 137 Cs, 90 Sr, 106 Ru, K, 54 Mn, U and T). A bibliographic selection is also presented [fr

  6. The development of ABWR

    International Nuclear Information System (INIS)

    Nishimura, N.; Nakai, H.; Ross, M.A.

    1999-01-01

    The first Advanced Boiling Water Reactor (ABWR) started commercial operation as Tokyo Electric Power Company's (TEPCO) Kashiwazaki-Kariwa Nuclear Power Station Unit No.6 (K-6) in November 1996 and its sister Unit No.7 (K-7) in July 1997. The ABWR was developed to achieve higher reliability and safety margin while improving overall operability and economics. To achieve these goals, the optimal Boiling Water Reactor (BWR) technologies had been studied, tested and were finally adopted into the ABWR design. These technologies were called 'First of a Kind' and include the Reactor Internal Pump (RIP), Fine Motion Control Rod Drive (FMCRD), Reinforced Concrete Containment Vessel (RCCV), and integrated digital Instrumentation and Control System (I and C). Intensive development study, confirmation tests and verification tests were conducted by the plant equipment suppliers, electric utilities, and government agencies. During plant construction, the system and equipment functions and operational characteristics were confirmed through various tests. Before the start of the commercial operation, it was confirmed that these first ABWR units met all the design goals that had been established for the next generation of nuclear power plants. Both units have now completed the first fuel cycle of operation without any unplanned plant shut down and have achieved very high availability factors. This paper describes the development and construction of these first ABWR units in the world. (author)

  7. UNLV Information Science Research Institute. Quarterly progress report

    International Nuclear Information System (INIS)

    Nartker, T.A.

    1994-01-01

    This document summarizes the activities and progress for the 1994 Fall quarter for the UNLV Information Science Research Institute. Areas covered include: Symposium activity, Staff activity, Document analysis program, Text-retrieval program, and Institute activity

  8. UNLV Information Science Research Institute. Quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Nartker, T.A.

    1994-12-31

    This document summarizes the activities and progress for the 1994 Fall quarter for the UNLV Information Science Research Institute. Areas covered include: Symposium activity, Staff activity, Document analysis program, Text-retrieval program, and Institute activity.

  9. ABWR evolution program

    International Nuclear Information System (INIS)

    Omoto, A.; Tanabe, A.; Moriya, K.; Dillmann, C.W.

    1993-01-01

    The ABWR plant is becoming a commercial reality in Japan where the first two units are being built by the Tokyo Electric Power Company. Although these units are scheduled to come on line in 1996 and '97, the Tokyo Electric Power Company, jointly with NSSS vendors (General Electric, Toshiba and Hitachi) and Japanese BWR utilities, initiated a program for a new plant design. This program is aimed at the further evolution of the ABWR to take advantage of new technological developments and to meet possible social changes in the years to come. The expected time for the first-of-a-kind plant to come on line is in the 2010's when the first generation plants in Japan may approach the time for replacement. This paper presents the ouline of this program with focus on the utility requirements and candidate technologies. (orig.)

  10. Quarterly Technical Progress Report June 2015

    Energy Technology Data Exchange (ETDEWEB)

    Buchholz, Bruce A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-06-08

    The project has two main goals: 1) Identify the types of adducts naphthalene (NA) forms with DNA and 2) determine whether adduct formation correlates with site selective tumor formation in defined subcompartments of the respiratory tract (respiratory and olfactory nasal epithelium and airways of mice, rats and rhesus monkeys). Five tasks are associated with the completion of the goals. Task 1: Contracting and Animal Use Approvals. IACUC and ACURO approvals are complete, The subcontract with UC Davis (UCD) was executed in December 2014. Task 2: Perform In Vitro Study for Goal 1. Rat samples exposed and in freezer while adduct standards are being made. Mouse samples need to be exposed in next quarter. Task 3: Perform In Vitro Study for Goal 2. Mouse ex vivo samples completed. Rat and monkey samples need to be completed in the next quarter. Task 4: Sample Preparation and Analysis. Mouse Goal 2 samples completed. Other samples remain to be done. Task 5: Data Interpretation and Reporting. Need rat data to write paper on adduct formation.

  11. Nuclear reactor system for ABWR

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Kitagawa, Koji

    1997-01-01

    Various tests and measurements were performed during the pre-operational test run of Unit No. 6 of The Tokyo Electric Power Co., Inc.'s Kashiwazaki-Kariwa Nuclear Power Station, the first advanced boiling water reactor (ABWR) unit in the world, and the design and performance adequacy of the ABWR were confirmed. The realization of the ABWR in Japan took about 20 years. It was decided that technologies for the reactor internal pump (RIP) and the fine-motion control rod drive (FMCRD), which had been applied in Europe, would be incorporated in the ABWR aiming at simplification of its structure and operation. These main components were evaluated, modified and verified in consideration of the unique Japanese environment, such as seismic conditions, through a joint study program with Japanese utilities as well as an improvement and standardization program in cooperation with the government. In addition to incorporating RIP and FMCRD technologies, the ABWR also has improved features in terms of the design of the reactor pressure vessel and internals, as well as automated servicing equipment for the RIP, FMCRD, and primary containment vessel. (author)

  12. Quarterly Progress Report (April 1 to June 30, 1950)

    Energy Technology Data Exchange (ETDEWEB)

    Brookhaven National Laboratory

    1950-07-01

    This is the second of a series of Quarterly Progress Reports. While most of the departments have summarized their work or used a form comparable to abstracts, the Chemistry Department has given both abstracts and complete reports on its work. The major part of the progress in the Reactor Science and Engineering Department is being presented simultaneously in a separate classified report. There are reports from the following departments: (1) physics department; (2) instrumentation and health physics department; (3) accelerator project; (4) chemistry department; (5) reactor science and engineering department; (6) biology department; and (7) medical department.

  13. ABWR construction experience in Japan

    International Nuclear Information System (INIS)

    Kawahata, Junichi; Miura, Jun; Saito, Fuyuki; Mori, Hiroya

    2003-01-01

    The construction of Kashiwazaki-Kariwa Nuclear Power Station Unit No. 6 and 7 (K6 and 7) owned by Tokyo Electric Power Company (TEPCO), have been in service since November 1996 and September 1997 respectively, and are the first ABWRs in the world. Hitachi, Ltd. and Toshiba Corporation took part in the projects and achieved safety construction in 52- month schedule from rock inspection to turnover in cooperation with TEPCO and other contractors with broad experience in BWRs. Taking advantage of experience of the Kashiwazaki construction, the ABWR construction methods realize to satisfy with requests from electric power companies and to fit site conditions. The Chubu Electric Power Company's Hamaoka Nuclear Power Station Unit No. 5 (Hamaoka 5) and Hokuriku Electric Power Company's Shika Nuclear Power Station Unit No. 2 (Shika 2), which are ABWRs, completed rock inspection in May 2000 and June 2001 respectively, and are under construction. The ABWR construction methods are proved their validity through four actual construction projects. Safe constructions with the highest quality have been advanced thus further aiming at the introduction of the latest technologies and contributing to reduce plant construction costs and also to shorten schedule. (author)

  14. Baseline gas turbine development program. Eighteenth quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, F W; Wagner, C E [comps.

    1977-04-30

    Progress is reported for a program whose goals are to demonstrate an experimental upgraded gas turbine powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine powered, compact-size American automobile. Initial running of the upgraded engine took place on July 13, 1976. The engine proved to be mechanically sound, but was also 43% deficient in power. A continuing corrective development effort has to date reduced the power deficiency to 32%. Compressor efficiency was increased 2 points by changing to a 28-channel diffuser and tandem deswirl vanes; improved processing of seals has reduced regenerator leakage from about 5 to 2.5% of engine flow; a new compressor turbine nozzle has increased compressor turbine stage efficiency by about 1 point; and adjustments to burner mixing ports has reduced pressure drop from 2.8 to 2.1% of engine pressure. Key compressor turbine component improvements are scheduled for test during the next quarterly period. During the quarter, progress was also made on development of the Upgraded Vehicle control system; and instrumentation of the fourth program engine was completed by NASA. The engine will be used for development efforts at NASA LeRC.

  15. Quarterly Progress Report (January 1 to March 31, 1950)

    Energy Technology Data Exchange (ETDEWEB)

    Brookhaven National Laboratory

    1950-04-01

    This is the first of a series of Quarterly Reports. These reports will deal primarily with the progress made in our scientific program during a three months period. Those interested in matters pertaining to organization, administration, complete scientific program, personnel and other matters not directly involved in current scientific progress are referred to our Annual Progress Report which is issued in January. We have attempted to describe new information that appears significant, or of interest, to other scientists within the Atomic Energy Commission Laboratories. No effort has been made, however, to detail progress in each and every research project. Little or no reference will therefore be found to the projects in which progress during the current period is considered too inconclusive. Since our organizational structure is departmental, the work described herein is arranged in the following sequence: (1) Accelerator Project; (2) Biology Department; (3) Chemistry Department; (4) Instrumentation and Health Physic8 Department; (5) Medical Department; (6) Physics Department; and (7) Reactor Science and Engineering Department.

  16. The status of development activities of ABWR-2

    International Nuclear Information System (INIS)

    Anegawa, T.; Aoyama, M.; Fennern, L.E.; Koh, F.

    2001-01-01

    This paper reports the current status of development activities for ABWR-II which is the next generation design based on ABWR. Six Japanese BWR utilities and three BWR plant venders, General Electric Company, Hitachi Ltd. and Toshiba Corporation, have jointly been promoting the program. The program has been progressing for a decade. In Phase I (1991-92), future technologies were discussed and several plant concepts were studied. In Phase II (1993-95), in order to establish a reference reactor concept, key design features were selected. In Phase III (1996-2000), based on the reference reactor concept, modifications and improvements have been done in order to satisfy the design requirements well. The start of commercial operation of ABWR-II is estimated to be in the late 2010 when replacements of the first generation of operating nuclear power plants are expected to start. Larger power output and some passive safety features are adopted in order to make ABWR-II competitive in power generation cost and attain public confidence on safety. The advantages of a large fuel bundle design are also discussed here. (author)

  17. Development, operating experience and future plan of ABWR in Japan

    International Nuclear Information System (INIS)

    Ujihara, N.

    2001-01-01

    construction at Hamaoka unit No. 5, Shika unit No. 2, and in plan at Ohma unit No. 1, Shimane unit No. 3. TEPCO is now progressing cost reduction of ABWR with other Japanese utilities. The most significant point is standardization. And we also plan to adopt some design improvements. By using these measures, TEPCO intends a 30% cost reduction of our next ABWR plants, compared with Kashiwazaki-Kariwa No. 6 and 7 of ABWR first plant. We would like to further develop ABWR for moreover cost reduction. And we start to develop ABWR-II as a large-scale (1700 MW(e)) next generation reactor with the aim to commence plant operation in the late 2010s. (author)

  18. Tribopolymerization as an anti-wear mechanism. Quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Furey, M.J.

    1996-04-01

    The primary objective of this activity is to obtain the necessary data which would enhance, promote, and encourage the introduction of advanced lubrication technology into the marketplace. This includes (a) defining specific but different applications, (b) establishing the limits or ranges of applied loads, speeds, and temperatures over which the concept of tribopolymerization would work in reducing wear and/or friction, (c) continuing in efforts to understand the film-forming process (this rates to (b) above), using this knowledge to develop new and even more effective additives, and (d) exploring possible connections with private and investment companies for the licensing and marketing of products which will reduce friction and wear in a variety of applications. Progress was made in several different but connected areas. These included (a) establishing of load/velocity limits of selected monomers for ceramic lubrication, (b) the discovery of new and effective monomers designed for higher temperature anti-wear applications, (c) improvements and modifications of the high load/high speed pin-on-disk machine, (d) the initiation of related or spin-off projects designed to get their advanced technology into the marketplace, (e) the filing of three new patent applications, and (f) collaborative research with Dr. Kajdas--the co-inventor with Dr. Furey--on tribopolymerization as a novel and effective approach to the boundary lubrication of ceramics and steel. These and other elements of progress made during the first Quarter of 1996 are discussed briefly.

  19. Further improvement of human-machine interface for ABWR main control room

    International Nuclear Information System (INIS)

    Makino, S.

    2001-01-01

    Tokyo Electric Power Company (TEPCO) has developed main control room panels based on progress in C and I technology. ABWR type main control room panels (ABWR MCR PNLs) are categorized as third generation type domestic BWR MCR, that is, they are were developed step by step based on operating experience with the first and the second generation BWR. ABWR type main control room panels were applied to Kashiwazaki-Kariwa Nuclear Power Station Units Number 6 and 7 (K-6/7) for the first time. K-6/7 are the first advanced BWR (ABWR), which started commercial operation in November 1996 and July 1997, respectively. The concept of ABWR MCR design was verified through wooden mock-up panels, start-up tests and commercial operation. Though the K-6/7 design has borne fruit, we are planning to refine and standardize the design based on the following concepts: to maintain the plant operation and monitoring style of ABWR MCR PNLs; to introduce brand-new HMI technology and devices; to incorporate operators' advice in the design. This paper outlines the features and improvements of the K6/7 MCR PNLs design. (author)

  20. Advanced boiling water reactor (ABWR). Design, construction, operation and maintenance experience

    International Nuclear Information System (INIS)

    Idesawa, M.

    1998-01-01

    The ABWR has experienced all phases of design, construction, operation and maintenance at Kashiwazaki-Kariwa Nuclear Power Station Units No.6 and 7 and confirmed that originally intended development targets have been achieved with highly satisfactory results. This is the fruit of a project that collected wisdom from various sources under a international cooperative organization, with Tokyo Electric Power Company taking the leading role from the onset. These two units have not only demonstrated that ABWRs have superior performance as the first standard units of advanced light water reactor but also aroused a hope for the big potential advantages that ABWRs can provide us. The ABWR has already been awarded a U.S. standard license for having proved that it can comply with the requirements of international regulatory systems with an ample margin. There are also many construction programs with ABWRs progressing both domestically and abroad, suggesting that it has won recognition as an international standard plant. We will do our utmost to perfect the operation and maintenance records of Kashiwazaki-Kariwa Units No.6 and 7, which is the top runner among ABWRs, and to make known the superiority of this reactor to the world. (J.P.N.)

  1. quarters

    Directory of Open Access Journals (Sweden)

    Elena Grigoryeva

    2016-10-01

    Full Text Available Are there many words combining both space and time? A quarter is one of such rare words: it means both a part of the city space and a period of the year. A regular city has parts bordered by four streets. For example, Chita is a city with an absolutely orthogonal historical center. This Utopian city was designed by Decembrists in the depth of Siberian ore-mines (120. The 130 Quarter in Irkutsk is irregular from its inception because of its triangular form. Located between two roads, the forked quarter was initially bordered by flows along the west-east axis – the main direction of the country. That is why it appreciated the gift for the 350 anniversary of its transit existence – a promenade for an unhurried flow of pedestrians. The quarter manages this flow quite well, while overcoming the difficulties of new existence and gathering myths (102. Arousing many expectations, the “Irkutsk’s Quarters” project continues the theme that was begun by the 130 Quarter and involved regeneration, revival and search for Genius Loci and the key to each single quarter (74. Beaded on the trading axis, these shabby and unfriendly quarters full of rubbish should be transformed for the good of inhabitants, guests and the small business. The triptych by Lidin, Rappaport and Nevlyutov is about happiness of urbanship and cities for people, too (58. The City Community Forum was also devoted to the urban theme (114. Going through the last quarter of the year, we hope that Irkutsk will keep to the right policy, so that in the near future the wooden downtown quarters will become its pride, and the design, construction and investment complexes will join in desire to increase the number of comfortable and lively quarters in our city. The Baikal Beam will get one more landmark: the Smart School (22 for Irkutsk’s children, including orphans, will be built in several years on the bank of Chertugeevsky Bay.

  2. Development of Innovative Construction Technologies for ABWRs

    International Nuclear Information System (INIS)

    Yamashita, T.; Fukuda, T.; Masuda, N.

    2002-01-01

    This paper describes an effort by Tokyo Electric Power Company (TEPCO) to shorten the construction time in a drastic manner for the Advanced Boiling Water Reactors (ABWR), thereby aiming at reducing construction costs. First an outline of the actual construction records for the five BWR Units and the two ABWR Units at the Kashiwazaki-Kariwa site is introduced along with the construction methods employed for these units. There is a continued trend in the reduction of construction time from Unit 1 to 7 owing to a number of improvements made to these units, and in particular it is noteworthy that the drastic reduction was accomplished due to the change in reactor type from BWR to ABWR. Explained next is an on-going effort for the next ABWR and the following next generation of ABWRs to further shorten construction time. In this effort an emphasis is laid on the development of innovative construction methods by the adoption of steel plate/concrete composite structures (SC Structure), and the application of those structures even to containment vessel (so-called SCCV). This work is being conducted as part of TEPCO's research and development for the next generation ABWRs (ABWR II). Presently it is expected that the construction time from bedrock inspection to fuel loading could be shortened in a stepwise fashion to 38 and 31.5 months for the next ABWR and finally to 23 months for the next generation ABWR II, thus enabling a greatly reduced power generating cost and enhanced safety during construction. In addition to the above effort, a preliminary study has been performed concerning the application of base isolation systems to ABWR plants. From this study which is aimed at standardization, lowered cost and mitigation of engineering work, it was found that base isolation system effectively reduces seismic response and is instrumental in achieving the above-mentioned objectives. Therefore it can be said that the use of this system gives more freedom in selecting sites

  3. Baseline gas turbine development program. Seventeenth quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, F W; Wagner, C E

    1977-01-31

    Progress is reported for a program whose goals are to demonstrate an experimental upgraded gas turbine powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine powered, compact-size American automobile. Initial running of the upgraded engine took place on July 13, 1976. The engine has proved to be mechanically sound, but has also been seriously deficient in power. Principal program effort has therefore been in the area of diagnostic testing and corrective development. To date, three upgraded engines have been assembled and run in the test cell. Engine 2 was installed in an upgraded vehicle and became operational on January 25, 1977. Special diagnostic instrumentation was installed on Engine 3 to evaluate the compressor, turbine, and hot engine leakage. It was determined that the power deficiency was principally due to problems in the compressor and first stage turbine areas and during this quarter several corrective changes have been initiated. Parts for a fourth engine being built for NASA Lewis have been shipped to NASA for installation of special instrumentation.

  4. Fast Reactor Programme. Second Quarter 1969. Progress Report. RCN Report

    International Nuclear Information System (INIS)

    Hoekstra, E.K.

    1969-12-01

    This progress report covers fast reactor research carried out by RCN during the second quarter 1969 forming part of the integrated fast breeder research and development programme also in progress at the national nuclear research centres Karlsruhe and Mol. The combined effort is based on a memorandum of co-operation in this field signed by the respective governments in 1968 and on a memorandum of understanding signed by the research centres. The RCN contribution is mainly concerned with the core of the fast breeder reactor and related safety aspects and, as such, must be looked upon as being complementary to the industrial research pro- field of fast reactors. The contribution comprises the following six items: - A Æéatîtôr , physics programme to determine the influence of fission products on several main characteristics of the reactor core such as void coefficient, Doppler coefficient and breeding ratio; - A fuel performance programme in which both stationary and transient irradiations are being carried out to establish the temperature and power limits of fuel rods; also the consequences of loss- of-cooling will be investigated; - Investigation into the change in mechanical properties of fuel canning materials due to high fast neutron doses; - A study of the corrosion behaviour of canning materials and their compatibility with the fuel under conditions of high temperature and high pressure; - Investigation into the behaviour of aerosols of fission products which could be formed after a fast reactor accident; a thorough understanding is of utmost importance for the reactor safety assessment ; - Studies on heat transfer in the reactor core. As fast breeders operate at high power densities, an accurate knowledge on the heat transfer phenomena is required

  5. Quarterly Program Progress Report April 1, 2002-June 30, 2002

    Energy Technology Data Exchange (ETDEWEB)

    Palafox, Neal A., MD, MPH

    2002-07-31

    DOE B188 DOE/PHRI Special Medical Care Program in the Republic of the Marshall Islands (RMI)Quarterly Program Progress Report The DOE/PHRI Special Medical Care Program continues to provide, on a year round basis, a broad spectrum of medical care to the DOE patient population. During the fourth quarter of Year 4, the following medical services were provided: (1) Annual medical examinations for the DOE patient population (see Exhibit 1 for details). (2) Medications for the DOE patient population. (3) Preventive and primary medical care to the DOE patient population in the RMI as time and resources permit. (4) Additional manpower for the outpatient clinics at Ebeye and Majuro Hospitals (see Exhibit 2 for details). (5) Ancillary services such as labs, radiology and pharmacy in coordination with Kwajalein Hospital, Majuro Hospital and the 177 Health Care Program (177 HCP). (6) Referrals to Ebeye Hospital, Majuro Hospital and Kwajalein Hospital as necessary. (7) Referrals to Straub Clinic and Hospital in Honolulu as necessary (for details see Exhibit 1). (8) Monitored and adjusted monthly annual examination schedules based on equipment failure at Kwajalein. In addition to the above, the program was also involved in the following activities during this quarter: (1) Organized and conducted continuing medical education (CME) talks for the program's RMI staff and other RMI healthcare workers. (2) Held meetings with RMI government officials and Local Atoll government officials. (3) Input past medical records into the Electronic Medical Record (EMR) system. (4) Made adjustments to and created more templates for the EMR system. (5) Coordinated with the Public Health Departments on Majuro and Ebeye. (6) Met with PEACESAT to discuss possible collaboration on high speed Internet access. (7) Looked for opportunities to expand the program's telehealth capabilities. (8) Participated in the DOE-RMI Meeting in Honolulu. (9) Finalized the agreement with the RMI Ministry of

  6. Wolsong 2, 3, and 4 quarterly progress review report on NSSS design and engineering

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Sung Hoon; Kim, Sun Kee; Park, Tae Keun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-01-01

    This is the Quarterly Progress Review Report for Wolsong NPP 2, 3 and 4 NSSS Design and Engineering which evaluates the performance of the project and describes the project highlight, manpower loading status, design and engineering and project related meetings by quarterly basis. 29 figs., 16 tabs. (Author).

  7. Environmental surveillance program. Quarterly progress report, July--September, 1993

    International Nuclear Information System (INIS)

    Walker, D.W.; Hall, L.F.; Downs, J.

    1996-01-01

    This report contains data developed from monitoring site measurements and laboratory analyses of environmental samples that were collected during the period of July-September, 1993. Because some laboratory procedures are lengthy and could adversely affect the desired timeliness of reports, results of some analyses from this time period will be included in the next quarterly report. Quarterly reports, then, will be routine periodic documents that present continually updated information concerning the potential presence of environmental contaminants in the vicinity of the Idaho National Engineering Laboratory (INEL). During the third calendar quarter of 1993, Environmental Surveillance Program (ESP) measurements did not reveal unexpected levels of contaminants in any environmental samples measured or analyzed. Most of the results reported in this document are related to off-site air and ground water measurements. Future reports will include results of monitoring at additional locations and for additional environmental materials. Annual reports from the ESP will contain data generated during the previous four calendar quarters, and will display measurement trends for various combinations of locations, contaminants and environmental media. The annual report will also include more interpretive material and discussions than will normally be found in quarterly reports

  8. Los Alamos National Laboratory Science Education Programs. Quarterly progress report, April 1--June 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Gill, D.

    1995-09-01

    This report is quarterly progress report on the Los Alamos National Laboratory Science Education Programs. Included in the report are dicussions on teacher and faculty enhancement, curriculum improvement, student support, educational technology, and institutional improvement.

  9. Road Transportable Analytical Laboratory (RTAL) system. Quarterly progress report, May 1994--July 1994

    International Nuclear Information System (INIS)

    1994-01-01

    Progress achieved on the development of the RTAL system during the quarter, May 1 through July 31, 1994 is reported. The work included NEPA analysis, drawings, prototype system construction, and on-site prototype demonstration

  10. Quarterly Progress Report Fuels Development Operation: October - December 1959

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, J. J. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation; Tobin, J. C. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Physical Metallurgy; Minor, J. E. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuel Element Design; Evans, E. A. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Ceramic Fuels Development; Bush, S. H. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuels Fabrication Development

    1960-01-15

    The present Quarterly Report is the continuation of a series issued by the new Fuels Development operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations. Studies formerly reported by the Radiometallurgy, Metallography, and Welding and Corrosion Units, in addition to portions of the Fuels Technology work, are reported elsewhere.

  11. Quarterly Progress Report Fuels Development Operation: January - March 1958

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, J. J. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation; Tobin, J. C. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Physical Metallurgy; Minor, J. E. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuel Element Design; Evans, E. A. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Ceramic Fuels Development; Bush, S. H. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuels Fabrication Development

    1958-04-15

    The present Quarterly Report is the continuation of a series issued by the new Fuels Development operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations. Studies formerly reported by the Radiometallurgy, Metallography, and Welding and Corrosion Units, in addition to portions of the Fuels Technology work, are reported elsewhere.

  12. Quarterly Progress Report Fuels Development Operation: July - September 1957

    Energy Technology Data Exchange (ETDEWEB)

    Bush, S. H. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Physical Metallurgy; Minor, J. E. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuel Element Design; Evans, E. A. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Ceramic Fuels Development; Wallace, W. P. [Hanford Site (HNF), Richland, WA (United States). Fuels Development Operation. Fuels Fabrication Development

    1957-10-15

    The present Quarterly Report is the continuation of a series issued by the new Fuels Development operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations. Studies formerly reported by the Radiometallurgy, Metallography, and Welding and Corrosion Units, in addition to portions of the Fuels Technology work, are reported elsewhere.

  13. Fast Reactor Programme. Third Quarter 1969. Progress Report

    International Nuclear Information System (INIS)

    Hoekstra, E.K.

    1970-02-01

    The RCN research programme on fast spectrum nuclear reactors comprises reactor physics, fuel performance, radiation damage in canning materials, corrosion behaviour in canning materials, aerosol research and heat transfer and hydraulics. An overview is given of the fast reactor experiments at the STEK critical facility in Petten, the Netherlands, in the third quarter of 1969

  14. Consolidated Reprocessing Progam. Quarterly progress report ending February 28, 1979

    International Nuclear Information System (INIS)

    1979-03-01

    This publication continues the quarterly series presenting results of work performed under the Consolidated Reprocessing Program at General Atomic Company. Results of work on this program prior to June 1974 were included in a quarterly series on the HTGR Base Program. The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle

  15. NEPA Project quarterly progress report, April 1--June 30, 1950

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1950-12-31

    Exploration of various types of power plant cycles for nuclear propelled aircraft has been continued during this quarter. The principal current objective of the project is the development of information which will make an intelligent choice of the basic power plant cycle possible. It is still hoped that this choice can be made late in 1950. The survey studies which have been under way for several months continued during the quarter. These consist of analyses and rough preliminary layouts for various types of aircraft, using each of the several basic cycles which have been seriously considered for each of the three phases of development. Although it is still extremely premature to discuss the relative merits of the various cycles, the information so for developed discloses some cycle differences which may, if confirmed by additional work, be significant. In this respect, there have been no recent major changes in the comparative standings of the cycles.

  16. Design of a reactor core in the Oma Full MOX-ABWR

    International Nuclear Information System (INIS)

    Hama, Teruo

    1999-01-01

    The Electric Power Development Co., Ltd. has progressed a construction plan on an improved boiling-water reactor aiming at loading of MOX fuel in all reactor cores (full MOX-ABWR) at Oma-cho, Aomori prefecture, which is a last stage on application of approval on establishment at present. Here were described on outlines of reactor core in the full MOX-ABWR and its safety evaluation. For the full MOX-ABWR loading MOX fuel assembly into all reactor core, thermal and mechanical design analysis of fuel bars and core design analysis were conducted. As a result, it was confirmed that judgement standards in mixed core of MOX fuel and uranium fuel were also applicable as well as that in uranium fuel. (G.K.)

  17. Technical features of ABWR safety systems

    International Nuclear Information System (INIS)

    Sugisaki, Toshihiko; Tominaga, Kenji; Horiuchi, Tetsuo

    1986-01-01

    The engineering safety facilities of ABWRs have been disigned so as to have many excellent characteristics such as safety, reliability and economy, reflecting the merit of adopting new technology such as internal pumps and new control rod driving mechanism, and coupled with the safety peculiar to BWRs. In this paper, about ECCS, containment vessels and others which compose the engineering safety facilities of ABWRs, the characteristics related to the safety owing to the adoption of internal pumps and others, and the evaluation of the performance at the time of various accidents are discussed. As the results of safety evaluation, it was clarified that due to the safety peculiar to ABWRs and the characteristics of the safety facilities, the large increases of safety, reliability and economy have been planned in the ABWRs, and for example, core flooding can be maintained even at the time of a hypothetical loss of coolant accident. BWRs have the simple system constitution, good self controllability, large natural circulation ability, simple operation control method and excellent ability of confining heat and radioactivity. BWRs have three safety functions to stop reactors, to remove heat from reactors, and to confine radioactive substances. These functions of ABWRs were evaluated, and very high safety was confirmed. (Kako, I.)

  18. Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 31, 1956

    Energy Technology Data Exchange (ETDEWEB)

    NA, NA [ORNL

    1957-03-12

    This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of research on circulating-fuel reactors and other ANP research at the Laboratory. The report is divided into five major parts: 1) Aircraft Reactor Engineering, 2) Chemistry, and 3) Metallurgy, 4) Heat Transfer and Physical Properties, Radiation Damage, and Fuel Recovery and Reprocessing, and 5) Reactor Shielding.

  19. Mechanism for Clastogenic Activity of Naphthalene. Quarterly Technical Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Buchholz, B. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-02-05

    The project has two main goals: 1) Identify the types of adducts naphthalene (NA) forms with DNA and 2) determine whether adduct formation correlates with site selective tumor formation in defined subcompartments of the respiratory tract (respiratory and olfactory nasal epithelium and airways of mice, rats and rhesus monkeys). Five tasks are associated with the completion of the goals. Task 1: Contracting and Animal Use Approvals. IACUC and ACURO approvals are complete. The subcontract with UC Davis (UCD) was executed in December 2014. Task 2: Perform In Vitro Study for Goal 1. Rat and mouse samples exposures completed. Monkey samples need to be exposed in next quarter. Task 3: Perform In Vitro Study for Goal 2. Mouse and rat ex vivo exposures completed. Monkey samples need to be completed in the next quarter. Task 4: Sample Preparation and Analysis. Mouse and Rat Goal 2 samples completed. Monkey samples remain to be done for Goal 2. Rat samples completed for Goal 1. Mouse and Monkey samples for Goal 1 need to be completed. Task 5: Data Interpretation and Reporting. Poster will be presented at 2016 Society of Toxicology Meeting. Outline for paper on adduct formation complete and similar to poster for SOT meeting.

  20. Full MOX core design in ABWR

    International Nuclear Information System (INIS)

    Ihara, Toshiteru; Mochida, Takaaki; Izutsu, Sadayuki; Fujimaki, Shingo

    2003-01-01

    Electric Power Development Co., Ltd. (EPDC) has been investigating an ABWR plant for construction at Oma-machi in Aomori Prefecture. The reactor, termed FULL MOX-ABWR will have its reactor core eventually loaded entirely with mixed-oxide (MOX) fuel. Extended use of MOX fuel in the plant is expected to play important roles in the country's nuclear fuel recycling policy. MOX fuel bundles will initially be loaded only to less than one-third of the reactor, but will be increased to cover its entire core eventually. The number of MOX fuel bundles in the core thus varies anywhere from 0 to 264 for the initial cycle and, 0 to 872 for equilibrium cycles. The safety design of the FULL MOX-ABWR briefly stated next considers any probable MOX loading combinations out of such MOX bundle usage scheme, starting from full UO 2 to full MOX cores. (author)

  1. Alarm system for ABWR main control panels

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Yuji; Saito, Koji [Toshiba Corp., Yokohoma (Japan)

    1997-09-01

    TOSHIBA has developed integrated digital control and instrumentation system for ABWR, which is the third-generation man machine interface system for main control room that we call A-PODIA (Advanced PODIA). A-Podia has been introduced the first actual ABWR plant in Japan. in A-PODIA, TOSHIBA has realized improvement of alarm system that all operator crews in the control room can recognize plant anomalies easily. The alarm system can recognize essential alarms for plant safety easily and understand annunciators with each integrated annunciators and their prioritized color easily by classifying alarms into plant-level essential annunciators, system-level integrated annunciators and equipment level individual annunciators with hierarchical structure. This paper describes conventional alarm system and the design philosophy, alarm system design and operation of ``Alarm System for ABWR Main Control Panels``. (author). 5 refs, 8 figs, 1 tab.

  2. Alarm system for ABWR main control panels

    International Nuclear Information System (INIS)

    Kobayashi, Yuji; Saito, Koji

    1997-01-01

    TOSHIBA has developed integrated digital control and instrumentation system for ABWR, which is the third-generation man machine interface system for main control room that we call A-PODIA (Advanced PODIA). A-Podia has been introduced the first actual ABWR plant in Japan. in A-PODIA, TOSHIBA has realized improvement of alarm system that all operator crews in the control room can recognize plant anomalies easily. The alarm system can recognize essential alarms for plant safety easily and understand annunciators with each integrated annunciators and their prioritized color easily by classifying alarms into plant-level essential annunciators, system-level integrated annunciators and equipment level individual annunciators with hierarchical structure. This paper describes conventional alarm system and the design philosophy, alarm system design and operation of ''Alarm System for ABWR Main Control Panels''. (author). 5 refs, 8 figs, 1 tab

  3. Design of full MOX core in ABWR

    International Nuclear Information System (INIS)

    Kinoshita, Y.; Hirose, T.; Sasagawa, M.; Sakuma, T

    1999-01-01

    A Full MOX-ABWR, loaded with mixed-oxide (MOX) fuels of up to 100% of the core, is planned. Increased MOX fuel utilization will result in greater savings of uranium. Studies on the fuel rod thermal-mechanical design, the core design and the safety evaluation have been made, and the results are summarized in this paper. To sum it all up, the safety of the Full MOX-ABWR has been confirmed through design evaluations adequately considering the MOX fuel and core characteristics. (author)

  4. Commercial LFCM vitrification technology. Quarterly progress report, October-December 1984

    Energy Technology Data Exchange (ETDEWEB)

    Burkholder, H.C.; Jarrett, J.H. (comps.)

    1985-07-01

    This report is the first in a series of quarterly reports compiled by the Nuclear Waste Treatment Program Office at Pacific Northwest Laboratory to document progress on commercial liquid-fed ceramic melter (LFCM) vitrification technology. Progress in the following technical subject areas during the first quarter of FY 1985 is discussed: pretreatment systems, melting process chemistry, glass development and characterization, feed preparation and transfer systems, melter systems, canister filling and handling systems, off-gas systems, process/product modeling and control, and supporting studies. 33 figs., 12 tabs.

  5. Performance Plan: Progress Report 2nd Quarter Fiscal Year 2000.

    Science.gov (United States)

    Department of Education, Washington, DC. Student Financial Assistance.

    This document is progress report on the U.S. Department of Education's Student Financial Assistance (SFA) programs. Regarding its customer satisfaction objective, SFA notes that it looks to private sector leaders in e-commerce and promotes electronic services; offers electronic filing of the Free Application For Student Aid (FAFSA); offers most…

  6. Baseline Gas Turbine Development Program. Fourteenth quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, F W; Wagner, C E

    1976-04-30

    Progress is reported for a Baseline Gas Turbine Development Program sponsored by the Heat Engine Systems Branch, Division of Transportation Energy Conservation (TEC) of the Energy Research and Development Administration (ERDA). Structurally, this program is made up of three parts: (1) documentation of the existing automotive gas turbine state-of-the-art; (2) conduction of an extensive component improvement program; and (3) utilization of the improvements in the design, and building of an Upgraded Engine capable of demonstrating program goals.

  7. Nuclear waste management. Quarterly progress report, October-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-04-01

    Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

  8. Nuclear waste management. Quarterly progress report, April-June 1979

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1979-09-01

    Progress is reported on: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste solidification process; TRU waste immobilization; krypton solidification; /sup 14/C and /sup 129/I fixation; waste management system and safety studies; waste isolation safety assessment; well logging instrumentation development for shallow land burial; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. 9 figures, 14 tables. (DLC)

  9. Electronic refrigerant leak detector. Quarterly technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Talamas, E. Jr.

    1998-10-15

    The project comprises three main tasks. They are (1) Develop, design, and fabricate sensors, (2) Develop, design, and fabricate test instruments, (3) Testing and data analysis. The milestone includes 17 sub-tasks for the 52-weeks project period, starting on May 1, 1998 and ending on April 30, 1999. As stated in the Application for Federal Assistance, Micronic intended to relocate to a new office by June of 1998. This decision was delayed, since the first partial payment was transferred on August 12, 1998. Micronic plans to relocate this November. A second Provisional Application for a US patent has been filed. Progress made during this period is reported.

  10. LFCM [liquid-fed ceramic melter] vitrification technology: Quarterly progress report, January--March 1987

    International Nuclear Information System (INIS)

    Brouns, R. A.; Allen, C. R.; Powell, J. A.

    1988-05-01

    This report is compiled by the Nuclear Waste Treatment Program and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to describe the progress in developing, testing, applying and documenting liquid-fed ceramic melter vitrification technology. Progress in the following technical subject areas during the second quarter of FY 1987 is discussed: melting process chemistry and glass development, feed preparation and transfer systems, melter systems, canister filling and handling systems, and process/product modeling. 23 refs., 14 figs., 10 tabs

  11. Fuel performance improvement program. Quarterly/annual progress report, October 1977--September 1978

    International Nuclear Information System (INIS)

    Crouthamel, C.E.

    1978-10-01

    This quarterly/annual report reviews and summarizes the activities performed in support of the Fuel Performance Improvement Program (FPIP) during Fiscal Year 1978 with emphasis on those activities that transpired during the quarter ending September 30, 1978. Significant progress has been made in achieving the primary objectives of the program, i.e., to demonstrate commercially viable fuel concepts with improved fuel - cladding interaction (FCI) behavior. This includes out-of-reactor experiments to support the fuel concepts being evaluated, initiation of instrumented test rod experiments in the Halden Boiling Water Reactor (HBWR), and fabrication of the first series of demonstration rods for irradiation in the Big Rock Point Reactor

  12. Quarterly progress report on the NSRR experiments, (4)

    International Nuclear Information System (INIS)

    Ishikawa, Michio; Tomii, Kakuzo; Hoshi, Tsutao; Onishi, Nobuaki; Saito, Shinzo

    1977-10-01

    Fuel behavior studies under simulated Reactivity Initiated Accident, (RIA), conditions have been in progress in NSRR since October 1975. About 200 tests have been conducted to investigate the fuel failure threshold, failure mechanisms and pressure pulse generation at fuel failure using unirradiated PWR and BWR type test rods. This report describes the test results obtained during the half year period from January through June 1977. A total of 61 tests were performed during this period. The tests consisted of six test series; i.e. scoping test, fuel enrichment parameter test, pre-pressurized rod test, flow area simulated test, bundled rod test and waterlogged rod test series. Objectives, major results and test number of each test series are summarized in Table. Test rod power calibrations were also performed in this period. The measurements were conducted both by chemical analysis of fission products and by a calorimetric method. The results obtained from these two different methods showed a good agreement. It was concluded that the former values of energy deposition which were based on calculations were 9%, 14% and 11% smaller than the actual values for 5%, 10% and 20% enrichment fuel rods respectively. The newly calibrated values are used in this report. Older values are also indicated in parentheses as reference to previously reported data. (auth.)

  13. Modern technology applied in the advanced BWR (ABWR)

    International Nuclear Information System (INIS)

    Hucik, S.A.

    1988-01-01

    The advanced boiling water reactor (ABWR) represents the next generation of light water reactors (LWR) to be introduced into commercial operation in the 1990's. The ABWR is the result of the continuing evolution of the BWR, incorporating state-of-the-art technology and improvements based on worldwide experience, and extensive design and test and development programs. This paper discusses how the ABWR development objective focused on an optimized selection of advanced technologies and proven BWR technologies. A technical evaluation of the ABWR shows its superiority in terms of performance characteristics and economics relative to current LWR designs

  14. Projects at the component development and integration facility. Quarterly technical progress report, April 1, 1994--June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY94. The CDIF is a major Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; and Spray Casting Project

  15. Heat Source Technology Programs. Quarterly progress report, April--June 1993

    Energy Technology Data Exchange (ETDEWEB)

    George, T.G. [comp.

    1993-12-01

    This quarterly report describes activities performed in support of Cassini fueled-clad production and studies related to the use of {sup 238}PuO{sub 2} in radioisotope power systems carried out for the Office of Special Applications of the US Department of Energy (DOE) by Los Alamos National Laboratory (LANL). Most of the activities described are ongoing; the results and conclusions described may change as the work progresses.

  16. Short-rotation woody-crops program. Quarterly progress report for period ending May 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Cushman, J.H.; Ranney, J.W.

    1982-04-01

    Progress of twenty projects in the Short Rotation Woody Crops Program is summarized for the period March 1 through May 31, 1981. Individual quarterly reports included from each of the projects discuss accomplishments within specific project objectives and identify recent papers and publications resulting from the research. The major project activities are species screening and genetic selection, stand establishment and cultural treatment, and harvest, collection, transportation, and storage.

  17. Short-rotation woody-crops program. Quarterly progress report for period ending August 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Cushman, J.H.; Ranney, J.W.

    1982-04-01

    Progress of twenty-one projects in the Short Rotation Woody Crops Program is summarized for the period June 1 through August 31, 1981. Individual quarterly reports included from each of the projects discuss accomplishments within specific project objectives and identify recent papers and publications resulting from the research. The major program activities are species screening and genetic selection, stand establishment and cultural treatment, and harvest, collection, transportation, and storage.

  18. Commercial Alpha Waste Program. Quarterly progress report, January--March, 1975

    International Nuclear Information System (INIS)

    Cooley, C.R.

    1975-10-01

    This is the fourth quarterly progress report on the Commercial Alpha Waste Program being conducted at the Hanford Engineering Development Laboratory (HEDL) for the Division of Nuclear Fuel Cycle and Production, U. S. Energy Research and Development Administration. Data on waste composition for fuel reprocessing operations are discussed as well as information on radwaste generation at nuclear power reactors. Progress to date on development of the acid digestion process for treating combustible waste is discussed including initial studies using a critically safe tray digester. Data on alpha waste generation and product storage are also presented

  19. Hanford Federal Facility Agreement and Consent Order, quarterly progress report, March 31, 1992

    International Nuclear Information System (INIS)

    1992-05-01

    This is the twelfth quarterly report as required by the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1990), established between the US Department of Energy (DOE), the US Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology). The Tri-Party Agreement sets the plan and schedule for achieving regulatory compliance and cleanup of waste sites at the Hanford Site. This report covers progress for the quarter that ended March 31, 1992. Topics covered under technical status include: disposal of tank wastes; cleanup of past-practice units; permitting and closure of treatment, storage, and disposal units; and other tri-party agreement activities and issues

  20. Co-sponsored second quarter progress review conference on district heating

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-01

    A summary of the progress review conference on district heating and cooling systems is presented. The agenda and lists of speakers and attendees are presented. A history of district heating and some present needs and future policies are given and an excerpt from the National District Heating Program Strategy (DOE, March 1980) is included. Following the presentation, District Heating and Cooling Systems Program, by Alan M. Rubin, a fact sheet on DOE's Integrated Community Energy Systems Program and information from an oral presentation, District Heating and Cooling Systems for Communities Through Power Plant Retrofit Distribution Network, are given. The Second Quarterly Oral Report to the US DOE on the District Heating and Cooling Project in Detroit; the executive summary of the Piqua, Ohio District Heating and Cooling Demonstration Project; the Second Quarterly Report of the Moorehead, Minnesota District Heating Project; and the report from the Moorehead, Minnesota mayor on the Hot Water District Heating Project are presented.

  1. Power systems development facility. Quarterly technical progress report, January 1, 1994--March 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This quarterly technical progress report summarizes work completed during the last quarter of the Second Budget Period, January 1 through March 31, 1994, entitled {open_quotes}Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.{close_quotes} The objective of this project is to evaluate hot gas particulate control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size.

  2. [Geothermal system temperature-depth database and model for data analysis]. 5. quarterly technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Blackwell, D.D.

    1998-04-25

    During this first quarter of the second year of the contract activity has involved several different tasks. The author has continued to work on three tasks most intensively during this quarter: the task of implementing the data base for geothermal system temperature-depth, the maintenance of the WWW site with the heat flow and gradient data base, and finally the development of a modeling capability for analysis of the geothermal system exploration data. The author has completed the task of developing a data base template for geothermal system temperature-depth data that can be used in conjunction with the regional data base that he had already developed and is now implementing it. Progress is described.

  3. Decontamination Systems Information and Research Program. Quarterly technical progress report, January 1--March 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

    West Virginia University (WVU) and the US DOE Morgantown Energy Technology Center (METC) entered into a Cooperative Agreement on August 29, 1992 entitled ``Decontamination Systems Information and Research Programs.`` Stipulated within the Agreement is the requirement that WVU submit to METC a series of Technical Progress Reports on a quarterly basis. This report comprises the first Quarterly Technical Progress Report for Year 2 of the Agreement. This report reflects the progress and/or efforts performed on the sixteen (16) technical projects encompassed by the Year 2 Agreement for the period of January 1 through March 31, 1994. In situ bioremediation of chlorinated organic solvents; Microbial enrichment for enhancing in-situ biodegradation of hazardous organic wastes; Treatment of volatile organic compounds (VOCs) using biofilters; Drain-enhanced soil flushing (DESF) for organic contaminants removal; Chemical destruction of chlorinated organic compounds; Remediation of hazardous sites with steam reforming; Soil decontamination with a packed flotation column; Use of granular activated carbon columns for the simultaneous removal of organics, heavy metals, and radionuclides; Monolayer and multilayer self-assembled polyion films for gas-phase chemical sensors; Compact mercuric iodide detector technology development; Evaluation of IR and mass spectrometric techniques for on-site monitoring of volatile organic compounds; A systematic database of the state of hazardous waste clean-up technologies; Dust control methods for insitu nuclear and hazardous waste handling; Winfield Lock and Dam remediation; and Socio-economic assessment of alternative environmental restoration technologies.

  4. PFBC HGCU Test Facility. Technical progress report No. 24, Third quarter, CY 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This is the twenty-fourth and final Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the work completed during the Third Quarter of CY 1995. All activity this quarter was directed toward the completion of the program final report. A draft copy of the final report was forwarded to DOE during this quarter, and DOE submitted their comments on the report to AEPSC. DOE requested that Westinghouse write an appendix to the report covering the performance of the fail-safe regenerator devices during Tad operation, and Westinghouse subsequently prepared the appendix. Additional DOE comments were incorporated into the report, and it will be issued in camera-ready form by the end of October, 1995, which is the program end date. Appendix 1 presents the results of filter candle posttest examination by Westinghouse performed on selected filter candles following final shutdown of the system.

  5. Salt repository project: Technical progress report for the quarter 1 April--30 June 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of Energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation

  6. Fossil-energy program. Quarterly progress report for June 30, 1983

    Energy Technology Data Exchange (ETDEWEB)

    McNeese, L.E.

    1983-08-01

    This quarterly report covers the progress made during the period March 31 through June 30 for the Oak Ridge National Laboratory research and development projects that are carried out in support of the increased utilization of coal and other fossil fuels as sources of clean energy. These projects are supported by various parts of DOE including Fossil Energy, Basic Energy Sciences, Office of Health and Environmental Research, Office of Environmental Compliance and Overview, the Electric Power Research Institute, and by the Tennessee Valley Authority and the EPA Office of Research and Development through inter-agency agreement with DOE.

  7. Salt Repository Project technical progress report for the quarter 1 January--31 March 1987

    International Nuclear Information System (INIS)

    1988-03-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation. 23 refs., 1 fig

  8. Application of ABWR construction database to nuclear power plant project

    International Nuclear Information System (INIS)

    Takashima, Atsushi; Katsube, Yasuhiko

    1999-01-01

    Tokyo Electric Power Company (TEPCO) completed the construction of Kashiwazaki-Kariwa Nuclear Power Station Unit No. 6 and No. 7 (K-6/7) as the first advanced boiling water reactors (ABWR) in the world successfully. K-6 and K-7 started their commercial operations in November, 1996 and in July, 1997 respectively. We consider ABWR as a standard BWR in the world as well as in Japan because ABWR is highly reputed. However, because the interval of our nuclear power plant construction is going to be longer, our engineering level on plant construction will be declining. Hence it is necessary for us to maintain our engineering level. In addition to this circumstance, we are planning to wide application of separated purchase orders for further cost reduction. Also there is an expectation for our contribution to ABWR plant constructions overseas. As facing these circumstances, we have developed a construction database based on our experience for ABWR construction. As the first step of developing the database for these use, we analyzed our own activities in the previous ABWR construction. Through this analysis, we could define activity units of which the project consists. As the second step, we clarified the data which are treated in each activity unit and the interface among them. By taking these steps, we could develop our database efficiently. (author)

  9. Human-system interfaces for the ABWR control room

    International Nuclear Information System (INIS)

    Gutierrez, R.; O'Neil, T.J.

    1993-01-01

    The 1300-MW(electric) advanced boiling water reactor (ABWR) design has been developed by General Electric Co. (G.E.) and its technical associates, Hitachi Ltd. and Toshiba Corporation, under the sponsorship of the Tokyo Electric Power Company. Key features of the ABWR include simplification, improved safety and reliability, reduced occupational exposure and radwaste, improved maneuverability, and reduced construction, fuel, and operating costs. The ABWR incorporates the best proven features from BWR designs in Japan, Europe, and the United States, combined with the broad-scope application of leading-edge technology. The first application of the ABWR design will be at TEP-CO's Kashiwazaki-Kariwa nuclear power station units 6 and 7, which are scheduled to begin commercial operation in 1996 and 1997, respectively. The ABWR is also the lead plant in the U.S. standard plant design certification program. It is scheduled to receive final approval from the U.S. Nuclear Regulatory Commission in early 1994. The development of the human system interaces (HSI) for the ABWR is an extension of the operating experience of existing man-machine interfaces currently being used at GE-designed plants

  10. Geothermal direct-heat utilization assistance. Quarterly project progress report, October--December 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    This report summarizes geothermal technical assistance, R and D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the first quarter of FY-98 (October--December 1997). It describes 216 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include requests for general information including maps and material for high school debates, and material on geothermal heat pumps, resource and well data, space heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, electric power and snow melting. Research activities include work on model construction specifications of lineshaft submersible pumps and plate heat exchangers, a comprehensive aquaculture developer package and revisions to the Geothermal Direct Use Engineering and Design Guidebook. Outreach activities include the publication of the Quarterly Bulletin (Vol. 18, No. 4) which was devoted entirely to geothermal activities in South Dakota, dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisition and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

  11. Federal assistance program. Quarterly project progress report, January 1998--March 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report summarizes geothermal technical assistance, R&D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the second quarter of FY-98-98 (January-March, 1998). It describes 268 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include requests for general information including maps and material for high school debates, and material on geothermal heat pumps, resource and well data, spacing heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, electric power and snow melting. Research activities include work on model construction specifications for line shaft submersible pumps and plate heat exchangers and a comprehensive aquaculture developer package. The revised Geothermal Direct Use Engineering and Design Guidebooks was completed, published and is available for distribution. Outreach activities include the publication of the Quarterly Bulletin (Vol. 19, No. 1) which was devoted entirely to geothermal equipment, dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisitions and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

  12. Damage analysis and fundamental studies. Quarterly progress report, October--December 1978

    Energy Technology Data Exchange (ETDEWEB)

    Zwilsky, Klaus M.

    1979-05-01

    This report is the fourth in a series of Quarterly Technical Progress Reports on Damage Analysis and Fundamental Studies (DAFS) which is one element of the Fusion Reactor Materials Program, conducted in support of the Magnetic Fusion Energy Program. This report is organized along topical lines in parallel to a Program Plan of the same title (to be published) so that activities and accomplishments may be followed readily relative to the Program Plan. Thus, the work of a given laboratory may appear throughout the report. Chapters 1 and 2 report topics which are generic to all of the DAFS Program: DAFS Task Group Activities and Irradiation Test Facilities, respectively. Chapters 3, 4, and 5 report the work that is specific to each of the subtasks around which the program is structured: A) Environmental Characterization, B) Damage Production, and C) Damage Microstructure Evolution and Mechanical Behavior.

  13. Fast Breeder Blanket Facility. Quarterly progress report, July 1, 1978--September 30, 1978

    International Nuclear Information System (INIS)

    Clikeman, F.M.

    1978-09-01

    This quarterly progress report summarizes work done at Purdue University's Fast Breeder Blanket Facility for the Department of Energy during the months July to September 1978. The summary includes reports on the models and methods used to characterize the FBBF facility. Using the reported models and calculational methods and computer codes a new cross section set has been generated, self-shielded for 300 0 K for use in all FBBF calculations using the 2DB computer code. The summary includes reports of the reproducability of foil activation data and measurements of the azmuthal symmetry of the facility. The status of the development of technique for the experimental measurements and preliminary foil activation measurements are also reviewed

  14. Damage analysis and fundamental studies. Quarterly progress report, July--September 1978

    Energy Technology Data Exchange (ETDEWEB)

    Zwilsky, Klaus M.

    1979-05-01

    This report is the third in a series of Quarterly Technical Progress Reports on Damage Analysis and Fundamental Studies (DAFS) which is one element of the Fusion Reactor Materials Program, conducted in support of the Magnetic Fusion Energy Program. This report is organized along topical lines in parallel to Section II, Damage Analysis and Fundamental Studies (DOE/ET-0032/2), of the Fusion Reactor Materials Program Plan so that activities and accomplishments may be followed readily relative to that Program Plan. Thus, the work of a given laboratory may appear throughout the report. Chapters 1 and 2 report topics which are generic to all of the DAFS Program: DAFS Task Group Activities and Irradiation Test Facilities, respectively. Chapters 3, 4, and 5 report the work that is specific to each of the subtasks around which the program is structured: A) Environmental Characterization, B) Damage Production, and C) Damage Microstructure Evolution and Mechanical Behavior.

  15. Outline of the advanced boiling water reactor (ABWR)

    International Nuclear Information System (INIS)

    Hucik, S.A.; Imaoka, T.; Minematsu, A.; Takashima, Y.

    1986-01-01

    The fundamental design of the Advanced Boiling Water Reactor (ABWR) was completed in December 1985. This design represents the next generation of Boiling Water Reactors (BWR) to be introduced into commercial operation in the 1990s. The ABWR is the result of the continuing evolution of the BWR, incorporating state-of-the-art technologies and many new improvements based on an extensive accumulation of world-wide experience through design, construction and operation of BWRs. The ABWR development program was initiated in 1978, with subsequent design and test and development programs started in 1981. Most of the development and verification tests of the new features have been completed. The ABWR development objective focused on an optimized selection of advanced technologies and proven BWR technologies. The ABWR objectives were specific improvements such as operating and safety margins, enhanced availability and capacity factor, and reduced occupational exposure while at the same time achieving significant cost reduction in both capital and operating costs. The ABWR is characterized by an improved NSSS including ten internal recirculation pumps, fine motion electric-hydraulic control rod drives, optimized safety and auxiliary systems, advanced control and instrumentation systems, improved turbine-generator with moisture/separator reheater with plant output increased to 1350 MWe, and an integrated reinforced concrete containment vessel and compact Reactor and Turbine Building design. The turbine system also included improvements in the Turbine-Generator, feedwater/heater system, and condensate treatment systems. The radwaste system was also optimized taking advantage of the plant design improvements and advances in radwaste technology. The ABWR is a truly optimal design which utilizes advanced technologies, capabilities, performance improvements, and yet provides an economic advantage. (author)

  16. Automated Array Assembly, Phase 2. Quarterly technical progress report, fourth quarter 1977. Texas Instruments report No. 03-77-56

    Energy Technology Data Exchange (ETDEWEB)

    Carbajal, B.G.

    1978-01-01

    The Automated Array Assembly Task, Phase 2 of the Low Cost Silicon Solar Array (LSSA) Project, is a process development task. This contract includes solar cell module process development activities in the areas of Surface Preparation, Plasma Processing, Diffusion, Cell Processing and Module Fabrication. In addition, a High Efficiency Cell Development Activity is included. During this quarter, effort was concentrated on wafer etching for saw damage removal, establishing a standard phosphorous diffusion process and a baseline solar cell process as a test bed, designing a large area square cell including test sites, analyzing module layouts for optimum packing efficiency and fabricating the first Tandem Junction Cells (TJC) for this contract. A TJC with backside contacts gave 15.1% efficiency at AM1.

  17. Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy: Quarter ending September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Ruhter, W.D.; Strait, R.S.; Mansur, D.L.; Davis, G.

    1993-10-01

    The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the fourth quarter of Fiscal Year 1993 (July through September, 1993). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise. These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in five areas: Safeguards Technology, Safeguard System Studies, Computer Security, DOE Automated Physical Security and DOE Automated Visitor Access Control System. The remainder of this report describes the activities in each of these five areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.

  18. Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the U.S. Department of Energy. Quarter ending December 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Davis, G.; Mansur, D.L.; Ruhter, W.D.; Strauch, M.S.

    1997-01-01

    The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the First Quarter of Fiscal Year 1997 (October through December, 1996). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise. These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in four areas: (1) safeguards technology; (2) safeguards and material accountability; (3) computer security--distributed systems; and (4) physical and personnel security support. The remainder of this report describes the activities in each of these four areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.

  19. Superconducting fault current limiter. Fifth quarterly technical progress report, August 8, 1978-November 7, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Progress in the development of fault current limiters for superconducting power transmission systems is reported. The analysis and design of a magnetically switched resistive device and the experimental program were emphasized and reported. A transient heat transfer model was developed which indicates the parameters which are important in determining the thermal heating and recovery of the superconduting film. Designs for the switching coil and the S/C element were also carried out and are reported. A four-pole magnetic coil is recommended; this generates a magnetic field which is nearly perpendicular to spiral or helical S/C film geometrics. A spirally-designed, 3000 ohm limiter is shown to be able to fit within a .5 to 1m inner radius, .05 to .03 m wide, 1.3 to 3.9 m long annualr region. The experimental program has included work on materials development and on prepartion of the switching and thermal recovery experimental facility. The material development program has uncovered several serious short-comings of NbN as the S/C film material. Macroscopic holes and surface debris, and microscopic imperfections reduce the critical current density below the expected value and, in addition, cause nonuniform switching. Reasons for these effects are postulated, and a continuing, vigorous materials program is suggested in hopes of alleviating these problems. Virtually all of the experimental equipment had been installed, and so the magnetic switching and thermal recovery experiments can begin and progress during the next quarter. (LCL)

  20. Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, Part 1 - 5

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, W. H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cramer, S. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Miller, A. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    1957-03-12

    This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and other ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into five major parts: 1. Aircraft Reactor Engineering, 2. Chemistry, 3. Metallurgy, 4. Heat Transfer and Physical Properties, Radiation Damage, and Fuel Recovery and Reprocessing, and 5. Reactor Shielding. The ANP Project is comprised of about 550 technical and scientific personnel engaged in many phases of research directed toward the achievement of nuclear propulsion of aircraft. A considerable portion of this research is performed in support of the work of other organizations participating in the national ANP effort. However, the bulk of the ANP research at ORNL is directed toward the development of a circulating-fuel type of reactor. The design, construction, and operation of the Aircraft Reactor Test (ART), with the cooperation of the Pratt & Whitney Aircraft Division, are the current objectives of the project. The ART is to be a power plant system that will include a 60-Mw circulating fuel reflector-moderator reactor and adequate means for heat disposal. Operation of the system will be for the purpose of determining feasibility and for studying the problems associated with the design, construction, and operation of a high-power circulating-fuel refIector-moderated aircraft reactor system.

  1. Power systems development facility. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This quarterly technical progress report summarizes work completed during the Second Quarter of the Second Budget Period, July 1 through September 30, 1993, under the Department of Energy (DOE) Cooperative Agreement No. DE-FC21-90MC25140 entitled ``Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.`` The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scaleup of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the existing Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. Hot Gas Cleanup Units to mate to all gas streams; Combustion Gas Turbine; and Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility.

  2. Hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    This report is the quarterly progress report for July through September 1995 for work done by Tulane and Xavier Universities under DOE contract number DE-FG01-93-EW53023. Accomplishments for various tasks including administrative activities, collaborative cluster projects, education projects, initiation projects, coordinated instrumentation facility, and an investigators` retreat are detailed in the report.

  3. The Amarillo National Resource Center for Plutonium. Quarterly progress detailed report, 1 November 1996--31 January 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    Progress for this quarter is given for each of the following Center programs: (1) plutonium information resource; (2) advisory function (DOE and state support); (3) environmental, public health and safety; (3) communication, education, and training; and (4) nuclear and other material studies. Both summaries of the activities and detailed reports are included.

  4. Technical features of advanced boiling water reactor (ABWR)

    International Nuclear Information System (INIS)

    Horiuchi, Tetsuo; Takashima, Yoshie; Yokomi, Michiro

    1986-01-01

    As the final stage of the development of ABWRs of 1300 MWe output class carried out since 1984, the design for optimizing the plants has been performed, but it was completed at the end of 1985. Hereafter, the ABWRs will advance to the development of the actual project toward the permission and approval and the construction. By the optimization, the simplification, compacting and the heightening of thermal efficiency of the ABWRs were further promoted. The above promotion was attained by a cylindrical concrete containment vessel constructed in one body with the structure of a reactor building, the optimization of the redundancy of facilities, the optimization of equipment size, the combination of a two-stage reheating, 52 in blade turbine and the recovery of heater drain and so on. The plant characteristics such as the capacity factor, operability and the radiation exposure dose of workers were examined in detail in the process of optimization. As the results, it was shown that the ABWRs have the excellent economical efficiency and the performance characteristics of high level. The technical features of the ABWRs are large capacity and high efficiency plants, the improved core adopting internal pumps and new control rod driving mechanism, rational waste treatment facilities and so on. (Kako, I.)

  5. Hitachi's experience and achievements in ABWR construction

    International Nuclear Information System (INIS)

    Inoue, Takashi; Miura, Jun; Murayama, Kouichi

    2003-01-01

    Hitachi, Ltd. (Hitachi) is taking charge of the turbine island of Chubu Electric Power Company's Hamaoka nuclear power plant Unit No. 5 (Hamaoka 5), and all facilities of Hokuriku Electric Power Company's Shika Nuclear Power Station Unit No. 2 (Shika 2). Hitachi has achieved shorter schedules and lower costs in the two projects with the following construction methods. First, Hitachi applied modularization and the area-by-area method. These methods enable us to undertake building and installation work in parallel. Second, the floor packaging construction method enables us to finish installation in every area earlier than conventional methods. Moreover, manpower can be distributed evenly. This paper reports the application of these advanced construction methods to the Hamaoka 5 and Shika 2 projects. Installations such as RCCV modules and condenser blocks are presented in this paper. In addition, Hitachi is using 3D-CAD engineering and our own construction management system to optimize the planning of construction procedures and the installation of equipment in these projects. Thus Hitachi is always striving to improve the reliability, safety and economy of ABWR construction technologies. (author)

  6. Fuel gas production from animal and agricultural residues and biomass. Quarterly coordination meeting, December 11-12, 1978, Denver, Colorado. Second Quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Wise, D L; Ashare, E; Wentworth, R L

    1979-01-05

    The tenth quarterly coordination meeting of the methane production group of the Fuels from Biomass Systems Branch, US Department of Energy was held at Denver, Colorado, December 11-12, 1978. Progress reports were presented by the contractors and a site visit was made to the Solar Energy Research Institute, Golden, Colorado. A meeting agenda, a list of attendees, and progress are presented. Report titles are: pipeline fuel gas from an environmental feedlot; operation of a 50,000 gallon anaerobic digester at the Monroe State Dairy Farm near Monroe, Washington; anaerobic fermentation of livestock and crop residues; anaerobic fermentation of agricultural residues - potential for improvement and implementation; heat treatment of organics for increasing anaerobic biodegradability; and biological conversion of biomass to methane. (DC)

  7. Quarterly progress report on the evaluation of critical materials for photovoltaic cells

    Energy Technology Data Exchange (ETDEWEB)

    Watts, R.L.; Pawlewicz, W.W.; Gurwell, W.E.; Jamieson, W.M.; Long, L.W.; Smith, S.A.; Teeter, R.R.

    1979-09-01

    The scope of the activities included in this program are as follows: (1) characterize new and improved photovoltaic cell designs and production processes for subsequent analysis; (2) review or screen these designs for potential material shortages or other constraints; (3) carry out investigations of the probable costs of new sources of materials potentially in short supply, concentrating on gallium and indium; and (4) identify options for coping with or mitigating the problems identified. The methodology and data base used in the CMAP (Critical Material Analysis Program) computer program were developed as part of a broad scale DOE program to review the potential material constraints of all solar programs. The photovoltaic report screened 13 cells in 15 systems and assumed 100% material utilization (process efficiency) in producing the photovoltaic cells. This study emphasizes the availability of cell fabrication feedstock materials and the effects of process efficiencies on material availability by adding characterizations of photovoltaic production processes. This quarterly report presents the results of work with emphasis on Task I, the characterization of photovoltaic cells and their production processes. Task IIA, CMAP Modification, Data Base Development and Operation has been initiated. Task IIB, Review, Integration, Interpretation and Analysis of Screening will begin once the baseline screening has been completed in Task IIA. Work on Task IIIA, the Assessment of Future Costs and Supplies of Gallium and Indium and Task IIIB, Economics of Coal Derived PV Materials have been initiated. Progress and initial results are reported. (WHK)

  8. Thermal energy storage for building heating and cooling applications. Quarterly progress report, April--June 1976

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, H.W.; Kedl, R.J.

    1976-11-01

    This is the first in a series of quarterly progress reports covering activities at ORNL to develop thermal energy storage (TES) technology applicable to building heating and cooling. Studies to be carried out will emphasize latent heat storage in that sensible heat storage is held to be an essentially existing technology. Development of a time-dependent analytical model of a TES system charged with a phase-change material was started. A report on TES subsystems for application to solar energy sources is nearing completion. Studies into the physical chemistry of TES materials were initiated. Preliminary data were obtained on the melt-freeze cycle behavior and viscosities of sodium thiosulfate pentahydrate and a mixture of Glauber's salt and Borax; limited melt-freeze data were obtained on two paraffin waxes. A subcontract was signed with Monsanto Research Corporation for studies on form-stable crystalline polymer pellets for TES; subcontracts are being negotiated with four other organizations (Clemson University, Dow Chemical Company, Franklin Institute, and Suntek Research Associates). Review of 10 of 13 unsolicited proposals received was completed by the end of June 1976.

  9. Enforcement actions: significant actions resolved. Quarterly progress report, July-September 1982

    International Nuclear Information System (INIS)

    1982-10-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July to September 1982) and includes copies of letters, notices, and orders sent by the Nuclear Regulatory Commission to the licensee with respect to the enforcement action. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, in the interest of promoting public health and safety as well as common defense and security. This publication is issued on a quarterly basis to include significant enforcement actions resolved during the preceding quarter

  10. Enforcement actions: significant actions resolved. Quarterly progress report, January-June 1982

    International Nuclear Information System (INIS)

    1982-09-01

    This compilation summarizes significant enforcement actions that have been resolved during two quarterly periods (January to June 1982) and includes copies of letters, notices, and orders sent by the Nuclear Regulatory Commission to the licensee with respect to the enforcement action. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, in the interest of promoting public health and safety as well as common defense and security. The intention is that this publication will be issued on a quarterly basis to include significant enforcement actions resolved during the preceding quarter

  11. Solvent refined coal (SRC) process. Quarterly technical progress report, January 1980-March 1980. [In process streams

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    This report summarizes the progress of the Solvent Refined Coal (SRC) project at the SRC Pilot Plant in Fort Lewis, Wahsington, and the Process Development Unit (P-99) in Harmarville, Pennsylvania. After the remaining runs of the slurry preheater survey test program were completed January 14, the Fort Lewis Pilot Plant was shut down to inspect Slurry Preheater B and to insulate the coil for future testing at higher rates of heat flux. Radiographic inspection of the coil showed that the welds at the pressure taps and the immersion thermowells did not meet design specifications. Slurry Preheater A was used during the first 12 days of February while weld repairs and modifications to Slurry Preheater B were completed. Two attempts to complete a material balance run on Powhatan No. 6 Mine coal were attempted but neither was successful. Slurry Preheater B was in service the remainder of the quarter. The start of a series of runs at higher heat flux was delayed because of plugging in both the slurry and the hydrogen flow metering systems. Three baseline runs and three slurry runs of the high heat flux program were completed before the plant was shut down March 12 for repair of the Inert Gas Unit. Attempts to complete a fourth slurry run at high heat flux were unsuccessful because of problems with the coal feed handling and the vortex mix systems. Process Development Unit (P-99) completed three of the four runs designed to study the effect of dissolver L/D ratio. The fourth was under way at the end of the period. SRC yield correlations have been developed that include coal properties as independent variables. A preliminary ranking of coals according to their reactivity in PDU P-99 has been made. Techniques for studying coking phenomenona are now in place.

  12. Public safety and sour gas quarterly progress report October - December 2002

    Energy Technology Data Exchange (ETDEWEB)

    Sikora, V.; Lillo, H.; Craig, M.; Neilson, G.

    2003-01-01

    This third quarterly progress report for the business year 2002-2003 on the Alberta Energy and Utilities Board (EUB) Public Safety and Sour Gas initiative covers projects based on the 87 recommendations made by the Provincial Advisory Committee on Public Safety and Sour Gas (Advisory Committee) in December 2000. As of December 2002, work has been completed on 16 recommendations and is proceeding on 50 recommendations. This report includes several tables indicating the status of recommendations as either complete or ongoing. The recommendation categories include: (1) sour gas development, planning and approval, (2) sour gas operations, (3) emergency preparedness, and (4) information, communication and consultation. The report also summarizes the health effects and sour gas research. Recommendations completed as of December 2002 include: plant proliferation; pre-license review of critical well license applications; license application training/certification information requirement; increase sour gas inspections; increase inspections of new and noncompliant operators; implement 100 per cent inspection rate for critical wells near people; response to sour gas complaints; enhance EUB capability to monitor for complaint response/compliance; complaint/incident response program for Aboriginal communities; interim policy on ERP review and reduced EPZs; infrastructure and resources for Aboriginal community ERP; field staff in industry-landowner discussions; EUB involvement in mediation of application issues; and, timely and meaningful public consultation for First Nations and Metis. Alberta Health and Wellness is currently evaluating the health effects of H{sub 2}S and SO{sub 2} and the work is near completion. Other ongoing work includes the development of a draft protocol to address the involvement of regional health authorities (RHAs), the early involvement of RHAs and other local government bodies, and a process for communication between the EUB field staff and

  13. Fusion-driven actinide burner design study. Second quarterly progress report

    International Nuclear Information System (INIS)

    Chi, J.W.H.; Gold, R.E.; Holman, R.R.

    1975-11-01

    The Second Quarterly Progress Report summarizes the status at the mid-point of the conceptual design effort. The fusion driver continues to pose some of the principal design problems due to the necessity of advancing plasma engineering and technology for long pulse, high duty cycle operation. The development of credible design solutions to these problems is one of the major objectives of the study. The TF and OH coil designs have been modified to provide a more compact arrangement in the nose region of the TF coils and to ensure fully cryostable operation. A unique concept has been developed to effectively shield the TF coils from the poloidal fields. A vacuum vessel concept which separates the functions for sustaining the differential pressure load and for sealing the vacuum system is described. The thickness of the blanket has been decreased to reduce the power density and the actinide inventory. Determination and presentation of actinide depletion characteristics represents a major element thus far in the study and is a principal objective. Evaluation of the changes in the hazard only during irradiation proved to be an inadequate measure of the reduction in long term hazards due to the importance of radioactive daughter products which appear much later in time. Therefore, comparisons have been made of long term decay characteristics before and after irradiation in the actinide burner. It has also been noted that some of the actinides that are produced during irradiation have beneficial applications as radioisotopic power sources. These and other considerations suggest that alternate approaches to assessing the waste management problem be considered to develop a meaningful perspective on long term hazards from the actinides

  14. Fusion-driven actinide burner design study. Second quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Chi, J.W.H.; Gold, R.E.; Holman, R.R.

    1975-11-01

    The Second Quarterly Progress Report summarizes the status at the mid-point of the conceptual design effort. The fusion driver continues to pose some of the principal design problems due to the necessity of advancing plasma engineering and technology for long pulse, high duty cycle operation. The development of credible design solutions to these problems is one of the major objectives of the study. The TF and OH coil designs have been modified to provide a more compact arrangement in the nose region of the TF coils and to ensure fully cryostable operation. A unique concept has been developed to effectively shield the TF coils from the poloidal fields. A vacuum vessel concept which separates the functions for sustaining the differential pressure load and for sealing the vacuum system is described. The thickness of the blanket has been decreased to reduce the power density and the actinide inventory. Determination and presentation of actinide depletion characteristics represents a major element thus far in the study and is a principal objective. Evaluation of the changes in the hazard only during irradiation proved to be an inadequate measure of the reduction in long term hazards due to the importance of radioactive daughter products which appear much later in time. Therefore, comparisons have been made of long term decay characteristics before and after irradiation in the actinide burner. It has also been noted that some of the actinides that are produced during irradiation have beneficial applications as radioisotopic power sources. These and other considerations suggest that alternate approaches to assessing the waste management problem be considered to develop a meaningful perspective on long term hazards from the actinides.

  15. ABWR certification work brings US licensing stability nearer

    International Nuclear Information System (INIS)

    Wilkins, D.R.; Quirk, J.F.

    1991-01-01

    The Advanced Boiling Water Reactor (ABWR) is now approaching Final Design Approval by the US Nuclear Regulatory Commission (NRC) and will then proceed on to the certification phase of the NRC's new standard plant licensing process. Successful completion of this will usher in a new era of standardization and reactor licensing stability in the US. (author)

  16. AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    1982-04-01

    The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1982-1986 in which projects are organized according to fossil energy technologies. This report is divided into parts and chapters with each part describing projects related to a particular fossil energy technology. Chapters within a part provide details of the various projects associated with that technology. We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program. Plans for the program will be issued annually. A draft of the program plan for FY 1982 to 1986 has been prepared and is in the review process. The implementation of these plans will be reflected by these quarterly progress reports, and this dissemination of information will bw augmented by topical or final reports as appropriate.

  17. I-NERI QUARTERLY TECHNICAL PROGRESS REPORT - JANUARY 1 - MARCH 31, 2005

    International Nuclear Information System (INIS)

    Chang Oh

    2005-01-01

    codes. The three categories of experiments were performed in the facility; (1) upper pool cooling trip test, (2) LOFC experiment, (3) emissivity measurement experiment. (C) Prof. NO continued Task 3. (Prof NO) The experimental work of air ingress is going on without any concern: Geometry and size effect test has been completed. The conversion factor for internal surface area was obtained through this experiment. Burn-off test was performed and the uniformity of internal reaction was confirmed. (D) INEEL engineers continued to extend the diffusion model for multiple chemical species and made some calculations. (E) Prof. Lee and Martin at University of Michigan continued to analyze the effect of the stochastic fuel on the neutronic analysis and have initiated fuel depletion calculations for the VHTGR core. Progress during the past quarter includes: Further analysis of stochastic fuel geometry; Preliminary Monte Carlo depletion of full-core VHTGR; and Installation of MCNP5 on Unix cluster

  18. Isotopic power materials development. Quarterly progress report for period ending March 31, 1976

    International Nuclear Information System (INIS)

    Schaffhauser, A.C.

    1976-06-01

    The second in a series of quarterly reports for Technology and Space Applications materials programs conducted by the Metals and Ceramics Division of Oak Ridge National Laboratory for the Nuclear Research and Applications Division of ERDA is presented. These quarterly reports replace the monthly and annual reports previously issued on this work. The areas of research covered include high-temperature alloys for space isotopic heat sources, physical and mechanical metallurgy of heat source containment materials, isotope Brayton system materials support, and space nuclear flight systems hardware

  19. Pulverized coal firing of aluminum melting furnaces. Quarterly technical progress report, October 1-December 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    West, C E

    1980-10-01

    Heaviest acitivity this quarter has been in the area of system design and specification and purchase of system components. Mechanical design is now complete. The design of electrical power, process control and data acquisition systems has begun. Combustor design meetings with General Electric Space Science Labs have resulted in an increasing awareness that analytical flow field modeling of the cyclonic combustor could not only enhance current understanding of the process but also broaden the future scope of implementation. A proposal to add specific additional modeling tasks was presented to the Department of Energy, and is included herein in Appendix B. Equipment procurement will continue and system construction will begin during the next quarter.

  20. Amarillo National Resource Center for Plutonium quarterly technical progress report, August 1, 1997--October 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This report summarizes activities of the Amarillo National Resource Center for Plutonium during the quarter. The report describes the Electronic Resource Library; DOE support activities; current and future environmental health and safety programs; pollution prevention and pollution avoidance; communication, education, training, and community involvement programs; and nuclear and other material studies, including plutonium storage and disposition studies.

  1. Enforcement actions: significant actions resolved. Quarterly progress report, October-December 1985. Volume 4, No. 4

    International Nuclear Information System (INIS)

    1986-02-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (October - December 1985) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory commission to licensees with respects to these enforcement actions, and the licensees' responses

  2. Evaluation of damages of airplane crash in European Advanced Boiling Water Reactor (EU-ABWR)

    International Nuclear Information System (INIS)

    Kamei, Kazuhiro; Tanoue, Tetsuharu; Kataoka, Kazuyoshi; Jimbo, Masakazu

    2011-01-01

    European Advanced Boiling Water Reactor (EU-ABWR) is developed by Toshiba. EU-ABWR accommodates an armored reactor building against Airplane Crash (APC), severe accident mitigation systems, N+2 principle in safety systems and a large output of 1600 MWe. Thanks to above mentioned features, EU-ABWR's design objectives and principles are consistent with safety requirements in an European market. In this paper, evaluation of damages induced by APC has been summarized. (author)

  3. Development of ABWR-2 and its safety design

    International Nuclear Information System (INIS)

    Takafumi, Anegawa; Kenji, Tateiwa

    2002-01-01

    This paper reports the current status of development project on ABWR-II, a next generation reactor design based on ABWR, and its safety design. This project was initiated over a decade ago and has completed three phases to date. In Phase I (1991-92), basic design requirements were discussed and several plant concepts were studied. In Phase II (1993-95), key design features were selected in order to establish a reference reactor concept. In Phase III (1996-2000), based on the reference reactor concept, modifications and improvements were made to fulfill the design requirements. By adopting large electric output (1 700 MW), large fuel bundle, modified ECCS, and passive heat removal systems, among other design features, we achieved a design concept capable of increasing both economic competitiveness and safety performance. Main focus of this paper will be on the safety design, safety performance, and further research needs related to safety. (authors)

  4. GE-Hitachi ABWR Design for 60 Years of Operation

    International Nuclear Information System (INIS)

    Hoang Xuan Hoa

    2011-01-01

    The GE Hitachi ABWR design benefits from the experiences of the prior generation BWRs in operation since the 1970s, and the knowledge learned from years of technical research on the aging effects on reactor systems, structures and components. The impact of exposure to neutrons over time to the reactor pressure vessel and internal components was evaluated to confirm their structural integrity. Other time-based plant analyses, such as fatigue vibration and corrosion effect, have also been performed on the ABWR to support a 60-year plant life assumption. Finally, operating experience and aging lessons learned have been used to verify the maintenance plans for plant aging management are acceptable to support operation up to 60 years. (author)

  5. Computational mechanics research and support for aerodynamics and hydraulics at TFHRC. Quarterly report January through March 2011. Year 1 Quarter 2 progress report.

    Energy Technology Data Exchange (ETDEWEB)

    Lottes, S. A.; Kulak, R. F.; Bojanowski, C. (Energy Systems)

    2011-05-19

    This project was established with a new interagency agreement between the Department of Energy and the Department of Transportation to provide collaborative research, development, and benchmarking of advanced three-dimensional computational mechanics analysis methods to the aerodynamics and hydraulics laboratories at the Turner-Fairbank Highway Research Center for a period of five years, beginning in October 2010. The analysis methods employ well-benchmarked and supported commercial computational mechanics software. Computational mechanics encompasses the areas of Computational Fluid Dynamics (CFD), Computational Wind Engineering (CWE), Computational Structural Mechanics (CSM), and Computational Multiphysics Mechanics (CMM) applied in Fluid-Structure Interaction (FSI) problems. The major areas of focus of the project are wind and water loads on bridges - superstructure, deck, cables, and substructure (including soil), primarily during storms and flood events - and the risks that these loads pose to structural failure. For flood events at bridges, another major focus of the work is assessment of the risk to bridges caused by scour of stream and riverbed material away from the foundations of a bridge. Other areas of current research include modeling of flow through culverts to assess them for fish passage, modeling of the salt spray transport into bridge girders to address suitability of using weathering steel in bridges, vehicle stability under high wind loading, and the use of electromagnetic shock absorbers to improve vehicle stability under high wind conditions. This quarterly report documents technical progress on the project tasks for the period of January through March 2011.

  6. Geothermal direct-heat utilization assistance. Quarterly project progress report, July 1996--September 1996. Federal Assistance Program

    Energy Technology Data Exchange (ETDEWEB)

    Lienau, P.

    1996-11-01

    This report summarizes geothermal technical assistance, R&D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the fourth quarter of FY-96. It describes 152 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include geothermal heat pumps, space heating, greenhouses, aquaculture, equipment, economics and resources. Research activities are summarized on greenhouse peaking. Outreach activities include the publication of a geothermal direct use Bulletin, dissemination of information, geothermal library, technical papers and seminars, and progress monitor reports on geothermal resources and utilization.

  7. U.S. licensing process and ABWR certification

    International Nuclear Information System (INIS)

    Quirk, J.F.; Williams, W.A.

    1996-01-01

    Part 50 of Title 10 of the Code of Federal Regulation (CFR) establishes a two-step licensing process by which the U.S. Nuclear Regulatory Committee (NRC) authorizes nuclear reactor plant construction through issuance of a construction permit and authorizes operation by issuance of an operating license. At each stage, the NRC Staff conducts technical reviews and there is potential for public hearings. In 1989, the NRC issued a new, simplified licensing process: Part 52. The purpose of the Part 52 licensing process is to provide a regulatory framework that brings about earlier resolution of licensing issues. Because issues are not resolved early in the Part 50 licensing process, approval of an operating license is not assured until after a significant investment has been made in the plant. Part 52 increases the stability and certainty of the licensing process by providing for the early resolution of safety and environmental issues. The Part 52 licensing process features (1) early site permits, (2) design certification, and (3) combined construction permit and operating licenses. As part of the U.S. Advanced Light Water Reactor (ALWR) Program to revitalize the nuclear option through the integration of government/utility/industry efforts, GE undertook the role of applying for certification for its latest product line, the Advanced Boiling Water Reactor (ABWR), under the U.S. ABWR certification program. The ABWR design is an essentially complete plant. Initial application for design certification was in 1987 under Part 50. GE reapplied in late 1991 under the newly promulgated Part 52. Following seven years of intensive interactions with the NRC and ACRS, GE was awarded the first Final Design Approval (FDA) under Part 52. The Commission initiated rulemaking by publishing the proposed ABWR Certification Rule in the Federal Register in early 1995. Certification is anticipated mid-1996. (J.P.N.)

  8. Probabilistic based design rules for intersystem LOCAS in ABWR piping

    International Nuclear Information System (INIS)

    Ware, A.G.; Wesley, D.A.

    1993-01-01

    A methodology has been developed for probability-based standards for low-pressure piping systems that are attached to the reactor coolant loops of advanced light water reactors (ALWRs) which could experience reactor coolant loop temperatures and pressures because of multiple isolation valve failures. This accident condition is called an intersystem loss-of-coolant accident (ISLOCA). The methodology was applied to various sizes of carbon and stainless steel piping designed to advanced boiling water reactor (ABWR) temperatures and pressures

  9. Experimental study on RCCV of ABWR plant-Part 1

    International Nuclear Information System (INIS)

    Saita, H.; Kikuchi, R.; Muramatsu, Y.; Hiramoto, M.; Oyamada, O.; Furukawa, H.; Sasagawa, K.; Ohmori, N.; Suzuki, S.; Suoita, M.; Kobayashi, I.; Yamaguchi, I.

    1989-01-01

    Steel containment vessels have generally been used for BWR (Boiling Water Reactor)-type nuclear power plants in Japan. However, in accordance with the development of the advanced-type BWR (ABWR), the introduction of a reinforced concrete containment vessel (RCCV) has been proposed because it enables greater freedom in flexibility of configuration. The study presented here accumulates basic data on RCCV's and verifies the integrity and ultimate strength of a trial-designed RCCV and the validity of its design method

  10. Enforcement actions: Significant actions resolved; Quarterly progress report, October--December 1993: Volume 12, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (October - December 1993) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  11. Geothermal direct-heat utilization assistance. Quarterly progress report, April--June 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    Progress is reported on the following R&D activities: evaluation of lineshaft turbine pump problems, geothermal district heating marketing strategy, and greenhouse peaking analysis. Other activities are reported on technical assistance, technology transfer, and the geothermal progress monitor.

  12. Advanced research and technology development fossil energy materials program. Quarterly progress report for the period ending September 30, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Bradley, R.A. (comp.)

    1981-12-01

    This is the fourth combined quarterly progress report for those projects that are part of the Advanced Research and Technology Development Fossil Energy Materials Program. The objective is to conduct a program of research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. Work performed on the program generally falls into the Applied Research and Exploratory Development categories as defined in the DOE Technology Base Review, although basic research and engineering development are also conducted. A substantial portion of the work on the AR and TD Fossil Energy Materials Program is performed by participating cntractor organizations. All subcontractor work is monitored by Program staff members at ORNL and Argonne National Laboratory. This report is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1981 in which projects are organized according to fossil energy technologies. We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program.

  13. NST Quarterly

    International Nuclear Information System (INIS)

    1995-01-01

    NST Quarterly reports current development in nuclear science and technology in Malaysia. It keeps readers informed on the progress of research, services, application of nuclear science and technology, and other technical news. It highlights MINT activities and also announces coming events

  14. NST Quarterly

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

    NST Quarterly reports current development in nuclear science and technology in Malaysia. It keeps readers informed on the progress of research, services, application of nuclear science and technology, and other technical news. It highlights MINT activities and also announces coming events.

  15. Enforcement actions: Significant actions resolved: Quarterly progress report, October--December 1988

    International Nuclear Information System (INIS)

    1989-02-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (October--December 1988) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  16. Physical protection of nuclear facilities. Quarterly progress report, July--September 1978. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, L.D. (ed.)

    1979-01-01

    Major activities during the fourth quarter of FY78 included (1) the vital area analysis of operational reactors and characterization of the Standardized Nuclear Unit Power Plant System (SNUPPS), (2) the algorithm development of a new pathfinding computer code, (3) the completion of contractor-supported work for the component generic data base, (4) the refinement of tests related to human parameters modeling, and (5) the addition of improvements to and demonstration of the Safeguards Automated Facility Evaluation (SAFE), Safeguards Network Analysis Procedure (SNAP), and Fixed-Site Neutralization Model (FSNM) methodologies.

  17. Enforcement actions: Significant actions resolved: Quarterly progress report, April-June 1987

    International Nuclear Information System (INIS)

    1987-08-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April-June 1987) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  18. Enforcement actions: significant actions resolved. Quarterly progress report, January-March 1986. Volume 5, No. 1

    International Nuclear Information System (INIS)

    1986-05-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (January-March 1986) and includes copies of letters, notices, and orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions, and the licensees' responses. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, in the interest of promoting public health and safety as well as common defense and security

  19. Enforcement actions: Significant actions resolved industrial licensees. Quarterly progress report, April 1994--June 1994

    International Nuclear Information System (INIS)

    1994-08-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April - June 1994) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to industrial licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  20. Magnetically controlled deposition of metals using gas plasma. Quarterly progress report, July 1994--September 1994

    International Nuclear Information System (INIS)

    1995-01-01

    This document reports the status of grant DE-FE07-93ID13220 for the July-September, 1994 quarter. The objective of this grant is to develop a method of spraying materials on a substrate in a controlled manner to eliminate the waste inherent in the present process. Thin layers of secondary material are plated on substrates either by plating or spraying processes. Plating operations produce large amounts of hazardous liquid waste. Spraying, while one of the less waste intensive methods, produces 'over spray' which is waste that is a result of the uncontrolled nature of the spray stream. In many cases the over spray produces a hazardous waste

  1. Enforcement actions: Significant actions resolved: Quarterly progress report, July--September 1988

    International Nuclear Information System (INIS)

    1988-12-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July--September 1988) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  2. Enforcement actions: significant actions resolved. Quarterly progress report, April-June 1986. Volume 5, No. 2

    International Nuclear Information System (INIS)

    1986-08-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April-June 1986) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions and the licensees' responses. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, in the interest of promoting public health and safety as well as common defense and security

  3. Enforcement actions: significant actions resolved. Quarterly progress report, July-September 1985. Volume 4, No. 3

    International Nuclear Information System (INIS)

    1985-11-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July-September 1985) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions, and the licensees' responses. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, in the interest of promoting public health and safety as well as common defense and security

  4. Enforcement actions: significant actions resolved. Quarterly progress report, July-September 1984. Volume 3, No. 3

    International Nuclear Information System (INIS)

    1984-10-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July-September 1984 and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions and the licensees' responses. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, in the interest of promoting public health and safety as well as common defense and security

  5. Enforcement actions: Significant actions resolved material licensees. Quarterly progress report, April 1995--June 1995

    International Nuclear Information System (INIS)

    1995-08-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April-June 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to material licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  6. Enforcement actions: Significant actions resolved: Quarterly progress report, April--June 1988

    International Nuclear Information System (INIS)

    1988-08-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April--June 1988) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  7. Enforcement actions: Significant actions resolved: Quarterly progress report, July-September 1987

    International Nuclear Information System (INIS)

    1987-12-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July-September 1987) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  8. Enforcement actions: significant actions resolved. Quarterly progress report, July-September 1983. Volume 2, No.3

    International Nuclear Information System (INIS)

    1983-11-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July-September 1983) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions ad licensees' responses. This and future issues will include cases involving Severity Level III violations for which no civil penalty was assessed. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, in the interest of promoting public health and safety as well as common defense and security

  9. Enforcement actions: Significant actions resolved. Quarterly progress report, April--June 1993: Volume 12, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April--June 1993) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  10. Enforcement actions: Significant actions resolved: Quarterly progress report, January-March 1988

    International Nuclear Information System (INIS)

    1988-06-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (January-March 1988) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  11. Catalytic conversion of light alkanes. Quarterly progress report, April 1--June 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Lyons, J.E.

    1992-06-30

    The second Quarterly Report of 1992 on the Catalytic Conversion of Light Alkanes reviews the work done between April 1, 1992 and June 31, 1992 on the Cooperative Agreement. The mission of this work is to devise a new catalyst which can be used in a simple economic process to convert the light alkanes in natural gas to oxygenate products that can either be used as clean-burning, high octane liquid fuels, as fuel components or as precursors to liquid hydrocarbon uwspomdon fuel. During the past quarter we have continued to design, prepare, characterize and test novel catalysts for the mild selective reaction of light hydrocarbons with air or oxygen to produce alcohols directly. These catalysts are designed to form active metal oxo (MO) species and to be uniquely active for the homolytic cleavage of the carbon-hydrogen bonds in light alkanes producing intermediates which can form alcohols. We continue to investigate three molecular environments for the active catalytic species that we are trying to generate: electron-deficient macrocycles (PHASE I), polyoxometallates (PHASE II), and regular oxidic lattices including zeolites and related structures as well as other molecular surface structures having metal oxo groups (PHASE I).

  12. ABWR-II Core Design with Spectral Shift Rods for Operation with All Control Rods Withdrawn

    International Nuclear Information System (INIS)

    Moriwaki, Masanao; Aoyama, Motoo; Anegawa, Takafumi; Okada, Hiroyuki; Sakurada, Koichi; Tanabe, Akira

    2004-01-01

    An innovative reactor core concept applying spectral shift rods (SSRs) is proposed to improve the plant economy and the operability of the 1700-MW(electric) Advanced Boiling Water Reactor II (ABWR-II). The SSR is a new type of water rod in which a water level is naturally developed during operation and changed according to the coolant flow rate through the channel. By taking advantage of the large size of the ABWR-II bundle, the enhanced spectral shift operation by eight SSRs allows operation of the ABWR-II with all control rods withdrawn. In addition, the uranium-saving factor of 6 to 7% relative to the reference ABWR-II core with conventional water rods can be expected due to the greater effect of spectral shift. The combination of these advantages means the ABWR-II with SSRs should be an attractive alternative for the next-generation nuclear reactor

  13. Orcas Power and Light Company [fourth quarterly] technical progress report, July--September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    After a year of operating the G-Van, OPALCO concluded that the company transportation needs were not being met by the G-Van. The previous quarterly report mentioned battery problems with the Solectria (No. 51). This problem is one of reduced range and power and has been determined to be caused by one or more individual monoblock failures. The local Solectria representative and Solectria headquarters personnel have been aware of this unsatisfactory condition and are continuing their attempt to solve it. The Solectria and G-Van continue to be used intermittently by company personnel for errands and engineering trips. Generally, the smaller, compact size of the Solectria make it the most preferred by company drivers. Clearly the G-Van is not selected for use because of its size and weight. It is important to note that the driver dissatisfaction is not related to the fact that it is an electric van, but more its lack of maneuverability.

  14. Orcas Power and Light Company [fourth quarterly] technical progress report, July--September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    After a year of operating the G-Van, OPALCO concluded that the company transportation needs were not being met by the G-Van. The previous quarterly report mentioned battery problems with the Solectria (No. 51). This problem is one of reduced range and power and has been determined to be caused by one or more individual monoblock failures. The local Solectria representative and Solectria headquarters personnel have been aware of this unsatisfactory condition and are continuing their attempt to solve it. The Solectria and G-Van continue to be used intermittently by company personnel for errands and engineering trips. Generally, the smaller, compact size of the Solectria make it the most preferred by company drivers. Clearly the G-Van is not selected for use because of its size and weight. It is important to note that the driver dissatisfaction is not related to the fact that it is an electric van, but more its lack of maneuverability.

  15. Energy conservation via heat transfer enhancement. Quarterly progress report, January 1-March 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Bergles, A.E.; Junkhan, G.H.; Webb, R.L.

    1979-06-01

    This report for the first quarter of 1979 summarizes visits and contacts relative to the theory and practice of heat transfer enhancement. The Technical Literature File and Manufacturers' File were expanded, and the initial Patent Technology Information File was completed. Application studies on enhancement of waste heat recuperators and laminar internal flow heat transfer are described. A comprehensive bibliography on laminar flow enhancement is included. The Technology study on performance of internally finned tubes is complete. New data for the heat transfer and friction characteristics of internally finned tubes will be analyzed to develop rationally based correlations. An assessment of natural convection from rough surfaces was performed. Major effort was directed toward planning of the Research Workshop on Energy Conservation Through Enhanced Heat Transfer. The Workshop, scheduled for May 24 and May 25, 1979 in Chicago, will be co-sponsored by NSF.

  16. Thorium utilization program. Quarterly progress report for the period ending May 31, 1977

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-01

    Results of work performed under the National HTGR Fuel Recycle Program (also known as the Thorium Utilization Program) at General Atomic Company are presented. Results of work on this program prior to June 1974 were included in a quarterly series on the HTGR Base Program. The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle.

  17. Thorium utilization program. Quarterly progress report for the period ending November 30, 1975

    International Nuclear Information System (INIS)

    1975-01-01

    The development program for HTGR fuel reprocessing continues to emphasize the design and construction of a prototype head-end line. Design work on the multistage crushing system, the primary and secondary fluidized bed burners, the pneumatic transfer systems, and the ancillary fixtures for semiremote assembly and disassembly is essentially complete. Fabrication and receipt of all major components is under way, and auxiliary instrumentation and support systems are being installed. Studies of flow characteristics of granular solids in pneumatic transfer systems are continuing and data are being collected for use in design of systems for solids handling. Experimental work on the 20-cm primary fluidized bed burner verified the fines recycle operating mode in runs of greater than 24 hr. Twelve leaching runs were performed during the quarter using crushed, burned-back TRISO coated ThC 2 particles and burned-back BISO coated sol gel ThO 2 particles to examine the effect of varying the Thorex-to-thoria ratio to give product solutions ranging from 0.25M to 1M in thorium. Only minor effects were observed and reference values for facility operations were specified. Two-stage leaching runs with burned-back ThC 2 indicate there are no measurable differences in total dissolution time as compared to single-stage leaching. Bench-scale tests on oxidation of HTGR fuel boron carbide at 900 0 C indicates that most if not all of the carbide will be converted to boron oxide in the fluidized bed burner. Eight solvent extraction runs were completed during the quarter. These runs represented the first cycle and second uranium cycle of the acid-Thorex flowsheet. A detailed calculation of spent fuel compositions by fuel block and particle type is being performed for better definition of process streams in a fuel reprocessing facility

  18. Geothermal direct-heat utilization assistance. Federal Assistance Program quarterly project progress report, April 1--June 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This report summarizes geothermal technical assistance, R and D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the third quarter of FY98 (April--June, 1998). It describes 231 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with included requests for general information including material for high school and university students, and material on geothermal heat pumps, resource and well data, spacing heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, snow melting and electric power. Research activities include work on model construction specifications for line shaft submersible pumps and plate heat exchangers, and a comprehensive aquaculture developers package. A brochure on Geothermal Energy in Klamath County was developed for state and local tourism use. Outreach activities include the publication of the Quarterly Bulletin (Vol. 19, No. 2) with articles on research at the Geo-Heat Center, sustainability of geothermal resources, injection well drilling in Boise, ID and a greenhouse project in the Azores. Other outreach activities include dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisitions and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

  19. LWR pressure vessel irradiation surveillance dosimetry. Quarterly progress report, July--September 1978

    Energy Technology Data Exchange (ETDEWEB)

    Guthrie, G L; McElroy, W N; Lippincott, E P; Gold, R

    1978-12-01

    Program objectives and progress to date by the national laboratories in LWR pressure vessel irradiation surveillance dosimetry are summarized. Participants in the program include: Rockwell International, Hanford Engineering Development Laboratory, National Bureau of Standards, and Oak Ridge National Laboratory.

  20. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1, 1997--July 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    Progress summaries are provided from the Amarillo National Center for Plutonium. Programs include the plutonium information resource center, environment, public health, and safety, education and training, nuclear and other material studies.

  1. Progress Report of the Materials Department. First Quarter 1971. RCN Report

    International Nuclear Information System (INIS)

    Sens, P.F.

    1971-06-01

    A description of the progress in the various projects concerning the materials development of water cooled reactors, sodium cooled fast reactors and gas cooled reactors. Similar reports have been issued regularly with an internal distribution only. (author)

  2. ERIP invention 637. Technical progress report 2nd quarter, April 1997--June 1997

    Energy Technology Data Exchange (ETDEWEB)

    Thacker, G.W.

    1997-07-22

    This technical report describes progress in the development of the Pegasus plow, a stalk and root embedding apparatus. Prototype testing is reported, and includes the addition of precision tillage. Disease data, organic matter, and nitrogen levels results are very briefly described. Progress in marketing is also reported. Current marketing issues include test use by cotton and wheat growers, establishment of dealer relationships, incorporation of design modifications, expansion of marketing activities, and expansion of loan and lease program.

  3. Geothermal direct-heat utilization assistance. Quarterly project progress report, April--June 1993

    Energy Technology Data Exchange (ETDEWEB)

    Lienau, P.

    1993-06-01

    Technical assistance was provided to 60 requests from 19 states. R&D progress is reported on: evaluation of lineshaft turbine pump problems, geothermal district heating marketing strategy, and greenhouse peaking analysis. Two presentations and one tour were conducted, and three technical papers were prepared. The Geothermal Progress Monitor reported: USGS Forum on Mineral Resources, Renewable Energy Tax Credits Not Working as Congress Intended, Geothermal Industry Tells House Panel, Newberry Pilot Project, and Low-Temperature Geothermal Resources in Nevada.

  4. Geothermal direct-heat utilization assistance: Federal assistance program. Quarterly project progress report, October--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    The report summarizes geothermal technical assistance, R&D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the first quarter of FY-96. It describes 90 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include geothermal heat pumps, space heating, greenhouses, aquaculture, equipment and resources. Research activities are summarized on low-temperature resource assessment, geothermal district heating system cost evaluation and silica waste utilization project. Outreach activities include the publication of a geothermal direct use Bulletin, dissemination of information, geothermal library, technical papers and seminars, development of a webpage, and progress monitor reports on geothermal resources and utilization.

  5. Upgraded prototype-reactor internal pump for ABWR

    International Nuclear Information System (INIS)

    Kumagai, Mikio; Amemori, Shiro; Saito, Takehiko

    1988-01-01

    In 1983, Toshiba, using their own technology, manufactured a commercial grade reactor internal pump (RIP). Recently, however, a licensing agreement with KSB of West Germany covering the RIP technology, has combined the know-how of KSB with Toshiba's technology to produce a truly high-quality prototype RIP. The pump produces the required coreflow for ABWR at low speed and with high efficiency, and simply by increasing the pump speed to the prior level, the coreflow can be further increased for such advantages as improved fuel cycle economy. Here, the advanced features and test results of the RIP are summarized. (author)

  6. Automated Array Assembly, Phase 2. Quarterly technical progress report, April-June 1979

    Energy Technology Data Exchange (ETDEWEB)

    Carbajal, B.G.

    1979-07-01

    The Automated Array Assembly Task, Phase 2 of the Low Cost Solar Array (LSA) Project is a process development task. This contract provides for the fabrication of modules from large area Tandem Junction Cells (TJC). The key activities in this contract effort are (a) Large Area TJC including cell design, process verification and cell fabrication and (b) Tandem Junction Module (TJM) including definition of the cell-module interfaces, substrate fabrication, interconnect fabrication and module assembly. The overall goal is to advance solar cell module process technology to meet the 1986 goal of a production capability of 500 megawatts per year at a cost of less than $500 per peak kilowatt. This contract will focus on the Tandem Junction Module process. During this quarter, effort was focused on design and process verification. The large area TJC design was completed and the design verification was completed. Process variation experiments led to refinements in the baseline TJC process. Formed steel substrates were porcelainized. Cell array assembly techniques using infrared soldering are being checked out. Dummy cell arrays up to 5 cell by 5 cell have been assembled using all backside contacts.

  7. Physical protection of nuclear materials in transit. Quarterly progress report, April--June 1978

    International Nuclear Information System (INIS)

    Chapman, L.D.

    1978-12-01

    A computer model, SOURCE, has been developed to study the impact of convoy configuration and tactics upon personnel survival and emergency signal generation during an initial armed attack. During this quarter, several improvements were made to the SOURCE code. These improvements include (1) the capability to model an ambush in which the adversaries set up a roadblock, (2) upgraded data on aiming accuracies and human vulnerabilities, and (3) two output formats for examining the locations of the surviving guards. To support the conflict analysis task, several complementary conflict modeling efforts are undergoing parallel development. These methodologies include the SABRES computerized conflict simulation models, the AMBUSH conflict board game, and an alternative methodology being developed by Vector Research, Inc. (VRI). The SABRES I combat model can be used to study the relative value of alternative defender tactics and the relative value of different weapon systems. AMBUSH is a tactical board game which provides a hypothetical conflict between a truck convoy and an adversary group attempting a hijacking. ORINCON Corporation developed network models to be used in determining the cost implications of alternative transportation regulations. SRI International provided weapon characterization data from representative types and calibers of sporting rifles, assault rifles, machine guns, submachine guns, shotguns, and handguns. The alternative methodology for conflict modeling being developed by VRI is the engagement model, CONVOY. SAI is under contract to model the communication system for transporters of SNM

  8. LLNL Underground-Coal-Gasification Project. Quarterly progress report, July-September 1981

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, D.R.; Clements, W. (eds.)

    1981-11-09

    We have continued our laboratory studies of forward gasification in small blocks of coal mounted in 55-gal drums. A steam/oxygen mixture is fed into a small hole drilled longitudinally through the center of the block, the coal is ignited near the inlet and burns toward the outlet, and the product gases come off at the outlet. Various diagnostic measurements are made during the course of the burn, and afterward the coal block is split open so that the cavity can be examined. Development work continues on our mathematical model for the small coal block experiments. Preparations for the large block experiments at a coal outcrop in the Tono Basin of Washington State have required steadily increasing effort with the approach of the scheduled starting time for the experiments (Fall 1981). Also in preparation is the deep gasification experiment, Tono 1, planned for another site in the Tono Basin after the large block experiments have been completed. Wrap-up work continues on our previous gasification experiments in Wyoming. Results of the postburn core-drilling program Hoe Creek 3 are presented here. Since 1976 the Soviets have been granted four US patents on various aspects of the underground coal gasification process. These patents are described here, and techniques of special interest are noted. Finally, we include ten abstracts of pertinent LLNL reports and papers completed during the quarter.

  9. Alloy development for irradiation performance. Quarterly progress report for period ending December 31, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1981-04-01

    Progress is reported in eight sections: analysis and evaluation studies, test matrices and test methods development, Path A Alloy Development (austenitic stainless steels), Path C Alloy Development (Ti and V alloys), Path D Alloy Development (Fe alloys), Path E Alloy Development (ferritic steels), irradiation experiments and materials inventory, and materials compatibility and hydrogen permeation studies. (DLC)

  10. Light-water-reactor safety research program. Quarterly progress report, July--September 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Progress is summarized in the following research and development areas: (1) loss-of-coolant accident research; heat transfer and fluid dynamics; (2) transient fuel response and fission-product release; and (3) mechanical properties of Zircaloy containing oxygen. Also included is an appendix on Kinetics of Fission Gas and Volatile Fission-product Behavior under Transient Conditions in LWR Fuel

  11. LMFBR aerosol release and transport program. Quarterly progress report, July--September 1975

    International Nuclear Information System (INIS)

    Fontana, M.H.; Kress, T.S.; Adams, R.E.; Parsly, L.F.; Parker, G.W.

    1976-04-01

    Progress is summarized in the areas of capacitor discharge vaporizer (CDV) development, small-vessel fuel and fuel-simulant aerosol studies, large-vessel aerosol studies, HCDA bubble simulant tests, fuel-simulant response to CDV electrical energy deposition, bubble shape and rise behavior, and structural integrity of equipment cell liners

  12. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1--July 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    Progress is reported on research projects related to the following: Electronic resource library; Environment, safety, and health; Communication, education, training, and community involvement; Nuclear and other materials; and Reporting, evaluation, monitoring, and administration. Technical studies investigate remedial action of high explosives-contaminated lands, radioactive waste management, nondestructive assay methods, and plutonium processing, handling, and storage.

  13. Alloy development for irradiation performance. Quarterly progress report for period ending December 31, 1980

    International Nuclear Information System (INIS)

    1981-04-01

    Progress is reported in eight sections: analysis and evaluation studies, test matrices and test methods development, Path A Alloy Development (austenitic stainless steels), Path C Alloy Development (Ti and V alloys), Path D Alloy Development (Fe alloys), Path E Alloy Development (ferritic steels), irradiation experiments and materials inventory, and materials compatibility and hydrogen permeation studies

  14. Quarterly technical progress report for the period ending June 30, 1984

    Energy Technology Data Exchange (ETDEWEB)

    1984-10-01

    The Magnetohydrodynamics Program (Component Development and Integration Facility) in Butte, Montana, continued its site preparation for the TRW first-stage combustor installation. In the area of flue gas cleanup, our in-house research program is continuing its investigation into the causes of sorbent attrition in PETC's fluidized-bed copper oxide process for simultaneous SO/sub 2//NO/sub x/ removal. Interwoven with these tests is a series of spray dryer/electrostatic precipitator tests that are being conducted with the cooperation of Wheelabrator-Frye, Inc. This test series was completed this quarter, and the data show that when using a Kentucky coal, Wheelabrator-Frye's electrostatic precipitator provides excellent particulate control efficiency while using a spray dryer for sulfur dioxide removal. A unique project at Carnegie-Mellon University is looking at the concept of integrated environmental control for coal-fired power plants making use of precombustion, combustion, and postcombustion control, including systems for the simultaneous removal of more than one pollutant. The objective of this research is to develop a computer model and assessment for integrated environmental control systems that utilize conventional or advanced systems. The Liquid Phase Methanol Project Development Unit in LaPorte, Texas, was restarted after a successful shakedown run was completed. PETC has recently begun an in-house research project aimed at exploring the basic chemistry of liquefying coal in the presence of water under supercritical conditions. In the Alternative Fuels Technology Program, the Gulf Research and Development Company has completed the preliminary testing phase of its erosion test loop. Their results indicate that when pumping a coal-water slurry fuel through a flow loop, the erosion rate increases as velocity increases, suggesting a well-defined relationship between these two parameters.

  15. Development of an Inertia-Increased ABWR Internal Pump

    International Nuclear Information System (INIS)

    Shirou Takahashi; Kousei Umemori; Kooji Shiina; Tetsuya Totani; Akihiro Sakashita; Norimichi Yamashita; Takahisa Kondo

    2002-01-01

    It is possible to simplify the reactor internal pump power supply system in the ABWR without affecting the core flow supply when a trip of all RIPs event occurs by eliminating the motor-generator sets and increasing the rotating inertia of the RIPs. This inertia increase due to an additional flywheel, which leads to a gain in weight and length, requires a larger diameter nozzle with a thicker sleeve. However, a thicker sleeve nozzle and a longer and heavier motor casing may change the RIP performance. In the present study, the inertia-increased RIP was verified through full-scale tests. The rotating inertia time constant for coast-down characteristics (behavior of the RIP speed in the event of power loss) for the inertia-increased RIP was doubled compared with the current RIP. The inertia-increased RIP with the thicker sleeve nozzle maintained good performance and its power supply system without motor-generator sets was judged appropriate for the ABWR. (authors)

  16. Advanced design and construction technology for ABWR

    International Nuclear Information System (INIS)

    Kawahara, Akira

    2003-01-01

    Recently, many countries start planning to construct nuclear plants, and the electric power companies and the plant suppliers are acutely aware of the importance of the technical infrastructure required for construction planning and execution as this has a significant influence on construction costs. Plant suppliers in Japan have been focusing its attention on the efficiency of construction from earlier, because of its significant role in determining overall construction costs. Through continuous efforts to reduce fieldwork costs, we have developed unique technologies, especially the 3D-CAD system and other advanced construction technologies including modularization. We, plant suppliers are now turning its attention to overseas nuclear plants construction also, and are developing more rational, economical, and global construction based on its vast experience in construction techniques. In this report, the evolution of plant engineering methods and construction technologies, the present level of progress in construction, and technical developments for the future, are described. (author)

  17. LMFBR aerosol release and transport program. Quarterly progress report, July-September 1981

    International Nuclear Information System (INIS)

    Kress, T.S.; Tobias, M.L.

    1982-01-01

    This report summarizes progress for the Aerosol Release and Transport Program sponsored by the Office of Nuclear Regulatory Research, Division of Accident Evaluation of the Nuclear Regulatory Commission for the period July-September 1981. Topics discussed include (1) preparations for under-sodium tests at the Fast Aerosol Simulant Test Facility, (2) progress in interpretation of Oak Ridge National Laboratory-Sandia Laboratory normalization test results, (3) U 3 O 8 in steam (light-water reactor accident) aerosol experiments conducted in the Nuclear Safety Power Plant, (4) experiments on B 2 O 3 and SiO 2 aerosols at the Containment Research Installation-II Facility, (5) fuel-melting tests in small-scale experimental facilities for the core-melt aerosol program, (6) analytical comparison of simple adiabatic nonlinear and linear analytical models of bubble oscillation phenomena with experimental data

  18. Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, October-December 1981

    International Nuclear Information System (INIS)

    Steindler, M.J.; Bates, J.K.; Cannon, T.F.

    1982-05-01

    Methods of measuring rates of leaching from simulated waste glasses using neutron activation analysis and radiotracers have been developed. Laboratory-scale impact tests of solid alternative waste forms are being performed to obtain a size analysis of the fragments. Logging techniques are being developed to measure the relative amount of residual oil in a depleted oil reservoir by injecting gamma-active solution into it. Work to test the behavior of radionuclides leached from proposed nuclear-waste repositories using laboratory-analog experiments is in progress. High potassium levels in crushed granite from a Northern Illinois drill hole are probably derived by the leaching of potassium feldspar. Testing and development of equipment for the destructive analysis of full-length irradiated fuel rods from the LWBR are in progress. 19 figures, 13 tables

  19. Low cost solar array project. Quarterly progress report, January-March, 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    The engineering design, fabrication, assembly, operation, economic analysis, and process support R and D for an Experimental Process System Development Unit (EPSDU) are presented. The civil construction work was completed and the mechanical bid package is in preparation. The electrical design effort is in progress. Parallel efforts which complement the mechanical design are the process flow diagrams and control instrumentation logic for startup operation and shutdown. These are in progress and will identify all process and utility streams, control systems, and flow logic. The data collection system takes the signals from the instrumentation, translates them into engineering units and finally develops a data report which summarizes all key performance parameters. Cleaning procedures have been established to assure a contamination-free product and inspection visits have been made to the fabricators of specialty equipment.

  20. Geothermal drilling and completion technology development program. Quarterly progress report, January-March 1980

    Energy Technology Data Exchange (ETDEWEB)

    Varnado, S.G. (ed.)

    1980-04-01

    The progress, status, and results of ongoing Research and Development (R and D) within the Geothermal Drilling and Completion Technology Development Program are described. The program emphasizes the development of geothermal drilling hardware, drilling fluids, completion technology, and lost circulation control methods. Advanced drilling systems are also under development. The goals of the program are to develop the technology required to reduce well costs by 25% by 1983 and by 50% by 1987.

  1. Nuclear reactor safety. Quarterly progress report, October 1--December 31, 1977

    International Nuclear Information System (INIS)

    Jackson, J.F.; Stevenson, M.G.

    1978-02-01

    Progress in reactor safety research is summarized. LWR studies include TRAC code development for thermal-hydraulic analysis of accidents, containment systems evaluation, and safety experiments. LMFBR studies include SIMMER code development and applications, modeling of core disruptive accidents, and safety test facilities studies. HTGR safety studies cover fission product release and transport, structural evaluation, phenomena modeling, systems analysis, and accident delineation. GCFR studies are focussed on core disruptive testing

  2. Computer Graphics Research Laboratory Quarterly Progress Report Number 49, July-September 1993

    Science.gov (United States)

    1993-11-22

    20 Texture Sampling and Strength Guided Motion: Jeffry S. Nimeroff 23 21 Radiosity : Min-Zhi Shao 24 22 Blended Shape Primitives: Douglas DeCarlo 25 23...placement. "* Extensions of radiosity rendering. "* A discussion of blended shape primitives and the applications in computer vision and computer...user. Radiosity : An improved version of the radiosity renderer is included. This version uses a fast over- relaxation progressive refinement algorithm

  3. Major Oil Plays in Utah and Vicinity. Quarterly Technical Progress Report

    International Nuclear Information System (INIS)

    Thomas C. Chidsey; Craig D. Morgan; Kevin McClure; Douglas A. Sprinkel; Roger L. Bon; Hellmut H. Doelling

    2003-01-01

    Utah oil fields have produced over 1.2 billion barrels (191 million m 3 ). However, the 13.7 million barrels (2.2 million m 3 ) of production in 2002 was the lowest level in over 40 years and continued the steady decline that began in the mid-1980s. The Utah Geological Survey believes this trend can be reversed by providing play portfolios for the major oil-producing provinces (Paradox Basin, Uinta Basin, and thrust belt) in Utah and adjacent areas in Colorado and Wyoming. Oil plays are geographic areas with petroleum potential caused by favorable combinations of source rock, migration paths, reservoir rock characteristics, and other factors. The play portfolios will include: descriptions and maps of the major oil plays by reservoir; production and reservoir data; case-study field evaluations; locations of major oil pipelines; identification and discussion of land-use constraints; descriptions of reservoir outcrop analogs; and summaries of the state-of-the-art drilling, completion, and secondary/tertiary techniques for each play. This report covers research activities for the sixth quarter of the project (October 1 through December 31, 2003). This work included describing outcrop analogs for the Jurassic Twin Creek Limestone and Mississippian Leadville Limestone, major oil producers in the thrust belt and Paradox Basin, respectively, and analyzing best practices used in the southern Green River Formation play of the Uinta Basin. Production-scale outcrop analogs provide an excellent view of reservoir petrophysics, facies characteristics, and boundaries contributing to the overall heterogeneity of reservoir rocks. They can be used as a ''template'' for evaluation of data from conventional core, geophysical and petrophysical logs, and seismic surveys. In the Utah/Wyoming thrust belt province, the Jurassic Twin Creek Limestone produces from subsidiary closures along major ramp anticlines where the low-porosity limestone beds are extensively fractured and sealed by

  4. Decontamination Systems Information and Research Program. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    Progress reports are presented for the following projects: systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies--drain-enhanced soil flushing (DESF) for organic contaminants removal; excavation systems for hazardous waste sites; chemical destruction of polychlorinated biphenyls; development of organic sensors--monolayer and multilayer self-assembled films for chemical sensors; Winfield Lock and Dam remediation; Winfield cleanup survey; assessment of technologies for hazardous waste site remediation--non-treatment technologies and pilot scale test facility implementation; assessment of environmental remediation storage technology; assessment of environmental remediation excavation technology; assessment of environmental remediation monitoring technology; and remediation of hazardous sites with steam reforming.

  5. The Pennsylvania State University Light Water Ultra-Safe Plant Concept: 3rd quarter progress report

    International Nuclear Information System (INIS)

    Klevans, E.

    1987-01-01

    Progress in the Ultra Safe study has substantially increased since the last report. The search for pressurizing pump turbine component information is now complete and a final plant layout for detailed evaluation has been chosen. Significant results for the normal operation performance of the Ultra Safe pressurizing technique are included. The plan of attack for the evaluation of the Ultra Safe shutdown scenario and natural circulation capability is discussed. This process is expected to be the next key area for analysis. The reactor design is complete including a change to alleviate the need for a soluble boron system. Material on the reactor building layout is also provided

  6. MHD power generation research, development and engineering. Quarterly progress report, October-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-01-01

    Progress is reported on the following tasks: characterization of coal for open-cycle MHD power generation systems; compressive creep and strength studies of MHD preheater materials; preparation of coals for utilization in direct coal-fired MHD generation; characterization of volatile matter in coal; MHD materials evaluation; operability of the Moderate Temperature Slag Flow Facility; slag-seed equilibria and separations related to the MHD system; thermionic emission of coal and electrode materials; MHD instrumentation, consolidated inversion simulator, and data acquisition; combined MHD-steam plant cycle analysis and control; and slag physical properties - electrical and thermal conductivity. (WHK)

  7. Decontamination Systems Information and Research Program. Quarterly technical progress report, July 1--September 30, 1993

    International Nuclear Information System (INIS)

    1993-10-01

    Progress reports are presented for the following projects: systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies--drain-enhanced soil flushing (DESF) for organic contaminants removal; excavation systems for hazardous waste sites; chemical destruction of polychlorinated biphenyls; development of organic sensors--monolayer and multilayer self-assembled films for chemical sensors; Winfield Lock and Dam remediation; Winfield cleanup survey; assessment of technologies for hazardous waste site remediation--non-treatment technologies and pilot scale test facility implementation; assessment of environmental remediation storage technology; assessment of environmental remediation excavation technology; assessment of environmental remediation monitoring technology; and remediation of hazardous sites with steam reforming

  8. Decontamination Systems Information and Research Program. Quarterly technical progress report, January 1--March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    This reports reports the progress/efforts performed on six technical projects: 1. systematic assessment of the state of hazardous waste clean-up technologies; 2. site remediation technologies (SRT):drain- enhanced soil flushing for organic contaminants removal; 3. SRT: in situ bio-remediation of organic contaminants; 4. excavation systems for hazardous waste sites: dust control methods for in-situ nuclear waste handling; 5. chemical destruction of polychlorinated biphenyls; and 6. development of organic sensors: monolayer and multilayer self-assembled films for chemical sensors.

  9. Thermionic cogeneration burner assessment study. Third quarterly technical progress report, April-June, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    The specific tasks of this study are to mathematically model the thermionic cogeneration burner, experimentally confirm the projected energy flows in a thermal mock-up, make a cost estimate of the burner, including manufacturing, installation and maintenance, review industries in general and determine what groups of industries would be able to use the electrical power generated in the process, select one or more industries out of those for an in-depth study, including determination of the performance required for a thermionic cogeneration system to be competitive in that industry. Progress is reported. (WHK)

  10. Electric and Hybrid Vehicle Program, Site Operator Program. Quarterly progress report, October--December 1995 (first quarter of fiscal year 1996)

    Energy Technology Data Exchange (ETDEWEB)

    Francfort, J.E. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Bassett, R.R. [Sandia National Labs., Albuquerque, NM (United States); Briasco, S. [Los Angeles Dept. of Water and Power, CA (United States)] [and others

    1996-03-01

    This is the Site Operator Program quarterly report for USDOE electric and hybrid vehicle research. Its mission now includes the three major activity categories of advancement of electric vehicle (EV) technologies, development of infrastructure elements needed to support significant EV use and increasing public awareness and acceptance of EVs. The 11 Site Operator Program participants, their geographic locations, and the principal thrusts of their efforts are identified. The EV inventories of the site operators totals about 250 vehicles. The individual fleets are summarized.

  11. Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy, quarter ending March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Ruhter, W.D.; Strait, R.S.; Mansur, D.L.; Davis, G.

    1993-04-01

    This quarterly report discusses activities in the Safeguards Technology Program (STP) which is a program in LLNL`s Nuclear Chemistry Division that develop advanced, nondestructive-analysis (NDA) technology for measurement of special nuclear materials. The work focuses on R&D relating to x{minus} and gamma-ray spectrometry techniques and to the development of computer codes for interpreting the spectral data obtained by these techniques.

  12. Chemistry Division. Quarterly progress report for period ending June 30, 1949

    Energy Technology Data Exchange (ETDEWEB)

    1949-09-14

    Progress reports are presented for the following tasks: (1) nuclear and chemical properties of heavy elements (solution chemistry, phase rule studies); (2) nuclear and chemical properties of elements in the fission product region; (3) general nuclear chemistry; (4) radio-organic chemistry; (5) chemistry of separations processes; (6) physical chemistry and chemical physics; (7) radiation chemistry; (8) physical measurements and instrumentation; and (9) analytical chemistry. The program of the chemistry division is divided into two efforts of approximately equal weight with respect to number of personnel, chemical research, and analytical service for the Laboratory. The various research problems fall into the following classifications: (1) chemical separation processes for isolation and recovery of fissionable material, production of radioisotopes, and military applications; (2) reactor development; and (3) fundamental research.

  13. Nuclear Medicine Program progress report for quarter ending June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; Hsieh, B.T.; McPherson, D.W.; Mirzadeh, S.; Lambert, C.R.

    1993-07-01

    The ``IQNP`` agent is an antagonist for the cholinergic-muscarinic receptor. Since the IQNP molecule has two asymmetric centers and either cis or trans isomerism of the vinyl iodide, there are eight possible isomeric combinations. In this report, the systematic synthesis, purification and animal testing of several isomers of radioiodinated ``IQNP`` are reported. A dramatic and unexpected relation between the absolute configuration at the two asymmetric centers and the stereochemistry of the vinyl iodide on receptor specificity was observed. The E-(R)(R) isomer shows specific and significant localization (per cent dose/gram at 6 hours) in receptor-rich cerebral structures (i.e. Cortex = 1.38 + 0.31; Striatum = 1.22 + 0.20) and low uptake in tissues rich in the M{sub 2} subtype (Heart = 0.10; Cerebellum = 0.04). In contrast, the E-(R)(S) isomer shows very low receptor-specific uptake (Cortex = 0.04; Striatum = 0.02), demonstrating the importance of absolute configuration at the acetate center. An unexpected and important observation is that the stereochemistry of the vinyl iodine appears to affect receptor subtype specificity, since the Z-(R,S)(R) isomer shows much higher uptake in the heart (0.56 + 0.12) and cerebellum (0.17 + 0.04). Studies are now in progress to confirm these exciting results in vitro. Progress has also continued during this period with several collaborative programs. The first large-scale clinical tungsten-188/rhenium-188 generator prototype (500 mCi) was fabricated and supplied to the Center for Molecular Medicine and Immunology (CMMI), in Newark, New Jersey, for Phase I clinical trials of rhenium-188-labeled anti CEA antibodies for patient treatment. Collaborative studies are also continuing in conjunction with the Nuclear Medicine Department at the University of Massachusetts where a generator is in use to compare the biological properties of {open_quotes}direct{close_quotes} and {open_quotes}indirect{close_quotes} labeled antibodies.

  14. What kind of nuclear energy should be offered? Ge's ABWR nuclear plant

    International Nuclear Information System (INIS)

    Hucik, S.; Redding, J.

    2000-01-01

    GE is proud of the ABWR design and our accomplishments in providing this safe, cost effective means of generating electricity to our customers around the world. The ABWR defines the new generation of advanced nuclear plant designs that have achieved higher levels of safety, compete economically with other forms of power generation, and can contribute importantly to the goals of sustainable development. The GE-led team has amassed significant experience in licensing, designing, and constructing the ABWR and has established a strong track record of success in doing so. We believe the quality of the ABWR design and our experience will have a strong appeal to utility business managers and the financial community. Finally we believe in nuclear energy and it's ability to improve the quality of people's lives throughout the world. Nuclear energy can and should play an important role in meeting the worlds' growing needs for electricity while at the same time preserving our environment for future generations. (authors)

  15. Cost reduction and safety design features of ABWR-II. Annex 5

    International Nuclear Information System (INIS)

    Koh, F.; Moriya, K.; Anegawa, T.

    2002-01-01

    The ABWR-II, which is aimed to be the next generation reactor following the latest BWR: Advanced Boiling Reactor (ABWR), is now under development jointly by the Japanese BWR utilities, General Electric Company, Hitachi Limited, and Toshiba Corporation. The key objectives of ABWR-II development include improvement in economics and further sophistication in safety for commercialization in the late 2010's and after. This paper summarizes the current status of ABWR-II development focusing on economics and safety. Plant power rating, fuel size, CRD rationalization and outage period are discussed from a cost reduction perspective. In terms of safety, the features such as diversification in emergency power sources and passive system application against severe accidents are being introduced. (author)

  16. Nuclear-waste-management. Quarterly progress report, July-September 1981

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.; Powell, J.A. (comps.)

    1981-12-01

    Progress reports and summaries are presented for the following: high-level waste process development, alternate waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and fuel pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

  17. Fuel-cycle programs. Quarterly progress report, January-March 1981

    International Nuclear Information System (INIS)

    Steindler, M.J.; Vogler, S.; Vandegrift, G.F.

    1982-03-01

    A program continues for the development of an interim waste form that can be transported from facilities where waste is generated to terminal waste processing. Measurements of rates of leaching from simulated nuclear waste forms ar continuing. The data suggest that leaching from SRL glasses is inhibited by the formation of a Si/Ca/Fe/Al-rich surface layer. Impact tests of solid alternative waste forms (glass and ceramic) are being performed to assess source terms of airborne release (from particle size distributions) and to assess the increases in source terms of leach rates (from increases in surface area). Logging techniques are being developed to measure the relative amount of residual oil in a depleted oil reservoir. A simple technique for the elution of pore fluid (groundwater) from igneous rocks is described, using a special coreholder, as is the elution of brine (in the same apparatus) from a core of Precambrian granite. Testing and development of equipment for the destructive analysis of full-length irradiated fuel rods from the LWBR is in progress

  18. Proton resonance spectroscopy. Quarterly technical progress report, December 1992--November 1995

    International Nuclear Information System (INIS)

    Shriner, J.F. Jr.

    1995-11-01

    Work on chaos in the low-lying levels of nuclei has continued on several fronts. The major effort has been study of the 29 Si(p,γ) reaction with the goal of establishing a complete level scheme for 30 P and analyzing the eigenvalue fluctuations for evidence of chaos. These measurements are in progress, and the current status is described. A related topic is the search for different signatures of chaos which do not require the extremely high degree of completeness and purity necessary for eigenvalue analyses; those efforts are discussed in Sections 2 and 3. The possibility of studying both parity violation and time-reversal invariance violation with charged particle resonances has been explored by performing calculations using experimentally measured resonance parameters. Large enhancements are indeed available; the results are discussed in Sections 4 and 5. Preparations for an experimental study of parity violation using these techniques are ongoing. An undergraduate project searching for experimental evidence of a parity dependence of level density is discussed in Section 6. A number of improvements to the operation of the TUNL KN accelerator have been implemented in the past three years. These are described in Section 7

  19. Proton resonance spectroscopy. Quarterly technical progress report, December 1992--November 1995

    Energy Technology Data Exchange (ETDEWEB)

    Shriner, J.F. Jr.

    1995-11-01

    Work on chaos in the low-lying levels of nuclei has continued on several fronts. The major effort has been study of the {sup 29}Si(p,{gamma}) reaction with the goal of establishing a complete level scheme for {sup 30}P and analyzing the eigenvalue fluctuations for evidence of chaos. These measurements are in progress, and the current status is described. A related topic is the search for different signatures of chaos which do not require the extremely high degree of completeness and purity necessary for eigenvalue analyses; those efforts are discussed in Sections 2 and 3. The possibility of studying both parity violation and time-reversal invariance violation with charged particle resonances has been explored by performing calculations using experimentally measured resonance parameters. Large enhancements are indeed available; the results are discussed in Sections 4 and 5. Preparations for an experimental study of parity violation using these techniques are ongoing. An undergraduate project searching for experimental evidence of a parity dependence of level density is discussed in Section 6. A number of improvements to the operation of the TUNL KN accelerator have been implemented in the past three years. These are described in Section 7.

  20. Chemical Engineering Division fuel cycle programs. Quarterly progress report, July-September 1978

    Energy Technology Data Exchange (ETDEWEB)

    Steindler, M.J.; Ader, M.; Barletta, R.E.

    1980-01-01

    Fuel cycle work included hydraulic performance and extraction efficiency of eight-stage centrifugal contactors, flowsheet for the Aralex process, Ru and Zr extraction in a miniature centrifugal contactor, study of Zr aging in the organic phase and its effect on Zr extraction and hydraulic testing of the 9-cm-ID contactor. Work for predicting accident consequences in LWR fuel processing covered the relation between energy input (to subdivide a solid) and the modes of particle size frequency distribution. In the pyrochemical and dry processing program corrosion-testing materials for containment vessels and equipment for studying carbide reactions in bismuth is under way. Analytical studies have been made of salt-transport processes; efforts to spin tungsten crucibles 13 cm dia continue, and other information on tungsten fabrication is being assembled; the process steps of the chloride volatility process have been demonstrated and the thoria powder product used to produce oxide pellets; solubility of UO/sub 2/, PuO/sub 2/, and fission products in molten alkali nitrates is being investigated; work was continued on reprocessing actinide oxides by extracting the actinides into ammonium chloroaluminate from bismuth; the preparation of thorium-uranium carbide from the oxide is being studied as a means of improving the oxide reactivity; studies are in progress on producing uranium metal and decontaminated ThO/sub 2/ by the reaction of (Th,U)O/sub 2/ solid solution in molten salts containing ThCl/sub 4/ and thorium metal chips. In the molten tin process, no basic thermodynamic or kinetic factors have been found that may limit process development.

  1. Instrumentation of dynamic gas pulse loading system. Technical progress report, first quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    Mohaupt, H.

    1992-04-14

    The overall goal of this work is to further develop and field test a system of stimulating oil and gas wells, which increases the effective radius of the well bore so that more oil can flow into it, by recording pressure during the gas generation phase in real time so that fractures can be induced more predictably in the producing formation. Task 1: Complete the laboratory studies currently underway with the prototype model of the instrumentation currently being studied. Task 2: Perform field tests of the model in the Taft/Bakersfield area, utilizing operations closest to the engineers working on the project, and optimize the unit for various conditions encountered there. Task 3: Perform field test of the model in DGPL jobs which are scheduled in the mid-continent area, and optimize the unit for downhole conditions encountered there. Task 4: Analyze and summarize the results achieved during the complete test series, documenting the steps for usage of downhole instrumentation in the field, and compile data specifying use of the technology by others. Task 5: Prepare final report for DOE, and include also a report on the field tests completed. Describe and estimate the probability of the technology being commercialized and in what time span. The project has made substantial technical progress, though we are running about a month behind schedule. Expenditures are in line with the schedule. Increased widespread interest in the use of DGPL stimulation has kept us very busy. The computer modeling and test instrumentation developed under this program is already being applied to commercial operations.

  2. Nuclear Medicine Technology. Progress report for quarter ending September 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, Jr., F. F.

    1979-02-01

    A unique class of radiopharmaceuticals labeled with the /sup 117m/Sn nuclide has been developed. The attractive properties of /sup 117m/Sn include a 14-day physical half-life and the emission of a single ..gamma..-photon with an optimal energy of 159 keV. A specialized apparatus was designed for the conversion of metallic /sup 117m/Sn to /sup 117m/SnCl/sub 4/ which was subsequently converted to a variety of useful /sup 117m/Sn-labeled organotin intermediates. The availability of this unique approach will now make possible the synthesis of a wide variety of /sup 117m/Sn-labeled compounds of biological interest. Such tissue-specific /sup 117m/Sn-labeled agents may represent a new class of useful radiopharmaceuticals. Continuing studies involving the preparation and testing of radiopharmaceuticals labeled with /sup 11/C, /sup 195m/Pt, and /sup 75/Se are also described. Several /sup 11/C-labeled amino acids including /sup 11/C-DL-tryptophan, /sup 11/C-1-aminocyclobutanecarboxylic acid (ACBC), and /sup 11/C-1-aminocyclopentanecarboxylic acid (ACPC) were prepared, and patient studies have demonstrated ACBC to be superior to ACPC for tumor localization. Studies with /sup 195m/Pt have recently been directed toward attempting to prepare high specific activity /sup 195m/Pt by the Szilard--Chalmers process. Progress is also reported in the development of an in vivo diffusion chamber assay technique that is being used to investigate the cytotoxicity of cyclophosphamide and cis-dichlorodiammineplatinum(II) on the growth of KB tumor cells. More recent studies with /sup 75/Se-labeled ..beta..-aminoethyl selenosulfate have demonstrated the significant pancreatic uptake of this agent. (ERB)

  3. Defence-in-depth concept for the EU-ABWR

    Energy Technology Data Exchange (ETDEWEB)

    Yamazaki, Hiroshi; Fuchs, Steffen; Takada, Toshiaki; Kataoka, Kazuyoshi [Toshiba International Limited (Japan)

    2013-07-01

    The current defence-in-depth (DiD) concept has been established by the Reactor Harmonization Working Group (RHWG) of Western European Nuclear Regulators Association (WENRA). Principally the DiD concept was already part of the very early power reactor designs. However, additional considerations have been done in order to take plant conditions into account which are beyond the original design basis. The most recent advancements have been done based on major lessons learned from the Fukushima Dai-Ichi accident. Especially for new nuclear reactors it has to be demonstrated that DiD aspects have been considered in their design. Currently Toshiba is adapting its Advanced Boiling Water Reactor (ABWR) for the European market, at first in Finland. This presentation aims to describe how the new DiD concept has been applied to achieve the safety goals for a modern reactor type and to ensure a design that can be licensed in Western Europe. (orig.)

  4. Photoelectronic properties of zinc phosphide crystals, films and heterojunctions. Quarterly progress report No. 1, February 26-June 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Bube, R.H.

    1979-07-01

    A closed tube method has been developed for the synthesis of Zn/sub 3/P/sub 2/ from the elements which eliminates the potential dangers associated with high P pressures. Subsequent materials synthesis will be done routinely by this method. Initial efforts at single crystal growth of Zn/sub 3/P/sub 2/ from this material yielded polycrystalline material because of nucleation along the walls of the tube. Techniques for improving the situation are being tested. Wafers of large-grain polycrystaline Zn/sub 3/P/sub 2/ have been received from Dr. A. Catalano at Delaware and will be used for exploratory research in the quarter ahead. Progress is reported on the development of a CVD apparatus for the deposition of wide bandgap oxides and sulfides on a variety of substrates including Zn/sub 3/P/sub 2/. Layer deposition by the close spaced vapor transport method to be applied to Zn/sub 3/P/sub 2/ was successfully tested using CdTe on both quartz and CdS substrates.

  5. Nuclear medicine technology progress report for quarter ending December 31, 1980

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.

    1981-05-01

    A method was developed for the synthesis of terminal haloalkyl (X-R)-substituted selenium (Se)- and tellurium (Te)-long-chain fatty acids. Several iodinated Se- and Te-fatty acids have now been prepared including the iodinated analog of methyl-9-THDA, methyl-17-iodo-9-telluraheptadecanoic acid [I-(CH 2 ) 8 -Te-(CH 2 ) 7 -COOCH 3 ]. A principal goal is the preparation and biological evaluation of the 123 I-labeled fatty acids. Osmium-191 was produced for the first time in the High Flux Isotope Reactor (HFIR) and supplied to collaborators for patient studies with the /sup 191m/Ir daughter obtained from the 191 Os → /sup 191m/Ir generator system. The /sup 191m/Ir is an excellent isotope for first-pass radionuclide angiographic evaluation of ventricular ejection fraction, intracardiac shunts, and a variety of other clinical applications. The factors affecting 191 Os production are being investigated and improvements in the generator are in progress. In a new cooperative program, /sup 117m/Sn has been produced in the HFIR and supplied to investigators to investigate the mechanism of labeling of red blood cells (rbc) with /sup 117m/SnCl 2 for performing rbc volume measurements, and gated blood pool imaging studies. Labeling is efficient (70%), and the /sup 117m/Sn is strongly bound to the cells. The attractive emission properties and moderate physical half-life of /sup 117m/Sn suggest that /sup 117m/Sn-labeled rbc ejection fraction measurements could be very useful if high specific activity /sup 117m/Sn can be produced. Five production runs of 11 C-labeled amino acids were made in conjunction with the Oak Ridge Associated Universities (ORAU). These agents were evaluated for tumor localization, pancreas imaging, and brain scanning in patients and included 11 C-DL-valine, 11 C-DL-tryptophan, and 11 C-l-aminocyclobutanecarboxylic acid ( 11 C-ACBC)

  6. Features of ABWR operator training with a full-scope simulator

    International Nuclear Information System (INIS)

    Kondou, Shin'ichi

    1999-01-01

    Many innovations have been incorporated into the Advanced BWR (ABWR) type control panels. In the BWR Operator Training Center (BTC), we started ABWR operator training using an ABWR full-scope simulator prior to the first ABWR plant's commercial operation. In consideration of the features of the ABWR type control panels, BTC has been conducting ABWR operator training focusing on the following 2 points; (1) Operator training reflecting the differences in the Human-Machine Interface (HMI). The new HMI devices which have the touch-operation function were introduced. These devices have higher operability, however, they require new operational skills. We planned the training program so that operators can fully acquire these skills. Also the compact main console and the new HMI devices made it relatively difficult for the operator crews to grasp visually what an operator was doing. We provide the training to have proper communication skills, and check trainees' operation using monitoring systems for simulator training. (2) Operator training responding to the expanded operation automation system. The scope of the automation system was expanded to reduce the operators' burden. We provide the training to improve the trainees' competence for 'operation and monitoring' suitable to both manual and automatic operational modes. (author)

  7. Computational mechanics research and support for aerodynamics and hydraulics at TFHRC year 1 quarter 4 progress report.

    Energy Technology Data Exchange (ETDEWEB)

    Lottes, S.A.; Kulak, R.F.; Bojanowski, C. (Energy Systems)

    2011-12-09

    under high wind conditions. This quarterly report documents technical progress on the project tasks for the period of July through September 2011.

  8. Evaluation of using cyclocranes to support drilling and production of oil and gas in wetland areas. Fifth quarterly technical progress report, Third quarter, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Eggington, W.J.

    1993-12-31

    The planned program falls under wetlands area research related to drilling, production, and transportation of oil and gas resources. Specifically the planned program addresses an evaluation of using cyclocraft to transport drill rigs, mud, pipes and other materials and equipment in a cost effective and environmentally safe manner to support oil and gas drilling and production operations in wetland areas. The cyclocraft is a proven hybrid aircraft that utilizes aerostatic and aerodynamic lift. This type of aircraft has considerable payload capacity, VTOL capability, high controllability, low operating cost, low downwash and high safety. The benefits of using a cyclocraft to transport drill rigs and materials over environmentally-sensitive surfaces would be significant. The cyclocraft has considerable cost and operational advantages over the helicopter. In 1992, Task 1, Environmental Considerations, and Task 2, Transport Requirements, were completed. In the first two quarters of 1993, Task 3, Parametric Analysis, Task 4, Preliminary Design, and Task 6, Ground Support, were completed. Individual reports containing results obtained from each of these tasks were submitted to DOE. In addition, through June 30, 1993, a Subscale Test Plan was prepared under Task 5, Subscale Tests, and work was initiated on Task 7, Environmental Impacts, Task 8, Development Plan, Task 9, Operating Costs, and Task 10, Technology Transfer.

  9. Evaluation of using cyclocranes to support drilling and production of oil and gas in wetland areas. Fourth quarterly technical progress report, Second quarter, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Eggington, W.J.

    1993-09-01

    The planned program falls under wetlands area research related to drilling, production, and transportation of oil and gas resources. Specifically the planned program addresses an evaluation of using cyclocraft to transport drill rigs, mud, pipes and other materials and equipment in a cost effective and environmentally safe manner to support oil and gas drilling and production operations in wetland areas. The cyclocraft is a proven hybrid aircraft that utilizes aerostatic and aerodynamic lift. This type of aircraft has considerable payload capacity, VTOL capability, high controllability, low operating cost, low downwash and high safety. The benefits of using a cyclocraft to transport drill rigs and materials over environmentally-sensitive surfaces would be significant. The cyclocraft has considerable cost and operational advantages over the helicopter. The major activity during the second quarter of 1993 was focussed on completion of Task 4, Preliminary Design. The selected design has been designated H.1 Cyclocraft by MRC. Also during the report period, Task 6, Ground Support, was completed and a report containing the results was submitted to DOE. This task addressed the complete H.1 Cyclocraft system, i.e. it included the need personnel, facilities and equipment to support cyclocraft operations in wetland areas.

  10. Man-machine interface systems and operator training program for ABWR in Japan

    International Nuclear Information System (INIS)

    Kunito, Susumu

    2004-01-01

    The Tokyo Electric Power Company (TEPCO) has developed a new Main Control Room design for the Advanced Boiling Water Reactor (ABWR) to improve man-machine interface. New configuration of panels and enhanced automation are some of the features of the ABWR type Main Control Room design. Various technologies such as Cathode Ray Tubes (CRTs) and Flat Displays (FDs) with touch-sensitive operations are contributed to the development of the ABWR type control room design. This design will be first applied to Kashiwazaki-Kariwa Nuclear Power Station unit 6 (K-6). To train the operators sufficiently, TEPCO reviewed the operator training program. Compared with the conventional training, new training menu will be added and the training of ABWR operators will be started 6 months earlier. An ABWR simulator is under construction and training using this simulator is scheduled to be started in August 1994, which is 18 months before fuel loading of K-6. We are reviewing malfunction modes on the simulator. (author)

  11. Transient analysis of ABWR reactor using a best estimate code

    International Nuclear Information System (INIS)

    Mizokami, S.; Kitamura, H.; Mototani, A.; Ono, H.

    2004-01-01

    Since the recirculation pumps are mounted internally within the ABWR, core flow will decrease rapidly in the event of a loss of their driving force. A rapid reduction in core flow may cause the onset of boiling transition (BT). Therefore, in order to prevent the onset of BT, a motor-generator (MG) set is added to the power supply system of the reactor internal pump (RIP). Recent studies, however, have shown that dryout within a fuel assembly over a short time period will result in only a small rise in fuel cladding temperature and thus does not pose a threat to fuel integrity. In response to this finding, the standards committee of the Atomic Energy Society of Japan (AESJ) has proposed a post-BT standard which incorporates a cladding temperature criterion. If it is assumed that the MG-set is not added to the RIP power supply system, the result of the safety analysis shows the onset of BT with a subsequent rise in fuel cladding temperature. Although BT occurs under the conservative assumptions of this safety analysis, a possibility exists that BT will not occur under actual operating conditions. The best estimate code TRACG was used to show that BT does not occur and that fuel integrity can be sufficiently maintained under actual conditions. (author)

  12. Initiatives to reduce the occupational radiation exposure of ABWR plants

    International Nuclear Information System (INIS)

    Hirasawa, Hajime; Urata, Hidehiro; Ueda, Taku; Yamamoto, Seiji; Yaita, Yumi

    2014-01-01

    Toshiba has carried out radiation exposure reduction by radiation level reduction, as reduction of reactor water activated corrosion products concentration, reduction of activated corrosion products deposition and radiation shielding, and exposure time reduction, as remote control and improvement of maintenance work procedures. Water chemistry has been mainly carried out reduction of reactor water activated corrosion products concentration and reduction of activated corrosion products deposition in radiation level reduction. The reduction measures of reactor water activated corrosion products concentration are mainly reduction of iron crud concentration and reduction of cobalt ion concentration. The activated corrosion products deposition are reduced by the means of water quality control and the surface treatment. Water quality control for reduction of activated corrosion products deposition moves to ultra low iron high nickel control from Ni/Fe ratio control. The surface treatments are adopted to the stainless steel piping and carbon steel piping. As a measure further to radiation exposure reduction for ABWR (Advanced Boiling Water Reactors), we report on the effect of generation amount reduction by the adoption of alternate material and the effect of deposition reduction by material change of piping and the adoption of advanced water quality control, etc. (author)

  13. Improvement of SSR core design for ABWR-II

    International Nuclear Information System (INIS)

    Moriwaki, Masanao; Aoyama, Motoo; Okada, Hiroyuki; Kitamura, Hideya; Sakurada, Koichi; Tanabe, Akira

    2003-01-01

    In order to enhance the spectral shift effect in the ABWR-II reactor, a novel core design to bring out better performance of spectral shift rods (SSRs) is studied. The SSR is a new type of water rod, in which the water level develops naturally during operation and changes according to the coolant flow rate through the channel. By using the SSR, the average moderator density, which is directly related to core reactivity, can be controlled over a wide range by the core flow rate. In the new SSR core design, two types of SSR bundles, in which settings for the SSR water levels are different, are utilized and loaded according to flow distribution in the core. This two-region SSR core design allows wide variation in the average SSR water level, thus improving fuel economy. Enhancement of SSR function in the two-region SSR core increases the uranium saving factor by about 25%, from the 6% of the conventional uniform SSR core to about 8%. (author)

  14. BX in-situ oil-shale project. Quarterly technical progress report, June 1, 1981-August 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Dougan, P.M.

    1981-09-20

    June 1, 1981-August 31, 1981 was the third consecutive quarter of superheated steam injection at the BX In Situ Oil Shale Project. Injection was continuous except for the period of July 14th to August 1st when the injection was suspended during the drilling of core hole BX-37. During the quarter, 99,760 barrels of water as superheated steam were injected into Project injection wells at an average well head temperature of 752/sup 0/F and an average wellhead pressure of 1312 PSIG. During the same period, 135,469 barrels of fluid were produced from the Project production wells for a produced to injected fluid ratio of 1.36 to 1.0. Net oil production during the quarter was 38 barrels.

  15. Contracts for field projects and supporting research on enhanced oil recovery: Progress review No. 74, Quarter ending March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    Accomplishments for the past quarter are presented for the following tasks: chemical flooding--supporting research; gas displacement--supporting research; thermal recovery--supporting research; geoscience technology; resource assessment technology; microbial technology; field demonstrations in high-priority reservoir classes; and novel technology. A list of available publication is also provided.

  16. Support of enhanced oil recovery to independent producers in Texas. Quarterly technical progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Fotouh, K.H.

    1995-09-30

    The main objective of this project is to support independent oil producers in Texas and to improve the productivity of marginal wells utilizing enhanced oil recovery techniques. The main task carried out this quarter was the generation of an electronic data base.

  17. NRC TLD Direct Radiation Monitoring Network. Volume 15, No. 4: Quarterly progress report, October--December 1995

    International Nuclear Information System (INIS)

    Struckmeyer, R.

    1996-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1995. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  18. NRC TLD Direct Radiation Monitoring Network. Volume 15, No. 4: Quarterly progress report, October--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    Struckmeyer, R.

    1996-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1995. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program.

  19. Enforcement actions: Significant actions resolved. Volume 14, No. 2, Part 1: Individual actions. Quarterly progress report, April--June 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April--June 1995) and includes copies of Orders sent by the Nuclear Regulatory Commission to individuals with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC. The Commission believes this information may be useful to licensees in making employment decisions

  20. Enforcement actions: Significant actions resolved. Volume 14, No. 2, Part 1: Individual actions. Quarterly progress report, April--June 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April--June 1995) and includes copies of Orders sent by the Nuclear Regulatory Commission to individuals with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC. The Commission believes this information may be useful to licensees in making employment decisions.

  1. Simulation technology to develop the automatic control rod operation system in ABWR

    Energy Technology Data Exchange (ETDEWEB)

    Yoshihiko, Ishii; Atsushi, Fushimi; Naoyuki, Ishida [Hitachi Ltd. Power and Industrial Systems R and D Laboratory, Ibaraki (Japan); Hitoshi, Ochi; Masakazu, Yuzuki [Hitachi Ltd. Power Systems, Hitachi Works, Ibaraki (Japan); Hideki, Hanami [Hitachi Ltd. Information and Control System Div., Ibaraki (Japan)

    2007-07-01

    To design and verify the automatic power regulator system (APR) for an advanced boiling water reactor (ABWR), Hitachi has developed a plant simulation code system. The 3-dimensional kinetic analysis code STAND, based on a polynomial nodal expansion method, was effective in developing an APR automatic control rod operation algorithm in the critical mode. The point kinetic plant simulator AUTSIMU is an off-line and real time online plant simulation code that can simulate ABWR start-up and shutdown processes from a sub-critical condition with a water temperature of 20 degrees C to the rated operation power level at about 7 MPa. APR operation algorithms were designed using the off-line mode. In this mode, less than one minute in real time was needed to simulate a ten-hour transient with an ordinary personal computer. In the online mode, APR hardware was efficiently verified in a factory test before shipping. The codes were verified with ABWR start-up experimental data. It was confirmed that the simulators were effective in simulating ABWR plant start-up behavior. (authors)

  2. Production and screening of carbon products precursors from coal. Quarterly progress report, July 1, 1996--September 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Zondlo, J.; Stiller, A.

    1996-10-25

    This quarterly report covers activities during the period from July 1, 1996 through September 30, 1996 on the development of carbon products precursor materials from coal. The first year of the project ended in February, 1996; however, the WVU research effort continued through August 14, 1997 on a no-cost extension of the original contract. PETC chose to exercise the option for continuation of the projects and $100,000 became available on August 9, 1996. The objective for year two is to focus on development of those carbon products from coal-based solvent extract precursors which have the greatest possibility for commercial success.

  3. Enforcement actions: Significant actions resolved medical licensees. Quarterly progress report, January 1995--March 1995. Volume 14, No. 1, Part 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (January-March 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to medical licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  4. Enforcement actions: Significant actions resolved material licensees (non-medical). Quarterly progress report, October 1994--December 1994

    International Nuclear Information System (INIS)

    1995-02-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (October - December 1994) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to material licensees (non-medical) with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  5. Enforcement actions: Significant actions resolved reactor licensees. Quarterly progress report, October--December 1994, Volume 13, No. 4, Part 1

    International Nuclear Information System (INIS)

    1995-02-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (October--December 1994) and includes copies of letters Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  6. Enforcement actions: Significant actions resolved, reactor licensees. Quarterly progress report, July--September 1994; Volume 13, Number 3, Part 1

    International Nuclear Information System (INIS)

    1994-12-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July--September 1994) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  7. Enforcement actions: Significant actions resolved. Reactor licensees: Volume 14, No. 1, Part 1, Quarterly progress report January--March 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (January--March 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  8. Enforcement actions: Significant actions resolved, medical licensees. Quarterly progress report, July--September 1994: Volume 13, Number 3, Part 2

    International Nuclear Information System (INIS)

    1994-12-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July--September 1994) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to medical licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  9. Enforcement actions: Significant actions resolved medical licensees. Quarterly progress report, January 1995--March 1995. Volume 14, No. 1, Part 2

    International Nuclear Information System (INIS)

    1995-05-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (January-March 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to medical licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  10. Enforcement actions: Significant actions resolved material licensees (non-medical). Quarterly progress report, October 1994--December 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (October - December 1994) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to material licensees (non-medical) with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  11. Enforcement actions: Significant actions resolved reactor licensees. Volume 14, No. 2, Part 2, Quarterly progress report, April--June 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April--June 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  12. Enforcement actions: Significant actions resolved reactor licensees. Quarterly progress report, October--December 1994, Volume 13, No. 4, Part 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (October--December 1994) and includes copies of letters Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  13. Enforcement actions: Significant actions resolved reactor licensees. Volume 14, No. 2, Part 2, Quarterly progress report, April--June 1995

    International Nuclear Information System (INIS)

    1995-08-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April--June 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  14. Enforcement actions: Significant actions resolved reactor licensees. Volume 13, No. 1, Part 1: Quarterly progress report, January--March 1994

    International Nuclear Information System (INIS)

    1994-06-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (January--March 1994) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to these described in this publication

  15. Safety design philosophy of the ABWR for the next generation LWRs

    International Nuclear Information System (INIS)

    Sato, Takashi; Akinaga, Makoto; Kojima, Yoshihiro

    2009-01-01

    The paper presents safety design philosophy of the advanced boiling water reactor (ABWR) to be reflected in developing the next generation light water reactors (LWRs). The basic policy of the ABWR safety design was to improve safety and reduce cost simultaneously by reflecting lessons learned of precursors, incidents and accidents that were beyond the design basis such as the Three Mile Island Unit 2 (TMI 2) accident. The ABWR is a fully active safety plant. The ABWR enhanced redundancy and diversity of active safety systems using probabilistic safety assessment (PSA) insights. It adopted a complete three division active emergency core cooling system (ECCS) and attained a very low core damage frequency (CDF) value of less than 10 -7 /ry for internal events. Only very small residual risks, if any, rather exist in external events such as an extremely large earthquake beyond the design basis. This is because external events can constitute a common cause that disables all the redundant active safety systems. Therefore, it is useless to add one more ECCS train and make a four division active ECCS for external events. Nowadays, however, fully passive safety LWRs are already established. Incorporating some of these passive safety systems we can also establish the next generation LWRs that are truly strong against external events. We can establish a plant that can survive a giant earthquake at least three days without AC power source, SA proof safety design that enables no containment failure and no evacuation to eliminate the residual risks. The same basic policy as the ABWR to improve safety and reduce cost simultaneously is again effective for the next generation LWRs. (author)

  16. Investigation of concept of efficient short wavelength laser. Quarterly progress report, 1 May 1978-31 July 1978

    Energy Technology Data Exchange (ETDEWEB)

    Piper, L.G.; Krech, R.H.; Pugh, E.R.; Kothandaraman, G.; Taylor, R.L.

    1978-08-01

    Emphasis on this program has shifted to the design and construction of two proof-of-concept laser device experiments based on azide chemistry. The laser concepts and the resulting experiments are briefly described in this quarterly report. Preliminary shake-down of the apparatus is now underway. In addition, measurements to provide critical kinetic and spectroscopic data in support of these laser-demonstration experiments have continued at a reduced level of effort. In particular, the solid azide pyrolysis experiment has been reactivated to obtain more quantitative data on branching ratios of certain critical processes. Finally, design and construction has begun on a system to provide 4.9 ..mu.. radiation to explore multiphoton dissociation of C1N/sub 3/ as an initiation technique.

  17. Plasma theory and simulation: Quarterly progress report Nos. 1 and 2, January 1, 1986-June 30, 1986

    International Nuclear Information System (INIS)

    Birdsall, C.K.

    1986-01-01

    This quarterly report deals with General Plasma Theory and Simulation. Computer simulation of bounded plasma systems, with external circuits, is discussed in considerable detail. Artificial cooling of trapped electrons in bounded simulations was observed and is now attributed to noiseless injection; the cooling does not occur if random injection is used. This report also deals with Plasma-Wall Physics and Simulation. The collector and source sheaths at the boundaries of warm plasma are treated in detail, including ion reflection and secondary electron emission at the collector. The Kelvin-Helmholtz instability is observed in a self-consistent magnetized sheath, producing long-lived vortices which increase the particle transport to the wall dramatically

  18. Improving the stability of coal slurries: Quarterly progress report for the period December 15, 1986-March 15, 1987. [Adsorption of gum tragacanth on polystyrene latex spheres

    Energy Technology Data Exchange (ETDEWEB)

    Fogler, H.S.

    1987-01-01

    The previous quarterly progress report focusing on the adsorption study of the polystyrene latex spheres with gum tragacanth (GT) indicated that the conformation of GT on the surface of latex spheres plays an important role in the stabilization. To prove this, photon correlation spectroscopy was undertaken, and the steric layer thickness was measured as a function of pH. The results showed that the thickness increases as pH decreases. It is possible that at lower pH the ionization of carboxylic groups is repressed so that GT molecules no longer repel each other and become extended. In addition, the experiments in which pH was lowered showed that the particles which flocculated in the GT solution at higher pH can be deflocculated owing to the increase in the steric layer thickness. 5 refs., 5 figs., 1 tab.

  19. Improving the stability of coal slurries: Quarterly progress report for the period Sep. 15, 1986-Dec. 15, 1986. [Adsorption of gum tragacanth on coal particles

    Energy Technology Data Exchange (ETDEWEB)

    Fogler, H.S.

    1986-01-01

    The last quarterly progress report focused on the adsorption study of the polystyrene latex spheres with gum tragacanth (GT), and the adsorption mechanism was found to be hydrophobic rather than electrostatic. Also, the effect of the amount of GT adsorbed, the bulk concentration of GT, incubation time and pH on the stability factor was examined, and the results indicated that the conformation of GT on the surface of latex spheres plays an important role in the stabilization. This report presents the results of the coal-water slurries, mainly focusing on the adsorption study of GT by changing pH and ionic strength. It was found from the experiment in which the ionic strength was changed that the adsorption of GT on the coal particles is hindered by the coulombic repulsion between GT and coal. In addition, the experiment in which pH was changed also indicated that the adsorption mechanism is electrostatic in nature. 7 refs., 2 figs.

  20. Bench-scale testing of on-line control of column flotation using a novel analyzer. Third quarterly technical progress report, April 1, 1993--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-24

    This document contains the third quarterly technical progress report for PTI`s Bench-Scale Testing Project of a circuit integrating PTI`s KEN-FLOTETM Column Flotation Technology and PTI`s On-Line Quality Monitor and Control System. The twelve-month project involves installation and testing of a 200--300 lb/hr. bench-scale flotation circuit at PETC`s Coal Preparation Process Research Facility (CPPRF) for two bituminous coals (Upper Freeport and Pittsburgh No. 8 Seam Raw Coals). Figure 1 contains the project plan, as well as the approach to completing the major tasks within the twelve-month project schedule. The project is broken down into three phases, which include: Phase I -- Preparation: The preparation phase was performed principally at PTI`s Calumet offices from October through December, 1992. It involved building of the equipment and circuitry, as well as some preliminary design and equipment testing; Phase II -- ET Circuit Installation and Testing: This installation and testing phase of the project was performed at PETC`s CPPRF from January through June, 1993, and was the major focus of the project. It involved testing of the continuous 200--300 lb/hr. circuit; and Phase III -- Project Finalization: The project finalization phase is occurring from July through September, 1993, at PTI`s Calumet offices and involves finalizing analytical work and data evaluation, as well as final project reporting. This Third Quarterly Technical Progress Report principally summarizes the results from the benchscale testing with the second coal (Pittsburgh No. 8 Seam Coal), which occurred in April through June, 1993. It also contains preliminary economic evaluations that will go into the Final Report, as well as the plan for the final reporting task.

  1. Quarterly Technical Progress Report of Radioisotope Power System Materials Production and Technology Program tasks for January 2000 through March 2000

    International Nuclear Information System (INIS)

    Moore, J.P.

    2000-01-01

    The Office of Space and Defense Power Systems (OSDPS) of the Department of Energy (DOE) provides radioisotope Power Systems (BPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of .I 997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVSs) and weld shields (WSs). This quarterly report has been divided into three sections to reflect program guidance from OSDPS for fiscal year (FY) 2000. The first section deals primarily with maintenance of the capability to produce flight quality carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, clad vent sets (CVSs), and weld shields (WSs). In all three cases, production maintenance is assured by the manufacture of limited quantities of flight quality (FQ) components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for two new RPS. The last section is dedicated to studies of the potential for the production of 238Pu at OBNL

  2. Thin film polycrystalline silicon solar cells. Quarterly technical progress report No. 3, 1 April 1980-30 June 1980

    Energy Technology Data Exchange (ETDEWEB)

    Sarma, K. R.; Rice, M. J.; Legge, R.; Ellis, R. J.

    1980-06-01

    During this third quarter of the program, the high pressure plasma (hpp) deposition process has been thoroughly evaluated using SiHCl/sub 3/ and SiCl/sub 4/ silicon source gases, by the gas chromatographic analysis of the effluent gases from the reactor. Both the deposition efficiency and reactor throughput rate were found to be consistently higher for hpp mode of operation compared to conventional CVD mode. The figure of merit for various chlorosilanes as a silicon source gas for hpp deposition is discussed. A new continuous silicon film deposition scheme is developed, and system design is initiated. This new system employs gas interlocks and eliminates the need for gas curtains which have been found to be problematic. Solar cells (2 cm x 2 cm area) with AM1 efficiencies of up to 12% were fabricated on RTR grain enhanced hpp deposited films. The parameters of a 12% cell under simulated AM1 illumination were: V/sub OC/ = 0.582 volts, J/sub SC/ = 28.3 mA/cm/sup 2/ and F.F. = 73.0%.

  3. Silicon ribbon growth by a capillary action shaping technique. Annual report (Quarterly technical progress report No. 9)

    Energy Technology Data Exchange (ETDEWEB)

    Schwuttke, G.H.; Ciszek, T.F.; Kran, A.

    1977-10-01

    Progress on the technological and economical assessment of ribbon growth of silicon by a capillary action shaping technique is reported. Progress in scale-up of the process from 50 mm to 100 mm ribbon widths is presented, the use of vitreous carbon as a crucible material is analyzed, and preliminary tests of CVD Si/sub 3/N/sub 4/ as a potential die material are reported. Diffusion length measurements by SEM, equipment and procedure for defect display under MOS structure in silicon ribbon for lifetime interpretation, and an assessment of ribbon technology are discussed. (WHK)

  4. Seismic margin analysis for Kashiwazaki Kariwa ABWR plant considering the Niigataken Chuetsu-oki earthquake

    International Nuclear Information System (INIS)

    Matsuo, Toshihiro; Nagasawa, Kazuyuki; Kawamura, Shinichi; Ueki, Takashi; Higuchi, Tomokazu; Sakaki, Isao

    2009-01-01

    Seismic Margin Analysis (SMA) study was conducted for Kashiwazaki Kariwa (KK) ABWR representative plant (unit 6). Considering that the installation behaved in a safe manner during and after the Niigataken Chuetsu-oki (NCO) Earthquake which significantly exceeded the level of the seismic input taken into account in the design of the plant, the study to find out how much margin the ABWR plant had toward the same seismic motion was conducted. In this study fragility analyses were conducted for SSCs that were included in the accident sequences and that were considered to have relatively small margin taking EPRI margin analysis method into consideration. In order to calculate plant level seismic margin Min-Max method was adopted. As the result of this study, the plant level High Confidence Low Probability of Failure (HCLPF) acceleration for unit 6 was calculated more than tripled NCO earthquake motion. (author)

  5. Effects of lower plenum flow structure on core inlet flow of ABWR

    International Nuclear Information System (INIS)

    Watanabe, Shun; Abe, Yutaka; Kaneko, Akiko; Watanabe, Fumitoshi; Tezuka, Kenichi

    2010-01-01

    The evaluation of coolant flow structure at a lower plenum of an advanced boiling water reactor (ABWR) in which there are many structures is very important in order to improve generating power. Although the simulation results by CFD (Computational Fluid Dynamics) codes can predict such complicated flow in the lower plenum, it is required to establish the database of flow structure in lower plenum of ABWR experimentally for the benchmark of the CFD codes. In the model of the lower plenum, we measured velocity profiles with LDV and PIV. And differential pressure of constructed model is measured with differential pressure instrument. It was identified that the velocity and differential pressure profiles also showed the tendency to be flat in the core inlet. Moreover, vortexes were observed around side entry orifice by PIV measurement. (author)

  6. Sodium boiling detection in LMFBRs (Phase I). 5th quarterly technical progress report, July 1, 1975--October 31, 1975

    International Nuclear Information System (INIS)

    Albrecht, R.W.; McCormick, N.J.

    1975-01-01

    Progress summarized includes the design of a gamma heated subassembly for sodium boiling experiments and an experiment showing that neutronic noise and acoustic noise caused by sodium boiling are highly correlated in a wide frequency band about the bubble repetition frequency

  7. Contracts for field projects and supporting research on enhanced oil recovery. Progress review No. 71, quarter ending June 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    Progress reports are presented for the following tasks: chemical flooding--supporting research; gas displacement--supporting research; thermal recovery--supporting research; geoscience technology; resource assessment technology; microbial technology; and novel technology. A list of available publication is also provided.

  8. Overview of internal fire hazards aspects of ABWR design for United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Yoshikawa, Kazuhiro; Kawai, Hiroki [Hitachi-GE Nuclear Energy, Ltd., Ibaraki (Japan)

    2015-12-15

    The ABWR (Advanced Boiling Water Reactor) is a generation III+ reactor, the most modern operational generation of nuclear power plants. The UK ABWR design is proposed for development and construction in the United Kingdom (UK), and under review by the Office for Nuclear Regulation (ONR) through Generic Design Assessment (GDA). The UK ABWR design has mainly two types of the safety system: ''preventing'' and ''mitigating'' a fault and their consequences. The prevention of internal hazards starts with design processes and procedures. These processes lead to limiting the sources of potential hazards. The mitigative safety systems are required to ensure the fundamental safety functions (FSFs): control of reactivity, Fuel cooling, long term heat removal, confinement/containment of radioactive materials, and others. Implementation of the safety philosophy is based upon redundant and diverse safety systems that deliver the FSFs. Three mechanical divisions are provided, each of which contains redundant systems, structures, and components (SSCs) capable of carrying out all the FSFs. The safety divisions are separated by robust barriers which act to contain a hazard in an affected division and prevent the spread of the hazard to a different division. The deterministic assessments and the hazard schedule argue that the rooms containing SSCs providing the FSFs are located in different fire safety divisions. The approach to maintaining the FSFs during and after internal fires is to ensure fires do not spread beyond that division to affect redundant equipment in other divisions. During the GDA process, it is demonstrated that generally barrier compartmentation (the divisional barrier walls, ceilings and floors) is sufficient to contain the postulated fires. The UK ABWR design has sufficient capability of withstanding the postulated internal fire hazard to achieve the FSFs. Further development is being undertaken with feedback in the GDA

  9. A characterization and evaluation of coal liquefaction process streams. Quarterly technical progress report, July 1--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Robbins, G.A.; Brandes, S.D.; Winschel, R.A.; Burke, F.P.

    1995-12-01

    The objectives of this project are to support the DOE direct coal liquefaction process development program and to improve the useful application of analytical chemistry to direct coal liquefaction process development. Independent analyses by well-established methods will be obtained of samples produced in direct coal liquefaction processes under evaluation by DOE. Additionally, analytical instruments and techniques which are currently underutilized for the purpose of examining coal-derived samples will be evaluated. The data obtained from this study will be used to help guide current process development and to develop an improved data base on coal and coal liquids properties. A sample bank will be established and maintained for use in this project and will be available for use by other researchers. The reactivity of the non-distillable resids toward hydrocracking at liquefaction conditions (i.e., resid reactivity) will be examined. From the literature and data experimentally obtained, a mathematical kinetic model of resid conversion will be constructed. It is anticipated that such a model will provide insights useful for improving process performance and thus the economics of direct coal liquefaction. Some of the contract activities for this quarter are: We completed many of the analyses on the 81 samples received from HTI bench-scale run CMSL-9, in which coal, coal/mixed plastics, and coal/high density polyethylene were fed; Liquid chromatographic separations of the 15 samples in the University of Delaware sample set were completed; and WRI completed CP/MAS {sup 13}C-NMR analyses on the Delaware sample set.

  10. Validations of BWR nuclear design code using ABWR MOX numerical benchmark problems

    International Nuclear Information System (INIS)

    Takano, Shou; Sasagawa, Masaru; Yamana, Teppei; Ikehara, Tadashi; Yanagisawa, Naoki

    2017-01-01

    BWR core design code package (the HINES assembly code and the PANACH core simulator), being used for full MOX-ABWR core design, has been benchmarked against the high-fidelity numerical solutions as references, for the purpose of validating its capability of predicting the BWR core design parameters systematically from UO 2 to 100% MOX cores. The reference solutions were created by whole core critical calculations using MCNPs with the precisely modeled ABWR cores both in hot and cold conditions at BOC and EOC of the equilibrium cycle. A Doppler-Broadening Rejection Correction (DCRB) implemented MCNP5-1.4 with ENDF/B-VII.0 was mainly used to evaluate the core design parameters, except for effective delayed neutron fraction (β eff ) and prompt neutron lifetime (l) with MCNP6.1. The discrepancies in the results between the design codes HINES-PANACH and MCNPs for the core design parameters such as the bundle powers, hot pin powers, control rod worth, boron worth, void reactivity, Doppler reactivity, β eff and l, are almost within target accuracy, leading to the conclusion that HINES-PANACH has sufficient fidelity for application to full MOX-ABWR core design. (author)

  11. Advanced Turbine Systems (ATS) program conceptual design and product development. Quarterly progress report, December 1, 1995--February 29, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    This report describes the overall program status of the General Electric Advanced Gas Turbine Development program, and reports progress on three main task areas. The program is focused on two specific products: (1) a 70-MW class industrial gas turbine based on the GE90 core technology, utilizing a new air cooling methodology; and (2) a 200-MW class utility gas turbine based on an advanced GE heavy-duty machine, utilizing advanced cooling and enhancement in component efficiency. The emphasis for the industrial system is placed on cycle design and low emission combustion. For the utility system, the focus is on developing a technology base for advanced turbine cooling while achieving low emission combustion. The three tasks included in this progress report are on: conversion to a coal-fueled advanced turbine system, integrated program plan, and design and test of critical components. 13 figs., 1 tab.

  12. Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems. NUCLEAR ENERGY RESEARCH INITIATIVE (NERI) QUARTERLY PROGRESS REPORT

    International Nuclear Information System (INIS)

    Pavel Hejzlar; Peter Yarsky; Mike Driscoll; Dan Wachs; Kevan Weaver; Ken Czerwinski; Mike Pope; James Parry; Marshall, Theron D.; Davis, Cliff B.; Dustin Crawford; Thomas Hartmann; Pradip Saha

    2005-01-01

    This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics; Task C: Plant Design; Task D: Fuel Design The lead PI, Michael J. Driscoll, has consolidated and summarized the technical progress submissions provided by the contributing investigators from all sites, under the above principal task headings

  13. Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems; NUCLEAR ENERGY RESEARCH INITIATIVE (NERI) QUARTERLY PROGRESS REPORT

    Energy Technology Data Exchange (ETDEWEB)

    ERROR, [value too long for type character varying(50); Hejzlar, Pavel; Yarsky, Peter; Driscoll, Mike; Wachs, Dan; Weaver, Kevan; Czerwinski, Ken; Pope, Mike; Parry, James; Marshall, Theron D.; Davis, Cliff B.; Crawford, Dustin; Hartmann, Thomas; Saha, Pradip

    2005-01-31

    This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics; Task C: Plant Design; Task D: Fuel Design The lead PI, Michael J. Driscoll, has consolidated and summarized the technical progress submissions provided by the contributing investigators from all sites, under the above principal task headings.

  14. Contracts for field projects and supporting research on enhanced oil recovery. Progress review number 86, quarter ending March 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    Summaries are presented for 37 enhanced oil recovery contracts being supported by the Department of Energy. The projects are grouped into gas displacement methods, thermal recovery methods, geoscience technology, reservoir characterization, and field demonstrations in high-priority reservoir classes. Each summary includes the objectives of the project and a summary of the technical progress, as well as information on contract dates, size of award, principal investigator, and company or facility doing the research.

  15. Contracts for field projects and supporting research on enhanced oil recovery. Progress review number 83, quarter ending June 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    Summaries of 41 research projects on enhanced recovery are presented under the following sections: (1) chemical flooding; (2) gas displacement; (3) thermal recovery; (4) geoscience technology; (5) resource assessment technology; and (6) reservoir classes. Each presentation gives the title of the project, contract number, research facility, contract date, expected completion data, amount of the award, principal investigator, and DOE program manager, and describes the objectives of the project and a summary of the technical progress.

  16. Quarterly Progress Report for the Chemical and Energy Research Section of the Chemical Technology Division: July-September 1999

    Energy Technology Data Exchange (ETDEWEB)

    Jubin, R.T.

    2001-04-16

    quarter, MSRE Remediation Studies focused on recovery of {sup 233}U and its conversion to a stable oxide and radiolysis experiments to permit remediation of MSRE fuel salt. Investigation of options for final disposition of the {sup 233}U inventory represents a new initiative within this area. In the area of Chemistry Research, activities included studies relative to molecular imprinting for use in areas such as selective sorption, chemical sensing, and catalysis, as well as spectroscopic investigation into the fundamental interaction between ionic solvents and solutes in both low- and high-temperature ionic liquids.

  17. Evaluation of pressure drop across area changes during blowdown. Quarterly progress report for period ending June 30, 1976

    International Nuclear Information System (INIS)

    Weisman, J.

    1976-11-01

    Transient pressure drops across abrupt area changes are being determined in a series of blowdown experiments. These tests are being conducted with Freon 113 as the test fluid in a well instrumented apparatus. During this period, test runs were obtained with the first abrupt expansion test section. Test data from two typical runs are included in this report. Additional progress was made in developing the computer programs which were to be used in analyzing this data but funding of this analytical effort has been suspended

  18. Coal-fired high performance power generating system. Quarterly progress report, July 1, 1993--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This report covers work carried out under Task 3, Preliminary Research and Development, and Task 4, Commercial Generating Plant Design, under contract DE-AC22-92PC91155, {open_quotes}Engineering Development of a Coal Fired High Performance Power Generation System{close_quotes} between DOE Pittsburgh Energy Technology Center and United Technologies Research Center. The goals of the program are to develop a coal-fired high performance power generation system (HIPPS) by the year 2000 that is capable of >47% thermal efficiency; NO{sub x}, SO{sub x}, and particulates {le} 25% NSPS; cost {ge} 65% of heat input; and all solid wastes benign. The report discusses progress in cycle analysis, chemical reactor modeling, ash deposition rate calculations for HITAF (high temperature advanced furnace) convective air heater, air heater materials, and deposit initiation and growth on ceramic substrates.

  19. Design and development of a continuously variable ratio transmission for an automotive vehicle. Phase IV. Quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-05-31

    Progress in the design and development of a continuously variable ratio transmission for an automotive vehicle is reported. The Major automotive hydromechanical transmission development problem continues to be the reduction of hydrostatic noise and the project plan, therefore, concentrated on the new hydrostatic module. The potential for achieving acceptably low noise levels in the second generation hydromechanical transmission is to be assessed by comparing the noise levels of the hydrostatic modules for the first and second generation transmissions. A set of twelve test points was selected comprising of road load steady state and wide-open-throttle acceleration at 10, 20, 30, 40, 50 and 60 mph. The module operating conditions for the two transmissions at each of these twelve points were calculated. Baseline noise data was measured on the first generation module. The results are given testing of co-axial hydrostatic module for second generation hydromechanical transmission will be emphasized. (LCL)

  20. Novel concepts in electrochemical solar cells. Second quarterly progress report, August 15, 1979-October 15, 1979. [Molten salt electrolytes

    Energy Technology Data Exchange (ETDEWEB)

    DuBow, J.; Job, R.; Krishnan, R.; Gale, B.

    1979-01-01

    It is considered that the short term stability of n-GaAs PEC's in a ferrocene-based, ambient temperature molten salt electrolyte is reasonably good. However, longer term evaluation is required to determine the extent and significance of corrosion, stability, etc. Extremely few fundamental studies have been made of the semiconductor/molten salt interphase and experiments in this area would be most useful. Indeed, even the design parameters for PECs of any kind have not been quantitatively delineated and present consideration will be given to models for PEC solar cells and limitations caused by ion transport in the electrolyte. The MoSe/sub 2/ and MoS/sub 2/ electrodes appear to have substrate reproducibility and transport limitations that make them unsuitable candidates for efficient PEC's at this time. Similarly, the lack of availability of high quality CuInSe/sub 2/ and CuInS/sub 2/ substrates limits the quantitative experimental evaluation of their utility for PEC applications. We are presently focusing attention on CdSe/CdTe mixtures and CdS as electrodes as well as Si and GaAs in molten salt and polyelectrolyte solutions. The system for solar cell evaluation and network analysis of substrates and cells was mode operational. Preliminary work on economic and theoretical modelling was begun. Progress is reported. (WHK)

  1. Study of plutonium disposition using the GE Advanced Boiling Water Reactor (ABWR)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-04-30

    The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the U.S. to disposition 50 to 100 metric tons of excess of plutonium in parallel with a similar program in Russia. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing long-term diversion resistance to this material. The NAS study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} identified light water reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a U.S. disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a 1350 MWe GE Advanced Boiling Water Reactor (ABWR) is utilized to convert the plutonium to spent fuel. The ABWR represents the integration of over 30 years of experience gained worldwide in the design, construction and operation of BWRs. It incorporates advanced features to enhance reliability and safety, minimize waste and reduce worker exposure. For example, the core is never uncovered nor is any operator action required for 72 hours after any design basis accident. Phase 1 of this study was documented in a GE report dated May 13, 1993. DOE`s Phase 1 evaluations cited the ABWR as a proven technical approach for the disposition of plutonium. This Phase 2 study addresses specific areas which the DOE authorized as appropriate for more in-depth evaluations. A separate report addresses the findings relative to the use of existing BWRs to achieve the same goal.

  2. ABWR (K-6/7) construction experience (computer-based safety system)

    International Nuclear Information System (INIS)

    Yokomura, T.

    1998-01-01

    TEPCO applied a digital safety system to Kashiwazaki-Kariwa Nuclear Power Station Unit Nos. 6 and 7, the world's first ABWR plant. Although this was the first time to apply a digital safety logic system in Japan, we were able to complete construction of K-6/7 very successfully and without any delay. TEPCO took a approach of developing a substantial amount of experience in digital non- safety systems before undertaking the design of the safety protection system. This paper describes the history, techniques and experience behind achieving a highly reliable digital safety system. (author)

  3. Participation in the ABWR Man-Machine interface design. Applicability to the Spanish Electrical Sector

    International Nuclear Information System (INIS)

    Rodriguez, C.; Manrique Martin, A.; Nunez, J.

    1997-01-01

    Project coordinated by DTN within the advanced reactor programme. Participation in the design activities for the Advanced Boiling Water Reactor (ABWR) man-machine interface was divided into two phases: Phase I: Preparation of drawings for designing, developing and assessing the advanced control room Phase II: Application of these drawings in design activities Participation in this programme has led to the following possible future applications to the electrical sector: 1. Design and implementation of man-machine interfaces 2. Human factor criteria 3. Assessment of man-machine interfaces 4. Functional specification, computerised operating procedures 5. Computerised alarm prototypes. (Author)

  4. Development of advanced concept for shortening construction period of ABWR plant (part 2)

    International Nuclear Information System (INIS)

    Fujita, Tomohiro; Satoh, Takashi

    2003-01-01

    The construction of the first building fully applying SC structure, which is indispensable for shortening construction period of ABWR plants (21.5 months from the first concrete work to fuel loading), has been started since August 2002 in Japan. Before the construction start, a pre-construction test with some actual size SC panels was carried out to confirm the SC modular construction method. The outline of the design and the construction of the first full-SC building and the results of the pre-construction test are reported. (author)

  5. Project SQUID: Quarterly Progress Report

    Science.gov (United States)

    1950-07-01

    JET ENGINES. ( HYU -eÄl) Submitted by» J» Lemeleon^ New York University, No data on the operations of the glass-walled pulse jet have been...It is felt at HYU that a better understanding of the rela- tively simple phenomenon of the Rijke tube is, therefore, essential before headway...tnd combustion, KYTJ-7R6. Lerge amplitude ges vibration theory 19 HyU -7R7. Photo-ignition 1.4 NYU-7R8. Hydrocorbon Fleme Bends 67 i NYU

  6. 3. Quarterly progress report, 1977

    International Nuclear Information System (INIS)

    1977-01-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, undergroung water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

  7. 4. Quarterly progress report, 1978

    International Nuclear Information System (INIS)

    1978-01-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

  8. 4. Quarterly progress report, 1977

    International Nuclear Information System (INIS)

    1977-01-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

  9. 4. Quarterly progress report 1981

    International Nuclear Information System (INIS)

    1981-01-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. the activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

  10. 3. Quarterly progress report 1984

    International Nuclear Information System (INIS)

    1984-01-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, undergroud water, sewage water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables. This report exposes also the state of surveillance and assistance operations on work sites and the state of incidents along the three months; a bibliographic selection is also presented [fr

  11. 3. Quarterly progress report, 1981

    International Nuclear Information System (INIS)

    1981-01-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

  12. 2. Quarterly progress report, 1981

    International Nuclear Information System (INIS)

    1981-01-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radiosotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

  13. 1. Quarterly progress report 1983

    International Nuclear Information System (INIS)

    1983-01-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 58 Co, 60 Co, 134 Cs, 137 Cs, 90 Sr, 106 Ru, K, 54 Mn, U and T). A bibliographic selection is also presented [fr

  14. 2. Quarterly progress report 1982

    International Nuclear Information System (INIS)

    1982-01-01

    The quaterly report of the SCPRI exposes an interpretation of the principal results concerning the survaillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 58 Co, 60 Co, 137 Cs, 125 Sb, 90 Sr, 106 Ru, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

  15. 3. Quarterly progress report, 1983

    International Nuclear Information System (INIS)

    1983-07-01

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

  16. CORE DESIGNS OF ABWR FOR PROPOSED OF THE FIRST NUCLEAR POWER PLANT IN INDONESIA

    Directory of Open Access Journals (Sweden)

    Yohannes Sardjono

    2015-04-01

    Full Text Available Indonesia as an archipelago has been experiencing high growth industry and energy demand due to high population growth, dynamic economic activities. The total population is around 230 million people and 75 % to the total population is living in Java. The introduction of Nuclear Power Plant on Java Bali electricity grid will be possible in 2022 for 2 GWe, using proven technology reactor like ABWR or others light water reactor with nominal power 1000 MWe. In this case, the rated thermal power for the equilibrium cycles is 3926 MWt, the cycle length is 18 month and overall capacity factor is 87 %. The designs were performed for an 872-fuel bundles ABWR core using GE-11 fuel type in an 9×9 fuel rod arrays with 2 Large Central Water Rods (LCWR. The calculations were divided into two steps; the first is to generate bundle library and the other is to make the thermal and reactivity limits satisfied for the core designs. Toshiba General Electric Bundle lattice Analysis (TGBLA and PANACEA computer codes were used as designs tools. TGBLA is a General Electric proprietary computer code which is used to generate bundle lattice library for fuel designs. PANACEA is General Electric proprietary computer code which is used as thermal hydraulic and neutronic coupled BWR core simulator. This result of core designs describes reactivity and thermal margins i.e.; Maximum Linear Heat Generation rate (MLHGR is lower than 14.4 kW/ft, Minimum Critical Power Ratio (MCPR is upper than 1.25, Hot Excess Reactivity (HOTXS is upper than 1 %Dk at BOC and 0.8 %Dk at 200 MWD/ST and Cold Shutdown Margin Reactivity (CSDM is upper than 1 %Dk. It is concluded that the equilibrium core design using GE-11 fuel bundle type satisfies the core design objectives for the proposed of the firs Indonesia ABWR Nuclear Power Plant. Keywords: The first NPP in Indonesia, ABWR-1000 MWe, and core designs.   Indonesia adalah sebagai negara kepulauan yang laju pertumbuhan industri, energi, penduduk

  17. Development of automated ultrasonic device for in-service inspection of ABWR pressure vessel bottom head

    International Nuclear Information System (INIS)

    Kojima, Y.; Matsuyama, A.

    1995-01-01

    An automated device and its controller have been developed for the bottom head weld examination of pressure vessel of Advanced Boiling Water Reactor (ABWR). The internal pump casings and the housings of control rod prevent a conventional ultrasonic device from scanning the required inspection zone. With this reason, it is required to develop a new device to examine the bottom head area of ABWR. The developed device is characterized by the following features. (1) Composed of a mother vehicle and a compact inspection vehicle. They are connected only by an electric wire without using the conventional arm mechanism. (2) The mother vehicle travels on a track and lift up the inspection vehicle to the vessel. (3) The mother vehicle can automatically attach the inspection vehicle to the bottom head, and detach the inspection vehicle from it. (4) Collision avoidance control function with a touch sensor is installed at the front of the inspection vehicle. The device was successfully demonstrated using a mock-up of reactor pressure vessel

  18. Advanced plant engineering and construction of Japanese ABWRs

    International Nuclear Information System (INIS)

    Gotoh, N.; Sumikawa, J.; Yoshida, N.; Yoshida, M.

    1998-01-01

    Remarkable improvement has been made in recent nuclear power plant design and construction in Japan. These many improved engineering technologies has been made a good use in the lately commercial operated two world's first 1,356MWe ABW's (Advanced Boiling Water Reactors), and made a great contribution to the smooth progress and the completion of a highly reliable plant construction. Especially, two engineering technologies, (1), three-dimensional computer aided design system through engineering data-base, and (2), large scale modularising construction method, have been successfully applied as the integrated engineering technologies of the plant construction. And two integrated reviews, 'integrated design review, confirmation of new and changed design and prevention of failure recurrence' in the design stage, and 'constructing plant review' at the site, have been widely and systematically conducted as a link in the chain of steady reliability improvement activities. These advanced and/or continuous and steady technologies are one of most important factors for high reliability through the entire lifetime of a nuclear plant, including planning, design, construction, operation and maintenance stages. (author)

  19. Shippingport Atomic Power Station. Quarterly operating report, third quarter 1978

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1978-01-01

    A loss of ac power to the station occurred on July 28, 1978 caused by an interaction between Beaver Valley Power Station and Shippingport Atomic Power Station when the main transformer of Unit No. 1 of the Beaver Valley Power Station developed an internal failure and tripped the BVPS. Two environmental studies were continued this quarter. The first involves reduction of main unit condenser chlorination and the second, river intake screen fish impingement sampling. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. During the third quarter of 1978, 874 cubic feet of radioactive solid waste was shipped out of state for burial. At the end of the quarter, the Fall shutdown continued with the plant heated up, the main turbine on turning gear and plant testing in progress prior to Station startup.

  20. A passive decay-heat removal system for an ABWR based on air cooling

    Energy Technology Data Exchange (ETDEWEB)

    Mochizuki, Hiroyasu, E-mail: mochizki@u-fukui.ac.jp [Research Institute of Nuclear Engineering, University of Fukui, 1-2-4 Kanawa-cho, Tsuruga, Fukui 914-0055 (Japan); Yano, Takahiro [School of Engineering, University of Fukui, 1-2-4 Kanawa-cho, Tsuruga, Fukui 914-0055 (Japan)

    2017-01-15

    Highlights: • A passive decay heat removal system for an ABWR is discussed using combined system of the reactor and an air cooler. • Effect of number of pass of the finned heat transfer tubes on heat removal is investigated. • The decay heat can be removed by air coolers with natural convection. • Two types of air cooler are evaluated, i.e., steam condensing and water cooling types. • Measures how to improve the heat removal rate and to make compact air cooler are discussed. - Abstract: This paper describes the capability of an air cooling system (ACS) operated under natural convection conditions to remove decay heat from the core of an Advanced Boiling Water Reactor (ABWR). The motivation of the present research is the Fukushima Severe Accident (SA). The plant suffered damages due to the tsunami and entered a state of Station Blackout (SBO) during which seawater cooling was not available. To prevent this kind of situation, we proposed a passive decay heat removal system (DHRS) in the previous study. The plant behavior during the SBO was calculated using the system code NETFLOW++ assuming an ABWR with the ACS. However, decay heat removal under an air natural convection was difficult. In the present study, a countermeasure to increase heat removal rate is proposed and plant transients with the ACS are calculated under natural convection conditions. The key issue is decreasing pressure drop over the tube banks in order to increase air flow rate. The results of the calculations indicate that the decay heat can be removed by the air natural convection after safety relief valves are actuated many times during a day. Duct height and heat transfer tube arrangement of the AC are discussed in order to design a compact and efficient AC for the natural convection mode. As a result, a 4-pass heat transfer tubes with 2-row staggered arrangement is the candidate of the AC for the DHRS under the air natural convection conditions. The heat removal rate is re-evaluated as

  1. Lungmen ABWR containment analyses during short-term main steam line break LOCA using GOTHIC

    International Nuclear Information System (INIS)

    Chen, Yen-Shu; Yuann, Yng-Ruey; Dai, Liang-Che

    2012-01-01

    Highlights: ► The Lungmen ABWR containment responses due to the main steam line break are analyzed. ► In the Lungmen FSAR, the peak drywell temperature is greater than the designed value. ► GOTHIC is used to calculate the containment responses in this study. ► With more realistic conditions, the drywell temperature can be reasonably suppressed. - Abstract: Lungmen Nuclear Power Plant in Taiwan is a GE-designed twin-unit Advanced Boiling Water Reactor (ABWR) plant with rated thermal power of 3926 MWt. Both units are currently under construction. In the Lungmen Final Safety Analysis Report (FSAR) section 6.2, the calculated peak drywell temperature during the short-term Main Steam Line Break (MSLB) event is 176.3 °C, which is greater than the designed temperature of 171.1 °C. It resulted in a controversial issue in the FSAR review process conducted by the Atomic Energy Council in Taiwan. The purpose of this study is to independently investigate the Lungmen ABWR containment pressure and temperature responses to the MSLB using the GOTHIC program. Blowdown conditions are either calculated by using a simplified reactor vessel volume in GOTHIC model, or provided by the RELAP5 transient analysis. The blowdown flow rate from the steam header side is calculated with a more reasonable pressure loss coefficient of the open main steam isolation valves, and the peak drywell temperature is then reduced. By using the RELAP5 blowdown data, the peak drywell temperature can be further reduced because of the initial liquid entrainment in the blowdown flow. The drywell space is either treated as a single volume, or separated into a upper drywell and a lower drywell to reflect the real configuration of the Lungmen containment. It is also found that a single drywell volume may not present the overheating of the upper drywell. With more realistic approaches and assumptions, the drywell temperature can be reasonably below the design value and the Lungmen containment integrity

  2. ABWR1. A Generation III.7 reactor after the Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Sato, Takashi; Matsumoto, Keiji; Kurosaki, Toshikazu; Taguchi, Keisuke

    2015-01-01

    iB1350 stands for an innovative, intelligent and inexpensive BWR 1350. It is the first Generation III.7 reactor after the Fukushima Daiichi accident. It has incorporated lessons learned from the Fukushima Daiichi accident and WENRA safety objectives. It has innovative safety to cope with devastating natural disasters including a giant earthquake, a large tsunami and a monster hurricane. The iB1350 can survive passively such devastation and a very prolonged SBO without any support from the outside of a site up to 7 days even preventing core melt. It, however, is based on the well-established proven ABWR design. The NSSS is exactly the same as that of the current ABWR. As for safety design it has a double cylinder RCCV (Mark W containment) and an in-depth hybrid safety system (IDHS). The Mark W containment has double FP confinement barriers and the in-containment filtered venting system (IFVS) that enable passively no emergency evacuation outside the immediate vicinity of the plant for a SA. It has a large volume to hold hydrogen, a core catcher, a passive flooding system and an innovative passive containment cooling system (iPCCS) establishing passively practical elimination of containment failure even in a long term. The IDHS consists of 4 division active safety systems for a DBA, 2 division active safety systems for a SA and built-in passive safety systems (BiPSS) consisting of an isolation condenser (IC) and the iPCCS for a SA. The IC/PCCS pools have enough capacity for 7 day grace period. The IC/PCCS heat exchangers, core and spent fuel pool are enclosed inside the CV building and protected against a large airplane crash. The iB1350 can survive a large airplane crash only by the CV building and the built-in passive safety systems therein. The dome of the CV building consists of a single wall made of steel and concrete composite. This single dome structure facilitates a short-term construction period and cost saving. The CV diameter is smaller than that of most

  3. MELCOR 1.8.2 calculations of selected sequences for the ABWR

    International Nuclear Information System (INIS)

    Kmetyk, L.N.

    1994-07-01

    This report summarizes the results from MELCOR calculations of severe accident sequences in the ABWR and presents comparisons with MAAP calculations for the same sequences. MELCOR was run for two low-pressure and three high-pressure sequences to identify the materials which enter containment and are available for release to the environment (source terms), to study the potential effects of core-concrete interaction, and to obtain event timings during each sequence; the source terms include fission products and other materials such as those generated by core-concrete interactions. Sensitivity studies were done on the impact of assuming limestone rather than basaltic concrete and on the effect of quenching core debris in the cavity compared to having hot, unquenched debris present

  4. Design features which mitigate severe accident challenges in the GE ABWR and SBWR

    International Nuclear Information System (INIS)

    Buchholz, Carol E.

    2004-01-01

    A reduction of the requirements for the emergency planning zone (EPZ) is a goal of advanced light water reactors. The technical basis for reducing the EPZ requirements is based on a very low frequency of a severe accident and high confidence that the offsite dose would be low even if a severe accident was to occur. Design features have been included in both the ABWR and SBWR to ensure that both of these goals are achieved. Probabilistic Risk Assessments (PRAs) have been performed for both plants. The PRAs indicate a core damage frequency on the order of IE-7 for both plants. The PRAs also show that the containments will not fail even if a severe accident should occur. The potential offsite is extremely low. (author)

  5. Commercial operation and outage experience of ABWR at Kashiwazaki-Kariwa units Nos. 6 and 7

    International Nuclear Information System (INIS)

    Anahara, N.; Yamada, M.; Kataoka, H.

    2000-01-01

    Kashiwazaki-Kariwa Nuclear Power Station Units Nos. 6 and 7, the world's first ABWRs (Advanced Boiling Water Reactor), started commercial operation on November 7, 1996 and July 2, 1997, respectively, and continued their commercial operation with a high capacity factor, low occupational radiation exposure and radioactive waste. Units 6 and 7 were in their 3rd cycle operation until 25th April 1999 and 1st November 1999, respectively. Thermal efficiency was 35.4-35.8% (design thermal efficiency: 34.5%) during these period, demonstrating better performance than that of BWR-5 (design thermal efficiency: 33.4%). Nos. 6 and 7 have experienced 2 annual outages. The first outage of unit No. 6 started on November 20, 1997 and was completed within 61 days (including 6 New Year holidays), and the second outage started on March 13, 1999 and was completed within 44 days. The first annual outage of unit No. 7 started on May 27, 1998, earlier than it would normally have been, to avoid an annual outage during the summer, and was completed within 55 days, and the second outage started on September 18th, 1999 and was completed within 45 days, All annual outages were carried out within a very short time period without any severe malfunctions, including newly designed ABWR systems and equipment. As the first outage in Japan, 55 days is a very short period, despite the fact that the Nos. 6 and 7 are the first ABWRs in the world and the largest capacity units in Japan. The total occupational radiation exposure of No. 6 was 300 man-mSv (1st outage) and 331 man-mSv (2nd outage). That of Unit 7 was 153 man-mSv (1st outage) Those of unit No. 6 were at the same level as those of unit No. 3, which is the latest design 1100MW(e) BWR-5. That of unit No. 7 was the lowest ever at Kashiwazaki-Kariwa nuclear power station. The drums of radioactive waste discharged during the annual outage numbered 54 (1st outage) for No. 6 and 62 (1st outage) for No. 7, which was less than the design target of 100

  6. Contracts for field projects and supporting research on enhanced oil recovery, October--December 1992. Progress review No. 73, quarter ending December 31, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    Accomplishments for this quarter ending December 31, 1992 are presented for the following tasks: chemical flooding--supporting research; gas displacement--supporting research; thermal recovery--supporting research; geoscience technology; resource assessment technology; microbial technology; reservoir classes; and novel technology.

  7. Contracts for field projects and supporting research on enhanced oil recovery, July--September 1992. Progress review No. 72, quarter ending September 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    Accomplishments for the past quarter are presented for the following tasks: Chemical flooding--supporting research; gas displacement--supporting research; thermal recovery--supporting research; geoscience technology; resource assessment technology; microbial technology; and novel technology. A list of available publication is also provided.

  8. Study of Education Satellite Communication Demonstration. Second Quarterly Progress Report. Report of Activities and Accomplishments, October 11, 1974 to January 10, 1975.

    Science.gov (United States)

    Syracuse Univ. Research Corp., NY. Educational Policy Research Center.

    A second quarterly report describes activities of the Syracuse Educational Policy Research Center's two-year analysis of educational satellites and telecommunications. Visits to Rocky Mountain, Appalachian and Alaskan sites are described. Activities of other nations are reviewed and summarized. Preliminary staff work and analysis for the final…

  9. Study of Education Satellite Communication Demonstration. Third Quarterly Progress Report. Report of Activities and Accomplishments January 11, 1975 to April 10, 1975.

    Science.gov (United States)

    Syracuse Univ. Research Corp., NY. Educational Policy Research Center.

    A report on the Education Satellite Communication Demonstration (ESCD) describes activities of the evaluators during the first quarter of 1975, including staff trips and site visits and activities of various staff members. A calendar of future events in satellites, telecommunications, and education is included, with revision on dates and new…

  10. Development of Advanced Concept for Shortening Construction Period of ABWR Plant

    International Nuclear Information System (INIS)

    Hiroshi Ijichi; Toshio Yamashita; Masahiro Tsutagawa; Hiroya Mori; Nobuaki Ooshima; Jun Miura; Minoru Kanechika; Nobuaki Miura

    2002-01-01

    Construction of a nuclear power plant (NPP) requires a very long period because of large amount of construction materials and many issues for negotiation among multiple sections. Shortening the construction period advances the date of return on an investment, and can also result in reduced construction cost. Therefore, the study of this subject has a very high priority for utilities. We achieved a construction period of 37 months from the first concrete work to fuel loading (F/L) (51.5 months from the inspection of the foundation (I/F) to the start of commercial operation (C/O)) at the Kashiwazaki-Kariwa NPPs No. 6 and 7 (KK-6/7), which are the first ABWR plants in the world. At TEPCO's next plant, we think that a construction period of less than 36 months (45 months from I/F to C/O) can be realized based on conventional methods such as early start of equipment installation and blocking of equipment to be brought in advance. Furthermore, we are studying the feasibility of a 21.5-month construction period (30 months from I/F to C/O) with advanced ideas and methods. The important concepts for a 21.5-month construction period are adoption of a new building structure that is the steel plate reinforced concrete (SC) structure and promotion of extensive modularization of equipment and building structure. With introducing these new concepts, we are planning the master schedule (M/S) and finding solutions to conflicts in the schedule of area release from building construction work to equipment installation work (schedule-conflicts.) In this report, we present the shortest construction period and an effective method to put it into practice for the conventional general arrangement (GA) of ABWR. In the future, we will continue the study on the improvement of building configuration and arrangements, and make clear of the concept for large composite modules of building structures and equipment. (authors)

  11. Trend chart: wind power. Forth quarter 2016

    International Nuclear Information System (INIS)

    Coltier, Yves

    2017-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the forth quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  12. Trend chart: wind power. First quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-05-01

    This publication presents the wind energy situation of continental France and overseas territories during the first quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  13. Trend chart: wind power. Second quarter 2017

    International Nuclear Information System (INIS)

    2017-08-01

    This publication presents the wind energy situation of continental France and overseas territories during the second quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  14. Trend chart: wind power. Fourth quarter 2017

    International Nuclear Information System (INIS)

    Moreau, Sylvain

    2018-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the fourth quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  15. Trend chart: wind power. Third quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  16. Trend chart: wind power. Second quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-08-01

    This publication presents the wind energy situation of continental France and overseas territories during the second quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  17. Trend chart: wind power. Third quarter 2017

    International Nuclear Information System (INIS)

    2017-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  18. Trend chart: wind power. First quarter 2017

    International Nuclear Information System (INIS)

    2017-05-01

    This publication presents the wind energy situation of continental France and overseas territories during the first quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  19. Trend chart: wind power. Forth quarter 2015

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the forth quarter 2015: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  20. Trend chart: wind power. Third quarter 2015

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2015-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2015: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  1. Post waterflood CO2 miscible flood in light oil fluvial - dominated deltaic reservoirs. Technical progress report, October 1, 1994--December 30, 1994. 1st Quarter, fiscal year 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-01-15

    Production is averaging about 450 BOPD for the quarter. The fluctuation was primarily due to a temporary shutdown of CO{sub 2} delivery and maturing of the first WAG cycle. CO{sub 2} and water injection were reversed again in order to optimize changing yields and water cuts in the producing wells. Measured BHP was close to the anticipated value. A limited CO{sub 2} volume of 120 MMCF was injected to stimulate well Kuhn No. 6 to test the Huff-Puff process, since the well did not respond to CO{sub 2} injection from the main reservoir. The well will be placed on February 1, 1995. Total CO{sub 2} injection averaged this quarter about 8.8 MMCFD, including 3.6 MMCFD purchased CO{sub 2} from Cardox. The stratigraphy of the sand deposits is also discussed.

  2. Occidental vertical modified in situ process for the recovery of oil from oil shale. Phase II. Quarterly progress report, September 1, 1980-November 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    The major activities at OOSI's Logan Wash site during the quarter were: mining the voids at all levels for Retorts 7 and 8; blasthole drilling; tracer testing MR4; conducting the start-up and burner tests on MR3; continuing the surface facility construction; and conducting Retorts 7 and 8 related Rock Fragmentation tests. Environmental monitoring continued during the quarter, and the data and analyses are discussed. Sandia National Laboratory and Laramie Energy Technology Center (LETC) personnel were active in the DOE support of the MR3 burner and start-up tests. In the last section of this report the final oil inventory for Retort 6 production is detailed. The total oil produced by Retort 6 was 55,696 barrels.

  3. A study on transient heat transfer of the EU-ABWR external core catcher using the phase-change effective convectivity model

    International Nuclear Information System (INIS)

    Tran Chi Thanh; Nguyen Viet Hung; Tahara, Mika; Kojima, Yoshihiro; Hamazaki, Ryoichi; Kudinov, Pavel

    2015-01-01

    In advanced designs of Nuclear Power Plants (NPPs), for mitigation of severe accident consequences, on the one hand, the In-Vessel Retention (IVR) concept has been implemented. On the other hand in other new NPP designs (Generation III and III+) with large power reactors, the External Core Catcher (ECC) has been widely adopted. Assessment of ECC design robustness is largely based on analysis of heat transfer of a melt pool formed in the ECC. Transient heat transfer analysis of an ECC is challenging due to (i) uncertainty in the in-vessel accident progression and subsequent vessel failure modes; (ii) long transient, (iii) high Rayleigh number and complex flows involving phase change of the melt pool formed in an ECC. The present paper is concerned with analysis of transient melt pool heat transfer in the ECC of new Advanced Boiling Water Reactor (ABWR) designed by Toshiba Corporation (Japan). According to the ABWR severe accident management strategy, the ECC is initially dry. In order to prevent steam explosion flooding is initiated after termination of melt relocation from the vessel. The ECC full of melt is cooled from the top directly by water and from the bottom through the ECC walls. In order to assess sustainability of the ECC, heat transfer simulation of a stratified melt pool formed in the ECC is carried out. The problem addressed in this work is heat flux distribution at ECC boundaries when cooling is applied (i) from the bottom, (ii) from the top and from the bottom. To perform melt pool heat transfer simulation, we employ Phase-change Effective Convectivity Model (PECM) which was originally developed as a computationally efficient, sufficiently accurate, 2D/3D accident analysis tools for simulation of transient melt pool heat transfer in the reactor lower plenum. Thermal loads from the melt pool to ECC boundaries are determined for selected ex-vessel accident scenarios. Performance of the ECC, efficiency of severe accident management (SAM) measures and

  4. Research on instability design method without occurring boiling transition for hyper ABWR plants of extended core power density

    International Nuclear Information System (INIS)

    Okamoto, T.; Hotta, A.; Ama, T.

    2008-01-01

    The hyper ABWR (Advanced Boiling Water Reactor) project aims to develop an advanced BWR concept that is competitive in the global market with both highly economic and safety features. Expecting plant construction within the coming ten years, a research program for substantiating the basic design of a high core power density ABWR was conducted. By inheriting the conventional ABWR design, it is possible to reduce construction costs. In order to achieve the rated core power of over 1650MWe which is almost equivalent to that of the EPR (European Pressurized Water Reactor), the core power density of ABWR will be up-rated by at least 25%. Three key subjects linked to this target were recognized. They are, (1) fuel design applicable to the high power density core, (2) improvement of the evaluation method for the coupled neutronic and thermal-hydraulic instability under a wider power-flow operating range, and (3) improvement of the steam separator performance under high quality conditions. In this paper, the second subject has been focused on. In the second subject, the uncertainty approach was introduced in the instability analysis where the best-estimate plant simulator was combined with a direct prediction of boiling transition by the sub-channel code. By employing the CSAU like method, a safety evaluation system that enables to include influences of uncertainties has been developed. Based on the correlation between the time margin for reaching the boiling transition under power oscillations and the decay ratio in the power-flow operation map, an automatic power oscillation suppressing system was designed. The set-point for activating suppression mechanisms (i.e. scram or SRI) could be determined based on this correlation. It was proposed that the present conservative acceptance criterion of the deterministic decay ratio can be replaced with a more rational one of the time margin with including uncertainties. (author)

  5. Enforcement actions: Significant actions resolved, material licensees (non-medical). Quarterly progress report, July--September 1994: Volume 13, Number 3, Part 3

    International Nuclear Information System (INIS)

    1994-12-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (July--September 1994) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to material licensees (non-medical) with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated the managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  6. Enforcement actions: Significant actions resolved material licensees (non-medical). Volume 14, No. 1, Part 3, Quarterly progress report, January--March 1995

    International Nuclear Information System (INIS)

    1995-05-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (January--March 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to Material Licensees (non-Medical) with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  7. Enforcement actions: Significant actions resolved material licensees (non-medical). Volume 14, No. 1, Part 3, Quarterly progress report, January--March 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (January--March 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to Material Licensees (non-Medical) with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.

  8. Tulane/Xavier University hazardous materials in aquatic environments of the Mississippi River basin. Quarterly progress report, January 1--March 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-17

    The objectives of this report are to provide the necessary administrative support to assure that the scientific and educational goals of the project are obtained and to assure that all Department of Energy reporting requirements and requests are fulfilled. The grant reporting is divided into three aspects: Collaborative Cluster projects, Initiation projects and Education projects. A cluster project is one or more closely related collaborative, multidisciplinary research projects in which a group of investigators employs a synergistic approach to the solution of problems in the same general area of research. The accomplishments this quarter of eleven cluster projects are presented. An initial project typically involves a single investigator. The purpose of the project is to undertake pilot work, lasting no more than one year, which will lead to the successful submission of an externally-funded proposal or the development of a collaborative cluster project. The accomplishments this quarter of eleven initiation projects are presented. The education projects are designed to develop courses with emphasis on environmental studies and/or to train students in areas of environmental research.

  9. The development and assessment of TRACE/PARCS model for Lungmen ABWR

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Hao-Tzu, E-mail: htlin@iner.gov.tw [Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C., 1000, Wenhua Road, Jiaan Village, Longtan Township, Taoyuan County, 32546, Taiwan, ROC (China); Wang, Jong-Rong, E-mail: jrwang@iner.gov.tw [Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C., 1000, Wenhua Road, Jiaan Village, Longtan Township, Taoyuan County, 32546, Taiwan, ROC (China); Chen, Hsiung-Chih, E-mail: km8385@gmail.com [Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang Fu Road, HsinChu 30013, Taiwan, ROC (China); Shih, Chunkuan, E-mail: ckshih@ess.nthu.edu.tw [Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang Fu Road, HsinChu 30013, Taiwan, ROC (China)

    2014-07-01

    Highlights: • The development of a TRACE/PARCS model of Lungmen (ABWR). • Thermal-hydraulics model of TRACE is coupling with 3-D neutronics model of PARCS. • The 3-D geometry vessel component of TRACE is used in this study. • The parameters responses of Lungmen TRACE/PARCS model are consistent with FSAR data. - Abstract: This study consists of two steps. The first step is the development of a TRACE (TRAC/RELAP Advanced Computational Engine)/PARCS (Purdue Advanced Reactor Core Simulator) model of Lungmen nuclear power plant (NPP) which includes the vessel, reactor internal pumps (RIPs), main steam lines, and important control systems (such as the feedwater control system, steam bypass and pressure control system, and recirculation flow control system), etc. Key parameters were identified to refine the TRACE/PARCS model further in the frame of a steady state analysis. The second step is the performance of Lungmen NPP TRACE/PARCS model transient analyses. The transient data of Final Safety Analysis Report (FSAR) chapter 15th were used to compare with the results of Lungmen NPP TRACE/PARCS model. The trends of TRACE/PARCS analysis results were consistent with the FSAR data. It indicated that there was a respectable accuracy in the Lungmen NPP TRACE/PARCS model and it also depicted that the Lungmen NPP TRACE/PARCS model was satisfying for the purpose of Lungmen NPP safety analyses.

  10. Effect of automatic recirculation flow control on the transient response for Lungmen ABWR plant

    Energy Technology Data Exchange (ETDEWEB)

    Tzang, Y.-C., E-mail: yctzang@aec.gov.t [National Tsing Hua University, Department of Engineering and System Science, Hsinchu 30013, Taiwan (China); Chiang, R.-F.; Ferng, Y.-M.; Pei, B.-S. [National Tsing Hua University, Department of Engineering and System Science, Hsinchu 30013, Taiwan (China)

    2009-12-15

    In this study the automatic mode of the recirculation flow control system (RFCS) for the Lungmen ABWR plant has been modeled and incorporated into the basic RETRAN-02 system model. The integrated system model is then used to perform the analyses for the two transients in which the automatic RFCS is involved. The two transients selected are: (1) one reactor internal pump (RIP) trip, and (2) loss of feedwater heating. In general, the integrated system model can predict well the response of key system parameters, including neutron flux, steam dome pressure, heat flux, RIP flow, core inlet flow, feedwater flow, steam flow, and reactor water level. The transients are also analyzed for manual RFCS case, between the automatic RFCS and the manual RFCS cases, comparisons of the transient response for the key system parameter show that the difference of transient response can be clearly identified. Also, the results show that the DELTACPR (delta critical power ratio) for the transients analyzed may not be less limiting for the automatic RFCS case under certain combination of control system settings.

  11. Development of ABWR inertia-increased reactor internal pump and thicker sleeve nozzle

    International Nuclear Information System (INIS)

    Takahashi, Shirou; Shiina, Kouji; Matsumura, Seiichi

    2002-01-01

    The conventional reactor internal pumps (RIPs) in the ABWR have an inertia moment coming from the shafts and Motor-Generator sets, enabling the RIPs to continue running for a few seconds, when a trip of all RIPs event occurs. It is possible to simplify the RIPs' power supply system without affecting the core flow supply when the above event occurs by eliminating M-G sets, if the rotating inertia is increased. This inertia increase due to an additional flywheel, which leads to gains in weight and length, requires the larger diameter nozzle with the thicker sleeve. However, too large a nozzle diameter may change the hydraulic performance. In authors' previous study, the optimum nozzle diameter (492 mm) was selected through 1/5-scale test. In this study, the 492 mm nozzle and the inertia-increased RIP were verified through the full-scale tests. The rotating inertia time constant on coastdown characteristics (behavior of the RIP speed in the event of power loss) for the inertia-increased RIP doubled compared with the current RIP. The casing and the shaft vibration were also confirmed to satisfy the design criteria. Moreover, hydraulic performance and heat increase in the motor casing due to the flywheel were evaluated. The inertia increased RIP with the 492 mm nozzle maintained good performance. (author)

  12. Hazardous materials in aquatic environments of the Mississippi River Basin Project management. Technical quarterly progress report, April 1, 1996--June 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    McLachlan, J.; Ide, C.F.; O`Connor, S.

    1996-08-01

    This quarterly report summarizes accomplishments for the Project examining hazardous materials in aquatic environments of the Mississippi River Basin. Among the many research areas summarized are the following: assessment of mechanisms of metal-induced reproductive toxicity in aquatic species as a biomarker of exposure; hazardous wastes in aquatic environment;ecological sentinels of aquatic contamination in the lower Mississippi River System; remediation of selected contaminants; rapid on-site immunassay for heavy metal contamination; molecular mechanisms of developmental toxicity induced by retinoids and retinoid-like molecules; resuseable synthetic membranes for the removal of aromatic and halogenated organic pollutants from waste water; Effects of steroid receptor activation in neurendocrine cell of the mammalian hypothalamus; modeling and assessment of environmental quality of louisiana bayous and swamps; enhancement of environmental education. The report also contains a summary of publications resulting from this project and an appendix with analytical core protocals and target compounds and metals.

  13. Tulane/Xavier Universities hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly progress report, October 1, 1995--December 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    To provide the necessary administrative support to assure that the scientific and educational goals of the project are obtained and to assure that all Department of Energy reporting requirements and requests are fulfilled.The grant reporting is divided into three aspects: Collaborative Cluster projects, Initiation projects and Education projects. A cluster project is one or more closely related collaborative, multidisciplinary research projects in which a group of investigators employs a synergistic approach to the solution of problems in the same general area of research. An initiation project typically involves a single investigator. The purpose of the project is to undertaken pilot work, lasting no more than one year, which will lead to the successful submission of an externally-funded proposal or the development of a collaborative cluster project. The education projects are designed to develop courses with emphasis on environmental studies and/or to train students in areas of environmental research. Accomplishments this quarter are: (1) Issued a request for proposals (RFP) to complete work during the next year of the project. Forty-two proposals were received in response to the RFP. (2) Selected and convened a panel of experts to review the proposals and make funding recommendations. (3) Assigned each proposal to two or more reviewers and sent copies of all proposals to each review panelist. (4) Interfaced with Oak Ridge National Laboratory regarding QA/QC issues related to sampling and analysis for the project. (5) Held numerous phone conversations with DOE representatives regarding funding allocations procedure changes as a result of the delays in the Federal budget and appropriations process this year. This quarterly report briefly describes research projects ongoing in this program.

  14. Design and development of a continuously variable ratio transmission for an automotive vehicle, Phase IV. Quarterly progress report, December 1977--February 1978

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-02-28

    Progress in developing and testing a continuously variable ratio hydraulic transmission unit for automobiles is reported. Major emphasis was placed on the development of a co-axial hydrostatic module.

  15. Application of integrated reservoir management and reservoir characterization to optimize infill drilling. Quarterly progress report, June 13, 1995--September 12, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Pande, P.K.

    1995-09-12

    At this stage of the reservoir characterization research, the main emphasis is on the geostatistics and reservoir simulation. Progress is reported on geological analysis, reservoir simulation, and reservoir management.

  16. Study on high performance MOX fuel and core design in full MOX ABWR(1) by GNF-J

    International Nuclear Information System (INIS)

    Izutsu, Sadayuki; Goto, Daisuke; Saeki, Jun; Kokubun, Takehiro; Yokoya, Jun

    2003-01-01

    The concepts of high-performance MOX fuel using 10x10 lattices suitable for full-MOX ABWR are shown in this paper, in which average discharge exposure is extended up to 45 GWd/t with heavy-metal inventory increased over current MOX, reducing the number of refueling bundles, resulting in fuel cycle cost reduction and core performance satisfaction. Also, the increase of Pu inventory is taken into account from the viewpoint to extend the flexibility of MOX fuel utilization. (author)

  17. Post waterflood CO{sub 2} miscible flood in light oil fluvial dominated deltaic reservoirs. Second quarterly technical progress report, [January 1, 1995--March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    Production from the Marg Area 1 at Port Neches is averaging 392 barrels of oil per day (BOPD) for this quarter. The production drop is due to fluctuation in both GOR and BS&W on various producing well, coupled with low water injectivity in the reservoir. We were unable to inject any tangible amount of water in the reservoir since late January. Both production and injection problems are currently being evaluated to improve reservoir performance. Well Kuhn (No. 6) was stimulated with 120 MMCF of CO{sub 2}, and was placed on production in February 1, 1995. The well was shut in for an additional month after producing dry CO{sub 2} initially. The well was opened again in early April and is currently producing about 40 BOPD. CO{sub 2} injection averaged 11.3 MMCFD including 4100 MMCFD purchased from Cardox, while water injection averaged 1000 BWPD with most of the injection occurring in the month of January.

  18. Progress toward the development of a ground-water velocity model for the radioactive waste management facility, Savannah River Plant, South Carolina: Quarterly report

    International Nuclear Information System (INIS)

    Parizek, R.R.; Root, R.W. Jr.

    1984-01-01

    This report presents the status and results of work performed to develop a numerical groundwater velocity model for the radioactive waste management facility at the Savannah River Plant (SRP). Work dealt with developing a hydrologic budget for the McQueen Branch drainage basin. Two hydrologic budgets were developed, covering two periods of time. The first period was from November 1, 1982 to May 19, 1984; the second period was from March 1, 1983 to March 31, 1984. Total precipitation for this period was 52.48 inches, all as rainfall. Water levels measured in wells in the basin quarterly, monthly, and continuously showed basically the same response over the period of the study. Maximum fluctuation of water levels of wells in the basin was five to seven feet during the study. Stream discharge measurements in McQueen Branch showed base flow varying between 1.5 and 5.7 cfs. Lowest base flow occurred during the summer, when evapotranspiration was greatest. Some impact of daily ground-water evapotranspiration from the Branch floodplain was seen in continuous stream records. These daily effects peaked in magnitude during the summer, disappeared during winter, and gradually returned during spring. Underflow past the Branch gauging station out of the basin was determined to be negligible. Leakage downward through the Green Clay is difficult to determine but is believed to be small, based on the overall results of the budget study

  19. Investigation of pyrite as a contributor to slagging in eastern bituminous coals. Quarterly progress report 9, October 1-December 31, 1983

    Energy Technology Data Exchange (ETDEWEB)

    Bryers, R.W.

    1984-06-01

    The objective of this program is to examine slags formed as a result of firing coals with varying concentration levels, size distribution, and orientation of pyrite with regard to mineral matter in the coal in a laboratory furnace. The program tasks are: (1) selection of eight candidate coals; (2) chemical characterization of the coal samples and identification of the pyrite size, distribution, and orientation with respect to other mineral matter and concentration levels; (3) testing of the candidate coals in a laboratory furnace; (4) chemical and physical characterization of the slag and fly ash samples created by the impurities in the coal sample; (5) influence of coal beneficiation on furnace slagging; and (6) analysis of data and identification of parameters influencing the contribution of pyrite to slagging problems. Washing of the Upper Freeport coal from Indiana County, Pennsylvania, was completed by the last quarter of 1983. The washed product was characterized for mineral content, and a combustion test was performed. Kentucky No. 9 from Henderson County, Kentucky, selected as the sixth coal to be investigated, was characterized using size and gravity fractionation techniques and was combusted in the laboratory furnace to evaluate its slagging and fouling potential. The remaining two coals to be characterized and combusted were identified as Illinois No. 5 and Lower Kittanning from Clarion County, Pennsylvania. 80 figures, 27 tables.

  20. Direct synthesis of 2-methyl-1-propanol/methanol fuels and feedstocks: Quarterly technical progress report for the period June--August 1985

    Energy Technology Data Exchange (ETDEWEB)

    Klier, K.; Herman, R. G.; Simmons, G. W.; Nunan, J.; Himelfarb, P. B.

    1985-09-01

    During the present quarter, and intensive series of aluminum- supported catalysts, both Cs promoted and unpromoted, have been prepared by a special preparation technique and tested to determine alcohol synthesis activity, selectivities, and stability. Preparation of a single-phase hydrotalcite-like ((Cu/sub x/Zn/sub 1 -x/)/sub 6/Al/sub 2/CO/sub 3/(OH)/sub 16//center dot/4H/sub 2/O) catalyst precursor has been successfully accomplished. Some of these catalysts have been tested to determine their activities in producing methanol and higher alcohols. It has been observed that catalysts obtained by calcination and reduction of the hydrotalcite-like precursor are very active methanol synthesis catalysts. Doping these catalysts with cesium in an aqueous solution leads to initial deactivation, which is partially recovered by doping at higher cesium levels. Results give us guidelines for altering the promoter doping procedure so that a more active and selective aluminum-supported higher alcohol synthesis catalyst will be obtained. 4 refs., 13 figs., 13 tabs.

  1. Trend chart: photovoltaic solar energy. Forth quarter 2016

    International Nuclear Information System (INIS)

    Coltier, Yves

    2017-02-01

    This publication presents a quarterly review of power generation from photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, detailed regional results, methodology used

  2. Wind/photovoltaic power indicators. Second quarter 2015

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2015-08-01

    This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

  3. Wind/photovoltaic power indicators. Third quarter 2011

    International Nuclear Information System (INIS)

    Thienard, Helene

    2011-11-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, projects in progress, regional status. (J.S.)

  4. Wind/photovoltaic power indicators. Third quarter 2014

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2014-11-01

    This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

  5. Wind/photovoltaic power indicators. Fourth quarter 2012

    International Nuclear Information System (INIS)

    Reynaud, Didier; Thienard, Helene

    2013-02-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status. (J.S.)

  6. Wind/photovoltaic power indicators. Third quarter 2010

    International Nuclear Information System (INIS)

    Thienard, Helene

    2010-11-01

    This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

  7. Wind/photovoltaic power indicators. Fourth quarter 2013

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2014-02-01

    This document presents a quarterly review of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status

  8. Wind/photovoltaic power indicators. Third quarter 2013

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2013-11-01

    This document presents a quarterly review of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status

  9. Wind/photovoltaic power indicators. Fourth quarter 2011

    International Nuclear Information System (INIS)

    Thienard, Helene

    2012-02-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, projects in progress, regional status. (J.S.)

  10. Trend chart: photovoltaic solar energy. Third quarter 2016

    International Nuclear Information System (INIS)

    Coltier, Yves

    2016-11-01

    This publication presents a quarterly review of power generation from photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, detailed regional results, methodology used

  11. Trend chart: photovoltaic solar energy. Forth quarter 2015

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-02-01

    This publication presents a quarterly review of power generation from photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, detailed regional results, methodology used

  12. Trend chart: photovoltaic solar energy. First quarter 2017

    International Nuclear Information System (INIS)

    2017-05-01

    This publication presents a quarterly review of power generation from photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, detailed regional results, methodology used

  13. Wind/photovoltaic power indicators. Third quarter 2012

    International Nuclear Information System (INIS)

    Thienard, Helene

    2012-11-01

    This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

  14. Wind/photovoltaic power indicators. First quarter 2014

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2014-05-01

    This document presents a quarterly review of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status

  15. Wind/photovoltaic power indicators. Second quarter 2012

    International Nuclear Information System (INIS)

    Thienard, Helene

    2012-09-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, projects in progress, regional status. (J.S.)

  16. Wind/photovoltaic power indicators. First quarter 2013

    International Nuclear Information System (INIS)

    Reynaud, Didier; Thienard, Helene

    2013-06-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional status. (J.S.)

  17. Wind/photovoltaic power indicators. Forth quarter 2014

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2015-02-01

    This document presents a quarterly review of power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

  18. Wind/photovoltaic power indicators. Second quarter 2014

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2014-08-01

    This document presents a quarterly review of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly distribution of new connections, progress of connected power during the last years, power generated since the beginning of the year and comparison with previous years, projects in progress, regional balance sheet

  19. Wind/photovoltaic power indicators. First quarter 2012

    International Nuclear Information System (INIS)

    Thienard, Helene

    2012-06-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, projects in progress, regional status. (J.S.)

  20. The ultimate response guideline simulation and analysis by using (TRACE) for Lungmen ABWR nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Hao-Tzu [Atomic Energy Council, Inst. of Nuclear Energy Research, Taoyuan City, Taiwan (China); Yang, Shu-Ming; Chen, Shao-Wen; Wang, Jong-Rong; Shih, Chunkuan [National Tsing Hua Univ., Inst. of Nuclear Engineering and Science, HsinChu, Taiwan (China)

    2015-07-15

    In this research, the TRACE/SNAP model of Lungmen ABWR nuclear power plant (NPP) has been established for the simulation and analysis of ultimate response guideline (URG). The main actions of URG are depressurization and low pressure water injection of reactor and containment venting. This research focuses to assess the URG utility of Lungmen NPP under Fukushima-like conditions. This study consists of three steps. The first step is the establishment of Lungmen NPP TRACE/SNAP model. In order to evaluate the system response of TRACE/SNAP model, FSAR data (MSIV closure and loss of feedwater flow transient) were used to compare with the results of TRACE. The second step is the URG simulation and analysis under Fukushima-like conditions by using Lungmen NPP TRACE/SNAP model. In this step, the no URG case was also performed in order to evaluate the URG effectiveness of Lungmen NPP. In order to confirm the mechanical property and integrity of fuel rods, the final step is FRAPTRAN analysis. According to TRACE analysis results, the URG can keep the peak cladding temperature (PCT) below the criteria 1088.7 K under Fukushima-like conditions which indicates that Lungmen NPP can be controlled in a safe situation. Nevertheless, if Lungmen NPP does not perform the URG under Fukushima-like conditions, the water level may drop lower than TAF after 1100 s which means a safety issue about the fuel rods may be generated. The analysis results of FRAPTRAN also indicate the integrity of fuel rods cannot be kept under the above conditions.

  1. Assessment of potential increased oil production by polymer-waterflood in northern and southern mid-continent oil fields. Progress report for the quarter ending September 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-10-15

    Activities in programs to conduct polymer-waterflood studies are reported. During the period a study was conducted of the Burbank-Bartlesville sand reservoir, located in the north half of the Stanley Stringer Field, Osage County, Oklahoma. Progress in the overall program is summarized in a chart. (JRD)

  2. Evaluation of geothermal energy in Arizona. Arizona geothermal planning/commercialization team. Quarterly topical progress report, July 1-September 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    White, D.H.; Mancini, F.; Goldstone, L.A.; Malysa, L.

    1980-01-01

    Progress is reviewed on the following: area development plans, evaluation of geothermal applications, continued evaluation of geothermal resources, engineering and economic analyses, technical assistance in the state of Arizona, the impact of various growth patterns upon geothermal energy development, and the outreach program. (MHR)

  3. QUARTERLY PROGRESS REPORT JANUARY, FEBRUARY, MARCH, 1968 REACTOR FUELS AND MATERIALS DEVELOPMENT PROGRAMS FOR FUELS AND MATERIALS BRANCH OF USAEC DIVISION OF REACTOR DEVELOPMENT AND TECHNOLOGY

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, J. J.; de Halas, D. R.; Nightingale, R. E.; Worlton, D. C.

    1968-06-01

    Progress is reported in these areas: nuclear graphite; fuel development for gas-cooled reactors; HTGR graphite studies; nuclear ceramics; fast-reactor nitrides research; non-destructive testing; metallic fuels; basic swelling studies; ATR gas and water loop operation and maintenance; reactor fuels and materials; fast reactor dosimetry and damage analysis; and irradiation damage to reactor metals.

  4. Computational modeling and experimental studies on NO{sub x} reduction under pulverized coal combustion conditions. Third quarterly technical progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Kumpaty, S.K.; Subramanian, K.

    1995-12-31

    An experimental plan outlining the first year`s activity was sent to Dr. Lori Gould, Project Officer/Contracting Officer`s Technical Representative on April 24, 1995. An approval was received with some questions on June 15, 1995. However, with some foresight of the director of the in-house combustion group of the PETC, Dr. Ekmann, a tentative hold-off on the purchase of the equipment was requested by the project officer on June 29, 1995. Enclosed with that request were some of Dr. Ekmann`s concerns. The research team spent the month of July in study of pertinent literature as well as in the preparation of the responses to Dr. Gould`s comments and Dr. Ekmann`s concerns. These responses included the choice of the reactor, reactor design, rate of gas heating, detailed test matrix and answers to host of other comments. Upon review of the above information submitted on July 24, 1995 by the Rust research team, the project officer called for a conference call on September 6, 1995 which involved the PI (Dr. Kumpaty), the research consultant (Mr. Subramanian), Dr. Gould and Dr. Ekmann. Dr. Ekmann insisted that further calculations be made on the rate of gas heating without taking radiation into account. Accordingly, calculations pertaining to the rate of gas heating based on convection were performed and submitted to Dr. Ekmann on September 13, 1995. This report contains the information emerged through the dialogue between the Rust College research team and the PETC represented by Dr. Gould and Dr. Ekmann during this quarter.

  5. Coal anion structure and chemistry of coal alkylation. Fourth quarterly progress report, December 1, 1977--February 28, 1978. [Carbon atoms in butyl groups

    Energy Technology Data Exchange (ETDEWEB)

    Stock, L.M.

    1978-01-01

    Three research problems are in progress. First, work is progressing well concerning the methods appropriate for the reductive alkylation of Illinois No. 6 coal samples. We have investigated the influence of the leaving group on the conversion of the Illinois coal to a soluble material. We find that the n-butyl iodide is more effective than other n-butyl halides. Second, preliminary results have been obtained concerning the distribution of hydrogen and deuterium atoms in the reaction of Illinois No. 6 coal samples with perdeuteriotetralin at 400/sup 0/C. Third, the nuclear magnetic resonance spectra of appropriate model compounds with n-butyl groups have been tabulated for comparison with the spectroscopic results obtained from coal alkylation products. Fourth, the chromatographic procedures necessary for the separation of the coal samples are being developed.

  6. Development and testing of industrial scale, coal fired combustion system, Phase 3. Eighteenth quarterly technical progress report, April 1, 1996--June 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Zauderer, B.

    1996-08-18

    In the second quarter of calendar year 1996, 16 days of combust- boiler tests were performed, including 2 days of tests on a parallel DOE sponsored project on sulfur retention in a slagging combustor. Between tests, modifications and improvements that were indicated by these tests were implemented. This brings the total number of test days to the end of June in the task 5 effort to 28, increased to 36 as of the date of this Report, 8/18/96. This compares with a total of 63 test days needed to complete the task 5 test effort. It is important to note that the only major modification to the Williamsport combustor has been the addition of a new downstream section, which lengthens the combustor and improves the combustor-boiler interface. The original combustor section, which includes the fuel, air, and cooling water delivery systems remained basically unchanged. Only the refractory liner was completely replaced, a task which occurs on an annual basis in all commercial slagging utility combustors. Therefore, this combustor has been operated since 1988 without replacement. The tests in the present reporting period are of major significance in that beginning with the first test on March 31st, for the first time slagging opening conditions were achieved in the upgraded combustor. The first results showed that the present 20 MMBtu/hr combustor design is far superior to the previous one tested since 1988 in Williamsport, PA. The most important change is that over 95% of the slag was drained from the slag tap in the combustor. This compares with an range of one-third to one-half in Williamsport. In the latter, the balance of the slag flowed out of the exit nozzle into the boiler floor. In addition, the overall system performance, including the combustor, boiler, and stack equipment, ranged from good to excellent. Those areas requiring improvement were of a nature that could be corrected with some work. but in no case were the problems encountered of a barrier type.

  7. Evaluation of using cyclocranes to support drilling & production of oil & gas in wetland areas. Sixth quarterly technical progress report, incorporating milestone schedule/status, October 1993--December 1993

    Energy Technology Data Exchange (ETDEWEB)

    Eggington, W.J.

    1994-04-01

    This report is a progress report on a planned program falling under wetlands area research related to drilling, production, and transportation of oil and gas resources. Specifically the planned program addresses an evaluation of using cyclocraft to transport drill rigs, mud, pipes and other materials and equipment in a cost effective and environmentally safe manner to support oil and gas drilling and production operations in wetland areas. During this period, task 5, subscale tests, and task 7, environmental impacts, were completed. Work was continued on task 10, technology transfer, and the preparation of the final report as part of task 11.

  8. A systematic assessment of the state of hazardous waste clean-up technologies. Quarterly technical progress report, April 1--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Berg, M.T.; Reed, B.E.; Gabr, M.

    1993-07-01

    West Virginia University (WVU) and the US DOE Morgantown Energy Technology Center (METC) entered into a Cooperative Agreement on August 29, 1992 entitled ``Decontamination Systems Information and Research Programs.`` Stipulated within the Agreement is the requirement that WVU submit to METC a series of Technical Progress Report for Year 1 of the Agreement. This report reflects the progress and/or efforts performed on the following nine technical projects encompassed by the Year 1 Agreement for the period of April 1 through June 30, 1993: Systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies -- drain-enhanced soil flushing (DESF) for organic contaminants removal; site remediation technologies -- in situ bioremediation of organic contaminants; excavation systems for hazardous waste sites; chemical destruction of polychlorinated biphenyls; development of organic sensors -- monolayer and multilayer self-assembled films for chemical sensors; Winfield lock and dam remediation; Assessments of Technologies for hazardous waste site remediation -- non-treatment technologies and pilot scale test facility implementation; and remediation of hazardous sites with stream reforming.

  9. Sequential purification and crystal growth for the production of low cost silicon substrates. Quarterly technical progress report No. 1, 15 September 1979-31 December 1979

    Energy Technology Data Exchange (ETDEWEB)

    Liaw, M.; Secco, F.; Ingle, B.; Down, D.

    1980-02-01

    Over the past several years, Motorola's Materials Technology Laboratory (MTL), has been conducting several projects with goals directed at the production of high quality low cost silicon crystals. One of the projects which is being investigated is the direct purification of MG-Si. A unique characteristic of the approach used by this project is the use of a crystal puller to perform both purification and crystal growth. Sequential steps of purification were taken. By the completion of this series of purification, the purified MG-Si melt will be further purified by impurity redistribution using ingot pulling. The final purified silicon will be in an ingot form of desired dimensions for slicing into silicon sheets. The sequential steps of purification include: (1) leaching of MG-Si charge, (2) phase separation, (3) reactive gas treatment, (4) liquid-liquid extraction (called Slagging), and (5) purification by redistribution of impurities using ingot pulling. Progress on items (1) and (2) is reported. (WHK)

  10. Identification and validation of heavy metal and radionuclide hyperaccumulating terrestrial plant species, Quarterly technical progress report, December 20, 1995--March 20, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Kochian, L.; Brady, D.; Last, M.; Ebbs, S.

    1995-12-01

    Although the period covered by this progress report began on December 20, 1994, which was the date that DOE approved the Interagency Agreement, the agreement was not approved by USDA until January 9, 1995 and the first scientists working on the project were not hired until February 1, 1995. The first goal of the research supported by the Interagency Agreement is to use hydroponic techniques to identify plant species and genotypes with potential for heavy metal hyperaccumulation for planting on a test site at Silverbow Creek and for radionuclide ({sup 90}Sr and {sup 137}Cs) accumulation on a test site at INEL, Idaho, later this year. The second goal of this research is to identify soil amendment procedures that will enhance the bioavailability of heavy metals and radionuclides in the soil without increasing the movement of the contaminants of concern (COC`s) into the groundwater. Our initial research covered in this report focuses on the first goal.

  11. Improving the stability of coal slurries. Quarterly progress report, March 15-June 15, 1986. [Sedimentation tests in the presence and absence of gum tragacanth

    Energy Technology Data Exchange (ETDEWEB)

    Fogler, H.S.

    1986-01-01

    In this report, we will describe the progress of our research in two key areas. The twin objectives of this research are: (a) to examine the effectiveness of hydrocolloids as stabilizers of coal-water slurries and (b) to gain an understanding of the mechanism of stabilization through the use of monodisperse polystyrene lattices as model systems. Sedimentation tests with ultrafine ground coal in presence and absence of gum tragacanth have been carried out. An isotherm of gum tragacanth binding to coal surface has been generated. We have also conducted rheological studies to characterize the stabilized coal-water slurries. Similar experiments with -200 mesh coal are currently under way. In the case of model system studies, the effect of article size on the gum tragacanth induced stability has been studied. Initial experiments on the effects of increased electrolyte concentration and the addition of nonsolvents like ethanol to the continuous phase have been undertaken. 9 refs., 16 figs., 1 tab.

  12. Tulane/Xavier University Hazardous Materials in Aquatic Environments of the Mississippi River Basin. Quarterly progress report, January 1, 1995--March 31, 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This progress report covers activities for the period January 1 - March 31, 1995 on project concerning 'Hazardous Materials in Aquatic Environments of the Mississippi River Basin.' The following activities are each summarized by bullets denoting significant experiments/findings: biotic and abiotic studies on the biological fate, transport and ecotoxicity of toxic and hazardous waste in the Mississippi River Basin; assessment of mechanisms of metal-induced reproductive toxicity in quatic species as a biomarker of exposure; hazardous wastes in aquatic environments: biological uptake and metabolism studies; ecological sentinels of aquatic contamination in the lower Mississippi River system; bioremediation of selected contaminants in aquatic environments of the Mississippi River Basin; a sensitive rapid on-sit immunoassay for heavy metal contamination; pore-level flow, transport, agglomeration and reaction kinetics of microorganism; biomarkers of exposure and ecotoxicity in the Mississippi River Basin; natural and active chemical remediation of toxic metals, organics and radionuclides in the aquatic environment; expert geographical information systems for assessing hazardous wastes in aquatic environments; enhancement of environmental education; and a number of just initiated projects including fate and transport of contaminants in aquatic environments; photocatalytic remediation; radionuclide fate and modeling from Chernobyl

  13. Development and application of a dual RELAP5-3D-based engineering simulator for ABWR

    International Nuclear Information System (INIS)

    Yang, C.-Y.; Liang, Thomas K.S.; Pei, B.S.; Shih, C.K.; Chiang, S.C.; Wang, L.C.

    2009-01-01

    For any innovated plant design, the designed paper plant can be converted into a computer as a digital plant with advanced simulation techniques before being constructed into a real plant. A digital plant, namely engineering simulator, can be applied for: (1) verification of system design and system integration, (2) power test simulation, (3) plant transient and accident analyses, (4) plant abnormal and emergency procedure development and verification, (5) design change verification and analysis, etc. An advanced engineering simulator was successfully developed for the LungMen advanced boiling water reactor (ABWR) plant to support various applications before and after commercial operation. This plant specific engineering simulator was developed based on two separate RELAP5-3D modules synchronized on a commercial simulation platform, namely 3-Key Master. On this advanced LungMen plant simulation (ALPS) platform, major plant dynamics were simulated by two separate RELAP5-3D modules, one for reactor system modeling and the other for balance of plant (BOP) system modeling. Moreover, major control systems as well as emergency core cooling system (ECCS) were all simulated in great detail with built-in tasks of this commercial simulation platform. Different from real time calculation on training simulator, precision of engineering calculation is intentionally kept by synchronizing modules based on the most time-consuming one. During synchronization, each module will check its' own converge criteria in each small time advancement. This plant specific advanced ABWR engineering simulator has been successfully applied on: (1) licensing blowdown analysis of feed water line break (FWLB) for containment design; (2) phenomena investigation of low-pressure ECC injection bypass during FWLB; (3) analysis of FW pump performance during power ascending; (4) verification of plant vendor's pre-test calculations of each start-up test.

  14. Wind/photovoltaic power indicators. Second quarter 2009

    International Nuclear Information System (INIS)

    2009-09-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  15. Wind/photovoltaic power indicators. Second quarter 2011

    International Nuclear Information System (INIS)

    2011-01-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  16. Wind/photovoltaic power indicators. First quarter 2010

    International Nuclear Information System (INIS)

    2010-01-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  17. Wind/photovoltaic power indicators. Second quarter 2010

    International Nuclear Information System (INIS)

    2010-01-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  18. Wind/photovoltaic power indicators. Fourth quarter 2010

    International Nuclear Information System (INIS)

    2011-01-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  19. Wind/photovoltaic power indicators. First quarter 2011

    International Nuclear Information System (INIS)

    2011-01-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  20. Wind/photovoltaic power indicators. Third quarter 2009

    International Nuclear Information System (INIS)

    2009-11-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  1. Wind/photovoltaic power indicators. Fourth quarter 2009

    International Nuclear Information System (INIS)

    2010-02-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  2. Wind/photovoltaic power indicators. Third quarter 2010

    International Nuclear Information System (INIS)

    2010-01-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  3. Quarterly Financial Report

    International Development Research Centre (IDRC) Digital Library (Canada)

    acray

    2011-06-30

    Jun 30, 2011 ... 2 IDRC QUARTERLY FINANCIAL REPORT JUNE 2011. Consolidated .... spending on capacity-building projects as well as to management's decision to restrict capacity- building ...... The investments in financial institutions.

  4. Information Science Research Institute quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Nartker, T.A.

    1995-09-30

    Subjects studied include optical character recognition (OCR), text retrieval, and document analysis. This report discusses the OCR test system and the text retrieval program. Staff and institute activities are given. Appendices give the ISRI methodology for preparing ground-truth test data and the test of OCR systems using DOE documents.

  5. Quarterly oil statistics. First quarter 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The aim of this report is to provide rapid, accurate and detailed statistics on oil supply and demand in the OECD area. Main components of the system are: complete balances of production, trade, refinery intake and output, final consumption, stock levels and changes; separate data for crude oil, NGL, feedstocks and nine product groups; separate trade data for main product groups, LPG and naphtha; imports for 41 origins; exports for 29 destinations; marine bunkers and deliveries to international civil aviation by product group; aggregates of quarterly data to annual totals; and natural gas supply and consumption.

  6. Areva - First quarter 2009 revenue climbs 8.5% to 3.003 billion euros; Areva - Progression du chiffre d'affaires du 1. trimestre 2009: + 8,5% a 3003 millions d'euros

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-04-15

    First quarter 2009 revenue was up 8.5% compared with the same period last year, to 3.003 billion euros. At constant exchange rates and consolidation scope, growth came to 3.9%. Currency translation had a positive impact of 57 million euros over the quarter. Changes in the consolidation scope had an impact of 66 million euros, primarily due to the consolidation of acquisitions made in 2008 in Transmission and Distribution and in Renewable Energies. The growth engines for first quarter revenue were the Reactors and Services division and the Transmission and Distribution division, with growth of 9.2% and 16.1% respectively. Outside France, revenue rose to 2.032 billion euros, compared with 1.857 billion euros in the first quarter of 2008, and represents 68% of total revenue. Orders were steady in the first quarter, particularly in the Front End, which posted several significant contracts with US and Asian utilities, and in Transmission and Distribution, with orders up sharply in Asia and South America. As of March 31, 2009, the group's backlog reached 49.5 billion euros, for 28.3% growth year-on-year, including 31.3% growth in Nuclear and 10.2% in Transmission and Distribution. For the year as a whole, the group confirms its outlook for backlog and revenue growth as well as rising operating income It should be noted that revenue may vary significantly from one quarter to the next in nuclear operations. Accordingly, quarterly data cannot be viewed as a reliable indicator of annual trends.

  7. EMSL Quarterly Highlights Report: FY 2008, 3rd Quarter

    Energy Technology Data Exchange (ETDEWEB)

    Showalter, Mary Ann

    2008-09-16

    The EMSL Quarterly Highlights Report covers the science, staff and user recognition, and publication activities that occurred during the 1st quarter (October 2007 - December 2007) of Fiscal Year 2008.

  8. EMSL Quarterly Highlights Report: 1st Quarter, FY08

    Energy Technology Data Exchange (ETDEWEB)

    Showalter, Mary Ann

    2008-01-28

    The EMSL Quarterly Highlights Report covers the science, staff and user recognition, and publication activities that occurred during the 1st quarter (October 2007 - December 2007) of Fiscal Year 2008.

  9. EMSL Quarterly Highlights Report: 1st Quarter, Fiscal Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    Showalter, Mary Ann; Kathmann, Loel E.; Manke, Kristin L.

    2009-02-02

    The EMSL Quarterly Highlights Report covers the science, staff and user recognition, and publication activities that occurred during the 1st quarter (October 2008 - December 2008) of Fiscal Year 2009.

  10. South African Crime Quarterly

    African Journals Online (AJOL)

    South African Crime Quarterly is an inter-disciplinary peer-reviewed journal that promotes professional discourse and the publication of research on the subjects of crime, criminal justice, crime prevention, and related matters including state and non-state responses to crime and violence. South Africa is the primary focus for ...

  11. English Leadership Quarterly, 1993.

    Science.gov (United States)

    Strickland, James, Ed.

    1993-01-01

    These four issues of the English Leadership Quarterly represent those published during 1993. Articles in number 1 deal with parent involvement and participation, and include: "Opening the Doors to Open House" (Jolene A. Borgese); "Parent/Teacher Conferences: Avoiding the Collision Course" (Robert Perrin); "Expanding Human…

  12. Quarterly fiscal policy

    NARCIS (Netherlands)

    Kendrick, D.A.; Amman, H.M.

    2014-01-01

    Monetary policy is altered once a month. Fiscal policy is altered once a year. As a potential improvement this article examines the use of feedback control rules for fiscal policy that is altered quarterly. Following the work of Blinder and Orszag, modifications are discussed in Congressional

  13. Sodium hydroxide injection passivation work for the reactor water clean-up system in a new ABWR plant

    International Nuclear Information System (INIS)

    Wen, Tung-Jen; Lu, Ju-Huang

    2012-09-01

    Several studies have identified that Co-58 and Co-60 as the primary source of radiation build up on out-of-core components in new BWR plants. The deposition rate of Co on stainless steel and carbon steel is shown to be controlled mainly by the thickness of oxide films and its morphology formed through pretreatment. The passivation treatment was implemented accordingly at Lungmen unit 1 in an ABWR plant in September 2010. It is determined that the passivation conditions should be maintained at the temperature of 180∼230 deg. C, pH of 8.0∼8.5 and dissolved oxygen content over 400 ppb. The films would provide effective protection against radioactive deposition. The application of the pre-filming process on piping before the pre-operation is done during the flow induced vibration test (FIV) period. The protectiveness of stable magnetite can be increased by the pH control under the specific condition. The pre-filming control process and evaluation of passivation effectiveness is discussed in detail based on the surface analysis of the passivated specimens. Many efforts have been devoted to sodium hydroxide injection method for pH control of the system through the filter demineralizer under smooth operation. A comparison of test specimens on the properties of oxide film formed between laboratory and in-plant tests through alkaline treatment are also shown in this report. (authors)

  14. Quarterly environmental data summary for third quarter 1999

    Energy Technology Data Exchange (ETDEWEB)

    McCracken, Stephen H. [Weldon Spring Site, St. Charles, MO (United States)

    1999-11-05

    A copy of the quarterly Environmental Data Summary (QEDS) for the third quarter of 1999 is enclosed. The data, except for air monitoring data and site KPA generated data (uranium analyses), were received from the contract laboratories, verified by the WSSRAP verification group and merged into the data base during the third quarter of 1999. Selected KPA results for on-site total uranium analyses performed during the quarter are also included. Air monitoring data presented are the most recent complete sets of quarterly data.

  15. Further improvement in ABWR (part-4) open distributed plant process computer system

    International Nuclear Information System (INIS)

    Makino, Shigenori; Hatori, Yoshinori

    1999-01-01

    In the nuclear industry of Japan, the electric power companies have promoted the plant process computer (PPC) technology of nuclear power plant (NPP). When PPC was introduced to NPP for the first time, because of very tight requirement such as high reliability, high speed processing, the large-scale customized computer was applied. As for recent computer field, the large market of computer contributes to the remarkable progress of engineering work station (EWS) and personal computer (PC) technology. Moreover because the data transmission technology has been progressing at the same time, world wide computer network has been established. Thanks to progress of both technologies, the distributed computer system has been established at reasonable price. So Tokyo Electric Power Company (TEPCO) is trying to apply it for PPC of NPP. (author)

  16. Quarterly environmental radiological survey summary - second quarter 1997 100, 200, 300, and 600 areas

    International Nuclear Information System (INIS)

    McKinney, S.M.; Marks, B.M.

    1997-01-01

    This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The Second Quarter 1997 survey results and the status of actions required are summarized below: All of the routine environmental radiological surveys scheduled during April, May, and June 1997, were performed as planned with the exception of UN-216-E-9. This site was not surveyed as stabilization activities were in progress. The sites scheduled for the Environmental Restorations Contractor (ERC) team were switched with those identified for the third quarter as there was a conflict with vegetation management activities

  17. EDF - Quarterly Financial Information

    International Nuclear Information System (INIS)

    Trivi, Carole; Boissezon, Carine de; Hidra, Kader

    2014-01-01

    EDF's sales in the first quarter of 2014 were euro 21.2 billion, down 3.9% from the first quarter of 2013. At constant scope and exchange rates, sales were down 4.2% due to mild weather conditions, which impacted sales of electricity in France, gas sales abroad and trading activities in Europe. UK sales were nonetheless sustained by B2B sales due to higher realised wholesale market prices. In Italy, sales growth was driven by an increase in electricity volumes sold. The first quarter of 2014 also saw the strengthening of the Group's financial structure with the second phase of its multi-annual hybrid funding programme (nearly euro 4 billion equivalent) as well as the issue of two 100-year bonds in dollars and sterling aimed at significantly lengthening average debt maturity. 2014 outlook and 2014-2018 vision: - EDF Group has confirmed its financial objectives for 2014; - Group EBITDA excluding Edison: organic growth of at least 3%; - Edison EBITDA: recurring EBITDA target of euro 1 billion and at least euro 600 million in 2014 before effects of gas contract re-negotiations; - Net financial debt / EBITDA: between 2x and 2.5x; - Pay-out ratio of net income excluding non-recurring items post-hybrid: 55% to 65%. The Group has reaffirmed its goal of achieving positive cash flow after dividends, excluding Linky, in 2018

  18. Control room unfiltered in-leakage limit analysis of design-basis LOCA for Lungmen ABWR plant

    International Nuclear Information System (INIS)

    Tsai Chihming; Chang Chinjang; Yuann Yngruey

    2014-01-01

    In USNRC's Generic Letter 2003-01, 'Control Room Habitability,' it requests utilities provide information to demonstrate that the control room at each of their respective facilities complies with the current licensing and design bases, and applicable regulatory requirements, and that suitable design, maintenance and testing control measures are in place for maintaining this compliance. In particular, each utility is required to perform the control room in-leakage test to demonstrate that the unfiltered in-leakage rate is within that assumed in the licensing analyses. It must be ensured that the control room envelope habitability, in terms of radiation dose, is maintained during normal operations as well as design basis accidents. In view of this, a dose analysis has been performed to establish the control room unfiltered in-leakage limit which can be used as an acceptance criterion for the in-leakage test. The analysis in this study is for Lungmen ABWR plant. The plant has twin units, with each unit having its own control room. The TID-4844 source terms and associated methodology are used. The USNRC RADTRAD v3.03 code is employed for the transport calculation of radioactive materials in different paths, including control room in-leakage path. The radiological criterion on protection of the operators specified in 10 CFR 50, Appendix A, General Design Criterion 19 is followed. It's demonstrated that the performance of Lungmen control room with 500 cfm unfiltered in-leakage air could meet the radiological habitability acceptance criteria in case of radiation hazards. (author)

  19. Development of advanced BWR fuel bundle with spectral shift rod (3) -transient analysis of ABWR core with SSR

    International Nuclear Information System (INIS)

    Ikegawa, T.; Chaki, M.; Ohga, Y.; Abe, M.

    2010-01-01

    The spectral shift rod (SSR) is a new type of water rod, utilized instead of the conventional water rod, in which a water level develops during core operation. The water level can be changed according to the fuel channel flow rate. In this study, ABWR plant performance with SSR fuel bundles under transient conditions has been evaluated using the TRACG code. The TRACG code, which can treat three-dimensional hydrodynamic calculations in a reactor pressure vessel, is well suited for evaluating the reactor transient performance with the SSR fuel bundles because it can calculate the water levels in the SSR at each channel grouping and therefore evaluate the core reactivity according to the water level changes in the SSR. 'Generator load rejection with total turbine bypass failure' and 'Recirculation flow control failure with increasing flow' were selected as cases which may increase the reactivity with the increasing water level in the SSR. It was found that the absolute value of the void reactivity coefficient in the SSR core was larger than that in the conventional water rod core because the core averaged void fraction in the SSR core, which has the vapor region above the water level in the SSR, was larger than that in the conventional water rod core. Therefore, AMCPR for the SSR core was a little larger than that for the conventional water rod core; however, the difference was smaller than 0.02 because the inlet of the SSR ascending path was designed to be small enough to prevent the rapid water level increase in the SSR. (authors)

  20. (Shippingport Atomic Power Station). Quarterly operating report, fourth quarter 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    At the beginning of the fourth quarter of 1980, the Shippingport Atomic Power Station remained shutdown for the normally planned semiannual maintenance and testing program, initiated September 12, 1980. Operational testing began on November 7. Maximum power was achieved November 28 and was maintained throughout the remainder of the quarter except as noted. The LWBR Core has generated 19,046.07 EFPH from start-up through the end of the quarter. During this quarter, approximately 0.000025 curies of Xe 133 activity were released from the station. During the fourth quarter of 1980, 1081 cubic feet of radioactive solid waste was shipped out of state for burial. These shipments contained 0.037 curies of radioactivity.

  1. NRC quarterly [status] report

    International Nuclear Information System (INIS)

    1987-01-01

    This report covers the third quarter of calendar year 1987. The NRC licensing activity during the period of this report included the issuance of a full-power license for Beaver Valley 2 on August 14, 1987, and operating license restricted to five percent power for South Texas Unit 1 on August 21, 1987. Additional licensing delay for Shoreham is projected due to complex litigation. Also, licensing delay may occur for Comanche Peak Unit 1, because the duration of the hearing is uncertain. Although a license authorizing fuel loading and precriticality testing for Seabrook Unit 1 has been issued, there is a projected delay for low-power licensing. Full-power licensing for Seabrook Unit 1 will be delayed due to offsite emergency preparedness issues. The length of the delay is not known at this time. With the exception of Seabrook and Shoreham, regulatory delays in this report are not impacted by the schedules for resolving off-site emergency preparedness issues

  2. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1980

    Energy Technology Data Exchange (ETDEWEB)

    Zagorski, J. F.

    1980-01-01

    At the beginning of the third quarter of 1980, the Shippingport Atomic Power Station was operating with the 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops in service. During the quarter, the Station was operated for Duquesne Light Company System grid including base load and swing load operation. Twelve (12) planned swing load operations were performed on the LWBR Core this quarter to complete the LWBR operating plan of fifty (50) during this operating phase. The Station was shutdown on September 12 for the Fall 1980 Shutdown and remained in this mode through the end of the quarter. The LWBR Core has generated 18,297.98 EFPH from start-up through the end of the quarter. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. The radioactive liquid waste effluent line to the river remained blanked off to prevent inadvertent radioactive liquid waste discharges. During the quarter, approximately 0.001 curies of Xe 133 activity were released from the station. The radioactivity released from Shippingport Station is far too small to have any measurable effect on the general background environmental radioactivity outside the plant.

  3. Joint Force Quarterly. Issue 41, 2nd Quarter, April 2006

    Science.gov (United States)

    2006-04-01

    companies participated, a million more people would be actively looking for threats. Aguas de Amazonas, a subsidiary of Suez Environnement, a...9 Richard B. Myers, “A Word from the Chair- man,” Joint Force Quarterly 37 (2d Quarter 2005), 5. 10 Wald, 26. 11 “Suez— Aguas de Amazonas Water for...humanitarian duties. They have overseen over 130 humani- tarian projects worth in excess of $7.6 million and ranging from a medical center, to potable

  4. Quarterly report of Biological and Medical Research Division, April 1955

    Energy Technology Data Exchange (ETDEWEB)

    Brues, A.M.

    1955-04-01

    This report is a compilation of 48 investigator prepared summaries of recent progress in individual research programs of the Biology and Medical Division of the Argonne National Laboratory for the quarterly period ending April,1955. Individual reports are about 3-6 pages in length and often contain research data.

  5. Wind/photovoltaic power indicators. Third quarter 2011; Tableau de bord eolien-photovoltaique - Troisieme trimestre 2011

    Energy Technology Data Exchange (ETDEWEB)

    Thienard, Helene

    2011-11-15

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, projects in progress, regional status. (J.S.)

  6. Wind/photovoltaic power indicators. Fourth quarter 2011; Tableau de bord eolien-photovoltaique - Quatrieme trimestre 2011

    Energy Technology Data Exchange (ETDEWEB)

    Thienard, Helene

    2012-02-15

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, projects in progress, regional status. (J.S.)

  7. NST Quarterly. July 1996 issue

    International Nuclear Information System (INIS)

    1996-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in in-vitro mutagenesis of ornamental plants, soil erosion studies and animal feed production from agricultural waste

  8. NST Quarterly - January 1998 issue

    International Nuclear Information System (INIS)

    1998-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in proposal of national networking for biotechnology culture collection centre (NNBCCC)

  9. NST Quarterly. October 1996 issue

    International Nuclear Information System (INIS)

    1996-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in latex vulcanization (first RVNRL-based rubber gloves produced in Malaysia), tank floor scanning system (TAFLOSS), incineration and radiotherapeutic agent

  10. NST Quarterly - issue January 2002

    International Nuclear Information System (INIS)

    2002-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. The subjects discussed are i. food and drinking water which are the major pathways of radionuclides to man and ii. nuclear techniques help to monitor sedimentation in reservoir

  11. NST Quarterly - April 1998 issue

    International Nuclear Information System (INIS)

    1998-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in ionizing radiation as an alternative method for sanitization of herbs and spices

  12. Environmental Biosciences Program Quarterly Report

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence C. Mohr, M.D.

    2009-01-30

    Current research projects have focused Environmental Biosciences Program (EBP) talent and resources on providing the scientific basis for risk-based standards, risk-based decision making and the accelerated clean-up of widespread environmental hazards. These hazards include trichloroethylene, low-dose ionizing radiation (gamma and neutron) and alpha radiation from plutonium. Trichloroethylene research has been conducted as a joint collaborative effort with the University of Georgia. Work on the trichloroethylene research projects has been slowed as a result of funding uncertainties. The impact of these funding uncertainties has been discussed with the United States Department of Energy (DOE). Laboratory work has been completed on several trichloroethylene risk assessment projects, and these projects have been brought to a close. Plans for restructuring the performance schedule of the remaining trichloroethylene projects have been submitted to the department. A comprehensive manuscript on the scientific basis of trichloroethylene risk assessment is in preparation. Work on the low-dose radiation risk assessment projects is also progressing at a slowed rate as a result of funding uncertainties. It has been necessary to restructure the proponency and performance schedule of these projects, with the project on Low-Dose Radiation: Epidemiology Risk Models transferred to DOE Office of Science proponency under a separate funding instrument. Research on this project will continue under the provisions of the DOE Office of Science funding instrument, with progress reported in accordance with the requirements of that funding instrument. Progress on that project will no longer be reported in quarterly reports for DE-FC09-02CH11109. Following a meeting at the Savannah River Site on May 8, 2008, a plan was submitted for development of an epidemiological cohort study and prospective medical surveillance system for the assessment of disease rates among workers at the Savannah River

  13. Quarterly environmental data summary for fourth quarter 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The Quarterly Environmental Data Summary (QEDS) for the fourth quarter of 1997 is prepared in support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement. The data presented constitute the QEDS. The data were received from the contract laboratories, verified by the Weldon Spring Site verification group and, except for air monitoring data and site KPA generated data (uranium analyses), merged into the data base during the fourth quarter of 1997. Air monitoring data presented are the most recent complete sets of quarterly data. Air data are not stored in the data base and KPA data are not merged into the regular data base. Significant data, defined as data values that have exceeded defined ``above normal`` level 2 values, are discussed in this letter for Environmental Monitoring Plan (EMP) generated data only. Above normal level 2 values are based, in ES and H procedures, on historical high values, DOE Derived Concentration Guides (DCGs), NPDES limits and other guidelines. The procedures also establish actions to be taken in response to such data. Data received and verified during the fourth quarter were within a permissible range of variability except for those which are detailed.

  14. Short-term energy outlook: Quarterly projections, fourth quarter 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-14

    The Energy Information Administration (EIA) prepares quarterly short-term energy supply, demand, and price projections for printed publication in January, April, July, and October in the Short-Term Energy Outlook. The details of these projections, as well as monthly updates on or about the 6th of each interim month, are available on the internet at: www.eia.doe.gov/emeu/steo/pub/contents.html. The forecast period for this issue of the Outlook extends from the fourth quarter of 1997 through the fourth quarter of 1998. Values for the fourth quarter of 1997, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in EIA`s Weekly Petroleum Status Report) or are calculated from model simulations that use the latest exogenous information available (for example, electricity sales and generation are simulated by using actual weather data). The historical energy data, compiled in the fourth quarter 1997 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. 19 tabs.

  15. Quarterly coal report, July--September 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks. Coke production consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for July through September 1997 and aggregated quarterly historical data for 1991 through the second quarter of 1997. Appendix A displays, from 1991 on, detailed quarterly historical coal imports data. 72 tabs.

  16. Short-term energy outlook. Quarterly projections, first quarter 1995

    International Nuclear Information System (INIS)

    1995-02-01

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). The forecast period for this issue of the Outlook extends from the first quarter of 1995 through the fourth quarter of 1996. Values for the fourth quarter of 1994, however, are preliminary EIA estimates or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data, compiled into the first quarter 1995 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS database is archived quarterly and is available from the National Technical Information Service. The cases are produced using the Short-Term Integrated Forecasting System (STIFS). The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. Macroeconomic estimates are produced by DRI/McGraw-Hill but are adjusted by EIA to reflect EIA assumptions about the world price of crude oil, energy product prices, and other assumptions which may affect the macroeconomic outlook. The EIA model is available on computer tape from the National Technical Information Service

  17. First quarter 2005 sales data

    International Nuclear Information System (INIS)

    2005-04-01

    This press release brings information on the AREVA group sales data. First quarter 2005 sales for the group were 2,496 millions of euros, up 3,6% year-on-year from 2,41 millions. The change in foreign exchange rates between the two periods show a negative impact of 22 millions euros, which is much lower than in the first quarter of 2004. It analyzes also in more details the situation of the front end, the reactors and service division, the back end division, the transmission and distribution division and the connectors division. (A.L.B.)

  18. Short-Term Energy Outlook: Quarterly projections. Fourth quarter 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-05

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent cases with those of other forecasting services, and discusses current topics related to the short-term energy markets. (See Short-Term Energy Outlook Annual Supplement, DOE/EIA-0202.) The forecast period for this issue of the Outlook extends from the fourth quarter of 1993 through the fourth quarter of 1994. Values for the third quarter of 1993, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data are EIA data published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications.

  19. Short-term energy outlook: Quarterly projections, Third quarter 1992

    International Nuclear Information System (INIS)

    1992-08-01

    The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent cases with those of other forecasting services, and discusses current topics related to the short-term energy markets. (See Short-Term Energy Outlook Annual Supplement, DOE/EIA-0202.) The principal users of the Outlook are managers and energy analysts in private industry and government. The forecast period for this issue of the Outlook extends from the third quarter of 1992 through the fourth quarter of 1993. Values for the second quarter of 1992, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available (for example, electricity sales and generation are simulated using actual weather data). The historical energy data are EIA data published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding

  20. Short-term energy outlook, quarterly projections, first quarter 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    The forecast period for this issue of the Outlook extends from the first quarter of 1998 through the fourth quarter of 1999. Values for the fourth quarter of 1997, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in EIA`s Weekly Petroleum Status Report) or are calculated from model simulations that use the latest exogenous information available (for example, electricity sales and generation are simulated by using actual weather data). The historical energy data, compiled in the first quarter 1998 version of the Short-Term Integrated Forecasting System (STIFS) database, are mostly EIA data regularly published in the Monthly Energy Review, Petroleum Supply Monthly, and other EIA publications. Minor discrepancies between the data in these publications and the historical data in this Outlook are due to independent rounding. The STIFS model is driven principally by three sets of assumptions or inputs: estimates of key macroeconomic variables, world oil price assumptions, and assumptions about the severity of weather. Macroeconomic estimates are adjusted by EIA to reflect EIA assumptions which may affect the macroeconomic outlook. By varying the assumptions, alternative cases are produced by using the STIFS model. 24 figs., 19 tabs.

  1. Quarterly coal report, April--June 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for April through June 1997 and aggregated quarterly historical data for 1991 through the first quarter of 1997. Appendix A displays, from 1991 on, detailed quarterly historical coal imports data. Appendix B gives selected quarterly tables converted to metric tons. To provide a complete picture of coal supply and demand in the US, historical information has been integrated in this report. 8 figs., 73 tabs.

  2. Energy situation - Fourth quarter 2017

    International Nuclear Information System (INIS)

    Guggemos, Fabien; Misak, Evelyne; Mombel, David; Moreau, Sylvain

    2018-02-01

    This publication presents, first, a quarterly report of the French energy situation: primary energy consumption, energy independence and CO 2 emissions, national production, imports, exports, energy costs, average and spot prices. Data are presented separately for solid mineral fuels, petroleum products, natural gas and electricity. The methodology, the definitions and the corrections used are explained in a second part

  3. 1st quarterly report 1977

    International Nuclear Information System (INIS)

    1977-06-01

    The present report describes the activities carried out in the 1st quarter of 1977 at the Gesellschaft fuer Kernforschung in Karlsruhe or on its behalf in the framework of the fast breeder project (PSB). The problems and main results of the partial projects fuel rod development, materials testing, reactor physics, reactor safety and reactor technology are presented. (RW) [de

  4. NST Quarterly - issue October 2001

    International Nuclear Information System (INIS)

    2001-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it reviews GM technology and GMOs - genetically modified organisms. The topics discussed includes the implication of GM in practice, the controversy and the prospect of GM technology. Radioactive pig - something like a ball or plug which cleanses the inner walls of the pipeline, also briefly presented

  5. NST Quarterly - October 1997 issue

    International Nuclear Information System (INIS)

    1997-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in scientific computer modelling and simulation. A report on 2-nd FAO/IAEA research coordination meeting (RCM) of the coordinated research programme (CRP) on public acceptance of the trade development in irradiated food in Asia and the Pacific (RPFI-IV) also presented

  6. NST Quarterly. January 1996 issue

    International Nuclear Information System (INIS)

    1996-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in nuclear medicine, healthcare products sterilization, industrial irradiation dosimetry and heavy metals determination in food. The Malaysian standard for food irradiation was discussed in this issue

  7. NST Quarterly - April 2000 issue

    International Nuclear Information System (INIS)

    1999-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in genetic engineering. The articles summarized the improvement of orchids and tulips through genetic engineering and generating new varieties for the floriculture industry. It also reported, MINT won gold and silver at the International Invention 2000, 12-16 April 2000, Geneva

  8. Quarter 9 Mercury information clearinghouse final report

    Energy Technology Data Exchange (ETDEWEB)

    Laudal, D.L.; Miller, S.; Pflughoeft-Hassett, D.; Ralston, N.; Dunham, G.; Weber, G.

    2005-12-15

    The Canadian Electricity Association (CEA) identified a need and contracted the Energy & Environmental Research Center (EERC) to create and maintain an information clearinghouse on global research and development activities related to mercury emissions from coal-fired electric utilities. A total of eight reports were completed and are summarized and updated in this final CEA quarterly report. Selected topics were discussed in detail in each quarterly report. Issues related to mercury from coal-fired utilities include the general areas of measurement, control, policy, and transformations. Specific topics that have been addressed in previous quarterly reports include the following: Quarterly 1 - Sorbent Control Technologies for Mercury Control; Quarterly 2 - Mercury Measurement; Quarterly 3 - Advanced and Developmental Mercury Control Technologies; Quarterly 4 - Prerelease of Mercury from Coal Combustion By-Products; Quarterly 5 - Mercury Fundamentals; Quarterly 6 - Mercury Control Field Demonstrations; Quarterly 7 - Mercury Regulations in the United States: Federal and State; and Quarterly 8 - Commercialization Aspects of Sorbent Injection Technologies in Canada. In this last of nine quarterly reports, an update of these mercury issues is presented that includes a summary of each topic, with recent information pertinent to advances made since the quarterly reports were originally presented. In addition to a comprehensive update of previous mercury-related topics, a review of results from the CEA Mercury Program is provided. 86 refs., 11 figs., 8 tabs.

  9. Quarterly, Bi-annual and Annual Reports

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Quarterly, Bi-annual and Annual Reports are periodic reports issued for public release. For the deep set fishery these reports are issued quarterly and anually....

  10. Nigerian Quarterly Journal of Hospital Medicine: Submissions

    African Journals Online (AJOL)

    Nigerian Quarterly Journal of Hospital Medicine: Submissions. Journal Home > About the Journal > Nigerian Quarterly Journal of Hospital Medicine: Submissions. Log in or Register to get access to full text downloads.

  11. Quarterly coal report, July--September 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-02-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for July through September 1998 and aggregated quarterly historical data for 1992 through the second quarter of 1998. 58 tabs.

  12. Joint Force Quarterly. Issue 64, 1st Quarter 2012

    Science.gov (United States)

    2012-01-01

    ndupress .ndu.edu issue 64, 1 st quarter 2012 / JFQ 43 experienced in cultural relativism belie the great commonality of moral solidarity in...Politics of Civil-Military Relations (Cambridge: Harvard University Press, 1957), 11. 12 Many people equate cultural relativism and moral relativism ...perhaps reluctantly, his muse was Platonic (the concept of the human for strategy to work in our age, it must possess solid moral and political

  13. Oil, Gas, Coal and Electricity - Quarterly statistics. Second Quarter 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-15

    This publication provides up-to-date and detailed quarterly statistics on oil, coal, natural gas and electricity for the OECD countries. Oil statistics cover production, trade, refinery intake and output, stock changes and consumption for crude oil, NGL and nine selected oil product groups. Statistics for electricity, natural gas, hard coal and brown coal show supply and trade. Import and export data are reported by origin and destination. Moreover, oil and hard coal production are reported on a worldwide basis.

  14. 32 CFR 643.127 - Quarters.

    Science.gov (United States)

    2010-07-01

    ... Additional Authority of Commanders § 643.127 Quarters. The assignment and rental of quarters to civilian employees and other nonmilitary personnel will be accomplished in accordance with AR 210-50. Responsibility of the Corps of Engineers for the establishment of rental rates for quarters rented to civilian and...

  15. 10 CFR 34.29 - Quarterly inventory.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Quarterly inventory. 34.29 Section 34.29 Energy NUCLEAR... RADIOGRAPHIC OPERATIONS Equipment § 34.29 Quarterly inventory. (a) Each licensee shall conduct a quarterly physical inventory to account for all sealed sources and for devices containing depleted uranium received...

  16. Quarterly financial reports | IDRC - International Development ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Quarterly Financial Report for the period ending 31 December 2011 · Quarterly Financial Report for the period ending 30 September 2011 · Quarterly Financial Report for the period ending 30 June 2011 · Summary of Expense Reductions to Accommodate Budget 2012 Appropriation Reduction (PDF) · What we do · Funding ...

  17. Wind/photovoltaic power indicators. Fourth quarter 2009; Tableau de bord eolien-photovoltaique. Quatrieme trimestre 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-02-15

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  18. Wind/photovoltaic power indicators. Third quarter 2010; Tableau de bord eolien-photovoltaique. troisieme trimestre 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  19. Wind/photovoltaic power indicators. Second quarter 2011; Tableau de bord eolien-photovoltaique. Deuxieme trimestre 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  20. Wind/photovoltaic power indicators. Third quarter 2009; Tableau de bord eolien-photovoltaique. troisieme trimestre 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-11-15

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  1. Wind/photovoltaic power indicators. Second quarter 2009; Tableau de bord eolien-photovoltaique. Deuxieme trimestre 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-09-15

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  2. Wind/photovoltaic power indicators. First quarter 2011; Tableau de bord eolien-photovoltaique. Premier trimestre 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  3. Wind/photovoltaic power indicators. Second quarter 2010; Tableau de bord eolien-photovoltaique. Deuxieme trimestre 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  4. Wind/photovoltaic power indicators. First quarter 2010; Tableau de bord eolien-photovoltaique. Premier trimestre 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  5. Wind/photovoltaic power indicators. Fourth quarter 2010; Tableau de bord eolien-photovoltaique. Quatrieme trimestre 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This document makes a quarterly status of the power generation from wind and photovoltaic power plants connected to the French grid (continental France, Corsica and overseas territories): total connected load, quarterly connected load during the last years, power generated since the beginning of the year, progress trend of wind and photovoltaic power in France, regional status. (J.S.)

  6. Quarterly report on the ferrocyanide safety program for the period ending December 31, 1994

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1995-01-01

    This is the fifteenth quarterly report on the progress of active addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0. 60 refs

  7. Quarterly report on the Ferrocyanide Safety Program for the period ending September 30, 1995

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1995-10-01

    This is the eighteenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0

  8. NST Quarterly - January 1997 issue

    International Nuclear Information System (INIS)

    1997-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in local heat shrinkable copolymer and electron beam technology for purification of flue gases. It announces an International Nuclear Conference themed ' a new era in nuclear science and technology - the challenge of the 21 century ' will be held in Kuala Lumpur, Malaysia from 29 to 30 Sept 1997

  9. NST Quarterly - Oct 2000 issue

    International Nuclear Information System (INIS)

    2000-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights the bioremediation of soils, the use of biological agents to reclaim soils and water polluted by substances hazardous to human health and/or the environment. Integrated waste management and thermal oxidation plant also reported, the topics discussed includes the role of the integrated waste management system, plant description and equipment design

  10. 3. quarter 2006 sales revenue

    International Nuclear Information System (INIS)

    2006-10-01

    This document presents the sales revenue of the 3. quarter 2006 for the Group AREVA. The sales revenues for the first nine months of 2006 are up by 8,1% to 7,556 millions euros; the nuclear operations are up by 5,2% reflecting strong performance in the front end division; the transmission and distribution division is up by 14%. (A.L.B.)

  11. Third quarter 2005 sales figures

    International Nuclear Information System (INIS)

    2005-01-01

    With manufacturing facilities in over 40 countries and a sales network in over 100, AREVA offers customers technological solutions for nuclear power generation and electricity transmission and distribution. The group also provides interconnect systems to the telecommunications, computer and automotive markets. This document presents the sales figures of the group for the third quarter of 2005: sales revenues in the front end division, in the reactor and services division, in the back end division and in the transmission and distribution division

  12. Quarterly coal report, January--March 1998

    Energy Technology Data Exchange (ETDEWEB)

    Young, P.

    1998-08-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for January through March 1998 and aggregated quarterly historical data for 1992 through the fourth quarter of 1997. Appendix A displays, from 1992 on, detailed quarterly historical coal imports data. To provide a complete picture of coal supply and demand in the United States, historical information has been integrated in this report. 58 tabs.

  13. Quarterly coal report, October--December 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for October through December 1996 and aggregated quarterly historical data for 1990 through the third quarter of 1996. Appendix A displays, from 1988 on, detailed quarterly historical coal imports data. To provide a complete picture of coal supply and demand in the US, historical information has been integrated in this report. 8 figs., 72 tabs.

  14. Quarterly coal report, April--June, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for April through June 1998 and aggregated quarterly historical data for 1992 through the first quarter of 1998. Appendix A displays, from 1992 on, detailed quarterly historical coal imports data. 58 tabs.

  15. Quarterly coal report, October--December 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. This report presents detailed quarterly data for October through December 1998 and aggregated quarterly historical data for 1992 through the third quarter of 1998. Appendix A displays, from 1992 on, detailed quarterly historical coal imports data. 58 tabs.

  16. NREL PV working with industry, first quarter 2000; pulling out all the stops

    Energy Technology Data Exchange (ETDEWEB)

    Moon, S.; Poole, L.; Cook, G.

    2000-05-03

    NREL PV Working With Industry is a quarterly newsletter devoted to the research, development, and deployment performed by NREL staff in concert with their industry and university partners. The First Quarter, 2000, issue offers an in-depth look at the PV Program's Five Year Plan and the PV industry's progress in developing a 20-year roadmap. The editorialist is Roger Little, President and CEO of Spire Corporation and a member of the NCPV Advisory Board.

  17. Establishing the SECME Model in the District of Columbia. Quarterly report, September 1, 1993--December 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    Technical progress and Federal Cash Transaction reports are presented for the first quarter. The work has been valuable in providing opportunities for greater academic achievement in mathematics and science for minority students in the District of Columbia.

  18. Short-term energy outlook, quarterly projections, second quarter 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The Energy Information Administration (EIA) prepares quarterly short-term energy supply, demand, and price projections. The details of these projections, as well as monthly updates, are available on the Internet at: www.eia.doe.gov/emeu/steo/pub/contents.html. The paper discusses outlook assumptions; US energy prices; world oil supply and the oil production cutback agreement of March 1998; international oil demand and supply; world oil stocks, capacity, and net trade; US oil demand and supply; US natural gas demand and supply; US coal demand and supply; US electricity demand and supply; US renewable energy demand; and US energy demand and supply sensitivities. 29 figs., 19 tabs.

  19. Applied Meteorology Unit (AMU) Quarterly Report - Fourth Quarter FY-09

    Science.gov (United States)

    Bauman, William; Crawford, Winifred; Barrett, Joe; Watson, Leela; Wheeler, Mark

    2009-01-01

    This report summarizes the Applied Meteorology Unit (AMU) activities for the fourth quarter of Fiscal Year 2009 (July - September 2009). Tasks reports include: (1) Peak Wind Tool for User Launch Commit Criteria (LCC), (2) Objective Lightning Probability Tool. Phase III, (3) Peak Wind Tool for General Forecasting. Phase II, (4) Update and Maintain Advanced Regional Prediction System (ARPS) Data Analysis System (ADAS), (5) Verify MesoNAM Performance (6) develop a Graphical User Interface to update selected parameters for the Hybrid Single-Particle Lagrangian Integrated Trajectory (HYSPLlT)

  20. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1979

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1979-01-01

    At the beginning of the third quarter of 1979, the Shippingport Atomic Power Station remained shutdown to complete repairs of the turbine generator hydrogen circulation fan following discovery of a rubbing noise on May 24, 1979. The Station was in a cooldown condition at approximately 180/sup 0/F and 300 psig with a steam bubble in the pressurizer and the reactor coolant pumps in slow speed. The reactor plant cooldown heat exchanger was in service to maintain coolant temperature. The 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops remained in service. All expended PWR Core 2 fuel elements have previously been shipped off-site. The remaining irradiated PWR Core 2 core barrel and miscellaneous refueling tools were in storage under shielding water in the deep pit of the Fuel Handling Building. The LWBR Core has generated 12,111.00 EFPH from startup through the end of the quarter.

  1. NST Quarterly - January 1999 issue

    International Nuclear Information System (INIS)

    1999-01-01

    NST Quarterly reports current development in Nuclear Science and Technology in Malaysia. In this issue it highlights MINT activities in radioactive tracer technique and medical services. Special report on the sediment tracing technique to study the sedimentation pattern at the power stations was presented. The syopsis on two new book launched by MINT also were reviewed. The books are Research Highlights on the Use of Induced Mutations for Plant Improvement in Malaysia and Rice Agro-Ecosystem of the Muda Irrigation Scheme, Malaysia. In medical services, MINT has a group, provide medical physics services such as QA checks on the country's diagnostic radiology equipment and related services

  2. Nuclear medicine progress report for quarter ending September 30, 1987

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Allred, J.F.; Ambrose, K.R.; Callahan, A.P.; Rice, D.E.; Srivastava, P.C.

    1988-03-01

    In this report the preparation of a new radioiodinated nucleoside as a potential tumor-localizing agent is described. The p-iodophenyl analogue of 5-amino-1-β-D-ribofuranosylimidazole-4-carboxamide (AlCA) was prepared by a 5-step reaction sequence. The iodine-125-labeled analogue was evaluated in rats and nude mice with implanted tumors. This agent crossed the intact blood-brain barrier (0.28% injected dose/gm at 5 min) and also showed some uptake in implanted tumors (0.74% injected dose/gm at 30 min). These preliminary results demonstrate that radioiodinated nucleoside analogues are good candiates for tumor localization. To evaluate the possible formation of 3-R,S-hydroxy-3-methyl metabolites from radioiodinated 15-(p-iodophenyl)-3-R,S-methylpentadecanoic acid (''BMIPP''), a new synthesis of 3-R,S-hydroxy fatty acids has been developed involving C-2 acylation of the ester (''Meldrum's'' acid) formed by condensation of malonic acid with acetone. Treatment with acid forms the methyl ketone which is condensed under Reformatsky conditions to give the racemic β-hydroxy-β-methyl ester which is then hydrolyzed with base. In this way, the β-hydroxy analogues of BMIPP and 3-methylheptadecanoic acid have been prepared for the first time and are being used in biological studies. 8 refs., 3 figs., 2 tabs

  3. Nuclear medicine progress report for quarter ending June 30, 1985

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Ambrose, K.R.; Goodman, M.M.; Srivastava, P.C.

    1985-10-01

    The subcellular distribution and lipid analysis studies of the 3-monomethyl-branched (BMIPP), 3,3-dimethyl-branched (DMIPP), and the parent straight-chain 15-para-iodophenylpentadecanoic acid (IPP) are described. Because of the observed differences of the relative myocardial uptake and retention of these agents in fasted and nonfasted rats, a detailed evaluation of the subcellular distribution profiles and the distribution of radioactivity within various lipid pools extracted from cell components was performed. The dimethyl DMIPP analogue showed the longest retention and also showed the highest association with the mitochondrial and microsomal fractions. The 3-monomethyl (BMIPP) analogue appeared to undergo slower oxidation than the straight chain (IPP), and the dimethyl-branched (DMIPP) analogue was apparently not oxidized by the myocardium. All three analogues showed some incorporation into triglycerides. Because the positron emitting radioisotopes of bromine show good radionuclidic properties, a new [ 82 Br]-labeled bromopentenyl-substituted cation was prepared. The tissue distribution of triphenyl-(E,Z-[ 82 Br]bromopenten-5-yl)phosphonium iodide in rats showed high heart uptake and retention with high heart to blood ratios. Radioiodinated (E)-2-C-iodovinyl-D-glucose has been prepared as a new iodovinyl-substituted carbohydrate containing C-iodovinyl-branching at the 2-position. 5 refs., 11 figs., 2 tabs

  4. Nuclear medicine progress report for quarter ending September 30, 1982

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Butler, T.A.; Goodman, M.M.; Hoeschele, J.D.; Srivastava, P.C.

    1983-01-01

    In this report a new kit is described for the rapid, regiospecific radioiodination of 15-(p-iodophenyl)pentadecanoic acid (IPP). Iodine-123-labeled IPP is used clinically to monitor myocardial fatty acid metabolism and the new kit offers a major improvement over present methods of radioiodination. During the period three shipments of /sup 191/Os-osmate were made to Medical Cooperative investigators for fabrication of the /sup 191/Os-/sup 191m/Ir radionuclide generator. Five production runs of /sup 11/C labeled amino acids including L-valine, DL-tryptophan and 1-aminocyclohexanecarboxylic acid were synthesized for clinical studies at the Oak Ridge Associated Universities. In addition, seven shipments of /sup 195m/Pt-cis-dichlorodiammineplatinum(II) were made to collaborators for evaluation of the pharmacologic properties of this antitumor agent and to monitor the effective therapeutic dose levels. Several /sup 125/I- and /sup 123m/Te-labeled fatty acids were prepared for evaluation in conjunction with collaborators at the Massachusetts General Hospital. Studies of radioiodinated barbiturates as potential new agents to measure cerebral blood perfusion have also continued. Iodine-125-labeled 5-ethyl-t-(meta-iodophenyl)barbituric acid was prepared as a model agent in which the iodine was stabilized by attachment to a phenyl ring. Evaluation in rats indicated brain uptake with only minimal deiodination. Preliminary studies with tritium-labeled benzo(a)pyrene have also been performed using Syrian hamster embryo (SHE) cells grown in diffusion chambers implanted in rats.

  5. Nuclear medicine. Progress report for quarter ending June 30, 1982

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Butler, T.A.; Goodman, M.M.; Hoeschele, J.D.; Srivastava, P.C.

    1982-09-01

    The oxidation products of tellurium and selenium fatty acids were shown to differ and may relate to the unique prolonged retention of tellurium fatty acids in the heart. The studies suggest that the trapping of tellurium fatty acids in the heart may result from the formation of an insoluble oxidation product after entry into the cells of the heart muscle. Also described in this report is the synthesis of several barbituric acid analogues for evaluation as potential cerebral perfusion agents. The present studies indicate that the iodovinyl-alkyl barbiturates cross the intact blood-brain barrier but undergo in vivo deiodination as measured by a high uptake of radioiodine in the thyroid. During this period four /sup 191/Os-osmate shipments were made to Medical Cooperative investigators for evaluation of the ultrashort-lived /sup 191//sup m/Ir (T/sub 1/2/ = 4.9 sec) obtained from the /sup 191//sup m/Ir generator. Seven shipments of the /sup 195//sup m/Pt-labeled cis-dichlorodiammineplatinum(II) antitumor drug were made to collaborators and fice shipments of radiolabeled tellurium fatty acids were made to the Massachusetts General Hospital.

  6. Quarterly progress report - metallurgy unit - April 1954--June 1954

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, J.J.

    1954-07-16

    Four irradiated tensile specimens were tested in the Radiometallurgy laboratory. The uranium was from a lot rolled at Simonds Saw and STeel Company, then beta heat treated by the triple dip process. The samples were irradiated to 310 MWD/AT. The corrected exposure was 620 MWD/T after compensating for the decrease in flux depression due to the specimen size. Two of the irradiated specimens were tested in the as-received condition while the other two were vacuum annealed at 400{degree}C for 15 hours prior to testing. When the tensile properties of the unirradiated controls, irradiated, and irradiated-annealed specimens were compared, it was observed that no marked change in modulus of elasticity occurred, the 0.1 percent offset yield strength increased by a factor of about two for the irradiated and irradiated-irradiated, and 35 for the irradiated-annealed specimens, compared to the controls. The marked change in mechanical properties on irradiation as well as the relatively small effect of the anneal, indicates that the foreign atom effect caused by fission product concentration and distribution is the controlling factor, and work-hardening type of damage is relatively insignificant.

  7. UNLV Information Science Research Institute quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Nartker, T.A.

    1994-03-31

    Sections of this report include: symposium activity, staff activity, document analysis program, text-retrieval program, institute activity, etc. It is believed that as large, complete collections of documents become available in digital libraries, users will demand complete interaction with the information; document access mechanisms will have to grow beyond keywords and full-text searches to include browsing, searching of images, and searching on basis of abstract concepts. It is proposed to study the microform document conversion process, including image preprocessing, recognition, postprocessing for extracting information, and natural language techniques. Characterization of algorithms will allow generation of a system that automatically adapts to a wide range of image quality, thereby allowing large-scale conversion efforts. It is proposed to focus first on the NSF Antarctic database (approx. 55,000 documents).

  8. Second quarter technical progress report for Thermally Modified Sand

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-14

    The objective was to have the Alaska Department of Transportation & Public Facilities Operation & Maintenance Section use Thermally Modified Sand (TMS) for treatment of icy state roadways. The project included the evaluation on the workability of a large stockpile of TMS material left undisturbed throughout the 1993/94 winter season.

  9. Nuclear waste management. Quarterly progress report, April-June 1980

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-09-01

    The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

  10. Fuel cycle programs. Quarterly progress report, January-March 1980

    International Nuclear Information System (INIS)

    Steindler, M.J.; Bates, J.K.; Brock, R.E.

    1981-02-01

    Studies were continued on the encapsulation of radioactive waste in metal. The possibility of interactions between simulated waste glass and lead in air and argon atmospheres was explored. No reactions were observed at 350 and 500 0 C; however, a potential reaction was indicated at 685 0 C in air. A comparative economic analysis of four waste solidification processes subcontracted to TERA Corporation was completed. Within the uncertainties of the cost estimates, the cost of the four processes (two yielding metal-matrix encapsulated waste forms and two yielding glass monoliths) was about the same, with the major cost component being the cost of the building structures. Results of ten drop-weight brittle-fracture tests with Pyrex cylinders indicated that, for the same impact energy density, threefold variations in either drop velocity or cylinder size had no significant effect on the principal parameters of the test model. The kinetics of fracture is being studied by means of high-speed motion pictures. Tests indicated that evaporation losses of solutions collected during infiltration experiments were too small to significantly affect the experimental results. Studies were initiated to determine the cause of the discrepancy between the experimental Cs + velocity in kaolinite columns during 0.1M NaHCO 3 flow and the velocity calculated from the partitioning coefficient. A mathematical model was developed in an effort to explain why the experimentally determined isotherm for IO 3 sorption on Fe 2 O 3 differed from the Langmuir isotherm. Developmental studies of the neutron activation method and the use of tracers for determining very low leach rates were continued. Other studies showed that hydrothermal leaching of glass produced a large increase in surface area

  11. Nuclear medicine technology. Progress report, quarter ending March 31, 1980

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.

    1980-10-01

    The successful detection of experimentally produced myocardial infarctions in rats and dogs using /sup 123m/Te-9-telluraheptadecanoic acid (9-[/sup 123m/Te]-THDA) is described. Preferential localization of radioactivity in normal myocardial tissue of rats that had experimentally produced infarctions was also demonstrated by tissue distribution studies following injection of 9-[/sup 123m/Te]-THDA. The effects of chain length on the myocardial uptake of 75 Se-labeled long-chain fatty acids was also studied further. Selenium-75-labeled 13-selenaheneicosonic acid [H 3 C-(CH 2 ) 7 - 75 Se-(CH 2 ) 11 -COOH, 13-[ 75 Se]-SHCA] shows the highest heart uptake in rats of the agents studied. These results indicate that myocardial imaging may be possible with 13-[ 75 Se]-SHCA and also suggest that potential positron emission tomography of the myocardium with the 73 Se-labeled agent should be explored. The results of continuing studies with 11 C and /sup 195m/Pt-labeled agents are also described. A variety of 11 C-labeled amino acids were prepared and tested as pancreas and tumor localizing agents in a Medical Cooperative Program with the Oak Ridge Associated Universities. The microscale synthesis of /sup 195m/Pt-labeled cis-dichloro-trans-dihydroxy-bis-(isopropylamine)platinum(IV) (/sup 195m/Pt-CHIP) was developed further and preliminary tissue distribution studies with this important second-generation antitumor drug were completed in rats. Platinum-195m-labeled cis-dichlorodiammineplatinum(II) (/sup 195m/Pt-cis-DDP) was supplied for testing to a number of Medical Cooperative Programs. Studies of arsenic trioxide (As 2 O 3 ) toxicity for human cells in the diffusion chamber assay system have continued. Further investigation of this arsenic-induced cytotoxicity has demonstrated a linear dose-response relationship and a difference in the permanence of the growth inhibitory effect using different doses

  12. Nuclear medicine progress report for quarter ending March 31, 1987

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Ambrose, K.R.; Srivastava, P.C.

    1987-08-01

    Studies using Langendorff-perfused rat hearts have shown for the first time the formation of a polar metabolite from the methyl-branched fatty acid, BMIPP. Evaluation of the radioactive components in the outflow tract of hearts after administration of the straight-chain analogue [I-131]IPPA and [I-125]BMIPP were pursued. Analysis of lipid extracts by thin-layer chromatography illustrated the presence of a product considerably more polar than BMIPP. These results suggest for the first time that the slow myocardial clearance observed with BMIPP in clinical studies may be associated with the wash-out of an unidentified metabolite. As a continuation of an evaluation of the effects of tellurium (Te) heteroatom position and the position of alkenyliodide substitution on myocardial uptake and retention properties, several new Te fatty acids have been synthesized and studied in rats. The new agents were prepared by coupling of internal alkenyl iodides prepared from the corresponding boronic acid analogues with sodium alkoxycarbonyl tellurols. Evaluation of the four new analogues demonstrated an unexpected relationship between chain length, and the position of the Te heteroatom and alkenyliodide moiety. 5 figs., 1 tab

  13. Nuclear waste management. Quarterly progress report, January-March, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.; Powell, J.A. (comp.)

    1981-06-01

    Reports and summaries are provided for the following programs: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclide in soils; low-level waste generation reduction handbook; waste management system studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

  14. Nuclear waste management. Quarterly progress report, January-March 1980

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-06-01

    Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

  15. Nuclear waste management. Quarterly progress report, July-September 1980

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.

    1980-11-01

    Research is reported on: high-level waste immobilization, alternative waste forms, TRU waste immobilization and decontamination, krypton solidification, thermal outgassing, /sup 129/I fixation, unsaturated zone transport, well-logging instrumentation, waste management system and safety studies, effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, backfill material, spent fuel storage (criticality), barrier sealing and liners for U mill tailings, and revegetation of inactive U tailings sites. (DLC)

  16. UNLV Information Science Research Institute quarterly progress report

    International Nuclear Information System (INIS)

    Nartker, T.A.

    1994-01-01

    Sections of this report include: symposium activity, staff activity, document analysis program, text-retrieval program, institute activity, etc. It is believed that as large, complete collections of documents become available in digital libraries, users will demand complete interaction with the information; document access mechanisms will have to grow beyond keywords and full-text searches to include browsing, searching of images, and searching on basis of abstract concepts. It is proposed to study the microform document conversion process, including image preprocessing, recognition, postprocessing for extracting information, and natural language techniques. Characterization of algorithms will allow generation of a system that automatically adapts to a wide range of image quality, thereby allowing large-scale conversion efforts. It is proposed to focus first on the NSF Antarctic database (approx. 55,000 documents)

  17. Quarterly technical progress report, October 1-December 30, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1984-04-01

    Several new initiatives were begun in coal preparation, including a project to develop a liquid CO/sub 2/ coalescence process that will produce a superclean coal containing less than 1% ash. Another new project in this area is focusing on chemical coal cleaning for the removal of harmful trace elements, such as arsenic, lead, and zinc. Milestones were reached in both of our major electron beam flue gas cleanup projects. In the area of coal-water mixtures, our major industrial contracts are now approaching critical milestones. The analysis of our in-house combustion testing of micronized coal-water mixtures in PETC's 700-horsepower oil-designed boiler has been completed. By reducing the coal particle size from 90% minus 200 mesh down to 87% minus 19 microns, the carbon conversion efficiency increased from a level of 96% to 98%. Combustion tests with a commercially available CWM showed that combustion air enriched to 23% oxygen reduced the needed air preheat temperature from 370/sup 0/ to 200/sup 0/F. Work also got underway in the new projects selected last summer to investigate advanced direct liquefaction processes. At Kerr-McGee, three scoping runs on their 350 pound/day integrated bench-scale unit were successfully completed. The objective of these runs was to evaluate subbituminous coal process options in terms of catalyst performance, distillate yields, and generation of coke precursors. Cities Service began its project on the characterization of hydrogen donor solvents in two-stage liquefaction. 7 figures, 33 tables.

  18. Nuclear waste management. Quarterly progress report, April-June 1981

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.; Powell, J.A.

    1981-09-01

    Reports and summaries are presented for the following: high-level waste process development; alternative waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; and analysis of spent fuel policy implementation.

  19. Nuclear Medicine Program progress report, quarter ending March 31, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.; Rice, D.E.

    1992-07-01

    We describe the design synthesis and initial animal testing of a new iodine-131-labeled triglyceride analogue for the potential evaluation of clinical pancreatic insufficiency. The new agent is 1,2-dipalmitoyl-3-[(15-p-iodophenyl)pentadecanoyl] rac-glycerol(1,2-Pal-3-IPPA). Following oral administration of the iodine-125-labeled agent to rats, 34.5+8.8% of the administered activity was excreted in the urine within one day, demonstrating that radioiodinated IPPA is absorbed in the intestine after release from the triglyceride by pancreatic lipase. The final catabolic product of IPPA is then conjugated and excreted via the urinary bladder. Urine analysis following oral administration of this new agent to patients may thus be a new, simple method for the clinical evaluation of various gastrointestinal diseases. The synthesis and the initial biological evaluation of the 3R-isomer of [{sup 125}I]IQNP are also described.

  20. Nuclear Medicine Program progress report, quarter ending March 31, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.; Rice, D.E.

    1992-07-01

    We describe the design synthesis and initial animal testing of a new iodine-131-labeled triglyceride analogue for the potential evaluation of clinical pancreatic insufficiency. The new agent is 1,2-dipalmitoyl-3-((15-p-iodophenyl)pentadecanoyl) rac-glycerol(1,2-Pal-3-IPPA). Following oral administration of the iodine-125-labeled agent to rats, 34.5+8.8% of the administered activity was excreted in the urine within one day, demonstrating that radioiodinated IPPA is absorbed in the intestine after release from the triglyceride by pancreatic lipase. The final catabolic product of IPPA is then conjugated and excreted via the urinary bladder. Urine analysis following oral administration of this new agent to patients may thus be a new, simple method for the clinical evaluation of various gastrointestinal diseases. The synthesis and the initial biological evaluation of the 3R-isomer of ({sup 125}I)IQNP are also described.

  1. Technical Division quarterly progress report, April 1--June 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Slansky, C.M.; Dickey, B.R.; Musgrave, B.C.; Rohde, K.L.

    1977-07-01

    Fuel Cycle Research and Development: Results are presented on the fluidized-bed calcination of high-level radioactive waste from reprocessing on the post treatment of the calcine, and on the removal of actinide elements from the waste prior to calcination. Other projects include the development of storage technology for /sup 85/Kr waste; a study of the hydrogen mordenite catalyzed reaction between NO/sub x/ and NH/sub 3/; the adsorption and storage of /sup 129/I on silver exchanged mordenite; physical properties, materials of construction, and unit operations studies on the evaporation of high-level waste; the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel; and the use of the uranium-ruthenium system in age-dating uranium ore bodies. Special Materials Production: The long-term management of defense waste from the ICPP covers postcalcination treatment of ICPP calcined waste; the removal of actinide elements from first-cycle raffinate; the retrieval and handling of calcined waste from ICPP storage vaults; and the preparation of the ''Defense Waste Document''. Process improvements are reported on the Fluorinel headend process for Zircaloy-clad fuels and on uranium accountability measurements. Other development results cover the process for recovering spent Rover fuel, buried pipeline transfer systems, support to the Waste Management Program, and effluent monitoring methods evaluation and development. Other Projects Supporting Energy Development: In this category are studies on nuclear materials security; application of a liquid-solid fluidized-bed heat exchanger to the recovery of geothermal heat; in-plant reactor source term measurements; burnup methods for fast breeder reactor fuels; absolute thermal fission yield measurements; analytical support to light water breeder reactor development; research on analytical methods; and the behavior of environmental species of iodine.

  2. Nuclear Medicine progress report for quarter ending March 31, 1986

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Goodman, M.M.; Srivastava, P.C.

    1986-10-01

    An in vitro analysis of the susceptibility of the 3,3-dimethyl-branched (DMIPP) and 3-monomethyl-branched (BMIPP) analogues, and the parent straight-chain 15-para-iodophenylpentadecanoic acid (IPP) to oxidation by an acyl CoA oxidase enzyme are described. The degree of myocardial retention appears to be directly related to the susceptibility to ..beta..-oxidation. Glucose analogues labeled with single photon emitting radionuclides are desirable candidates for measuring brain glucose utilization using SPECT. Because of the attractive radionuclidic properties of iodine-123, a new deoxy-substituted iodovinyl-substituted carbohydrate has been prepared and evaluated in rats with the objective of achieving high brain uptake. The model agent, methyl-2-deoxy-2-(E)-(/sup 125/I)iodovinyl-2,4,6-0-tri-acetyl-..beta..-D-altropyranoside, was prepared by a 5-step sequence of reactions. The new radioiodinated iodovinyl-branched carbohydrate showed significant brain uptake (2.31% dose/gm at 2 min), and retention (0.78% dose/gm at 60 min) in rats. The new carbohydrate represents the first reported transport of radioiodide stabilized onto carbon of a sugar molecule across the blood-brain barrier.

  3. Nuclear medicine progress report for quarter ending June 30, 1985

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Goodman, M.M.; Srivastava, P.C.

    1985-10-01

    The subcellular distribution and lipid analysis studies of the 3-monomethyl-branched (BMIPP), 3,3-dimethyl-branched (DMIPP), and the parent straight-chain 15-para-iodophenylpentadecanoic acid (IPP) are described. Because of the observed differences of the relative myocardial uptake and retention of these agents in fasted and nonfasted rats, a detailed evaluation of the subcellular distribution profiles and the distribution of radioactivity within various lipid pools extracted from cell components was performed. The dimethyl DMIPP analogue showed the longest retention and also showed the highest association with the mitochondrial and microsomal fractions. The 3-monomethyl (BMIPP) analogue appeared to undergo slower oxidation than the straight chain (IPP), and the dimethyl-branched (DMIPP) analogue was apparently not oxidized by the myocardium. All three analogues showed some incorporation into triglycerides. Because the positron emitting radioisotopes of bromine show good radionuclidic properties, a new (/sup 82/Br)-labeled bromopentenyl-substituted cation was prepared. The tissue distribution of triphenyl-(E,Z-(/sup 82/Br)bromopenten-5-yl)phosphonium iodide in rats showed high heart uptake and retention with high heart to blood ratios. Radioiodinated (E)-2-C-iodovinyl-D-glucose has been prepared as a new iodovinyl-substituted carbohydrate containing C-iodovinyl-branching at the 2-position. 5 refs., 11 figs., 2 tabs.

  4. Quarterly technical progress report, February 1, 1996--April 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-28

    This report from the Amarillo National REsource Center for PLutonium provides research highlights and provides information regarding the public dissemination of information. The center is a a scientific resource for information regarding the issues of the storage, disposition, potential utilization and transport of plutonium, high explosives, and other hazardous materials generated from nuclear weapons dismantlement. The center responds to informational needs and interpretation of technical and scientific data raised by interested parties and advisory groups. Also, research efforts are carried out on remedial action programs and biological/agricultural studies.

  5. Nonanalytic Laboratory Automation: A Quarter Century of Progress.

    Science.gov (United States)

    Hawker, Charles D

    2017-06-01

    Clinical laboratory automation has blossomed since the 1989 AACC meeting, at which Dr. Masahide Sasaki first showed a western audience what his laboratory had implemented. Many diagnostics and other vendors are now offering a variety of automated options for laboratories of all sizes. Replacing manual processing and handling procedures with automation was embraced by the laboratory community because of the obvious benefits of labor savings and improvement in turnaround time and quality. Automation was also embraced by the diagnostics vendors who saw automation as a means of incorporating the analyzers purchased by their customers into larger systems in which the benefits of automation were integrated to the analyzers.This report reviews the options that are available to laboratory customers. These options include so called task-targeted automation-modules that range from single function devices that automate single tasks (e.g., decapping or aliquoting) to multifunction workstations that incorporate several of the functions of a laboratory sample processing department. The options also include total laboratory automation systems that use conveyors to link sample processing functions to analyzers and often include postanalytical features such as refrigerated storage and sample retrieval.Most importantly, this report reviews a recommended process for evaluating the need for new automation and for identifying the specific requirements of a laboratory and developing solutions that can meet those requirements. The report also discusses some of the practical considerations facing a laboratory in a new implementation and reviews the concept of machine vision to replace human inspections. © 2017 American Association for Clinical Chemistry.

  6. Quarterly coal report, October--December 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities. This report presents detailed quarterly data for october through December 1997 and aggregated quarterly historical data for 1991 through the third quarter of 1997. Appendix A displays, from 1991 on, detailed quarterly historical coal imports data, as specified in Section 202 of the energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric tons. To provide a complete picture of coal supply and demand in the US, historical information has been integrated in this report. 8 figs., 73 tabs.

  7. Quarterly coal report, January--March 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

    This Quarterly Coal Report (QCR) provides comprehensive information about U.S. coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience,including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275), as amended. This report presents detailed quarterly data for January through March 1997 and aggregated quarterly historical data for 1991 through the fourth quarter of 1996. Appendix A displays, from 1988 on, detailed quarterly historical coal imports data, as specified in Section 202 of the Energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric tons.

  8. Quarterly coal report, January--March 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-24

    The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275), as amended. This report presents detailed quarterly data for January through March 1994 and aggregated quarterly historical data for 1986 through the fourth quarter of 1993. Appendix A displays, from 1986 on, detailed quarterly historical coal imports data, as specified in Section 202 of the Energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric tons.

  9. Applied Meteorology Unit (AMU) Quarterly Report - Fourth Quarter FY-10

    Science.gov (United States)

    Bauman, William; Crawford, Winifred; Barrett, Joe; Watson, Leela; Wheeler, Mark

    2010-01-01

    Three AMU tasks were completed in this Quarter, each resulting in a forecast tool now being used in operations and a final report documenting how the work was done. AMU personnel completed the following tasks (1) Phase II of the Peak Wind Tool for General Forecasting task by delivering an improved wind forecasting tool to operations and providing training on its use; (2) a graphical user interface (GUI) she updated with new scripts to complete the ADAS Update and Maintainability task, and delivered the scripts to the Spaceflight Meteorology Group on Johnson Space Center, Texas and National Weather Service in Melbourne, Fla.; and (3) the Verify MesoNAM Performance task after we created and delivered a GUI that forecasters will use to determine the performance of the operational MesoNAM weather model forecast.

  10. Quarterly report on the Ferrocyanide Safety Program for the period ending June 30, 1995

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1995-07-01

    This is the seventeenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six pans of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented

  11. Quarterly coal report, January--March 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-20

    The United States produced 242 million short tons of coal in the first quarter of 1993, a decrease of 6 percent (14 million short tons) from the amount produced during the first quarter of 1992. The decrease was due to a decline in production east of the Mississippi River. All major coal-producing States in this region had lower coal production levels led by West Virginia, which produced 5 million short tons less coal. The principal reasons for the overall drop in coal output compared to a year earlier were: A decrease in demand for US coal in foreign markets; a slower rate of producer/distributor stock build-up; and a drawn-down of electric utility coal stocks. Distribution of US coal in the first quarter of 1993 was 10 million short tons lower than in the first quarter of 1992, with 5 million short tons less distributed to both electric utilities and overseas markets. The average price of coal delivered to electric utilities during the first quarter of 1993 was $28.65 per short ton, the lowest value since the first quarter of 1980. Coal consumption in the first quarter of 1993 was 230 million short tons, 4 percent higher than in the first quarter of 1992, due primarily to a 5-percent increase in consumption at electric utility plants. Total consumer stocks, at 153 million short tons, and electric utility stocks, at 144 million short tons, were at their lowest quarterly level since the end of 1989. US. coal exports totaled 19 million short tons, 6 million short tons less than in the first quarter of 1992, and the lowest quarterly level since 1988. The decline was primarily due to a 1-million-short-ton drop in exports to each of the following destinations: Italy, France, Belgium and Luxembourg, and Canada.

  12. Quarterly coal report, January--March 1993

    International Nuclear Information System (INIS)

    1993-01-01

    The United States produced 242 million short tons of coal in the first quarter of 1993, a decrease of 6 percent (14 million short tons) from the amount produced during the first quarter of 1992. The decrease was due to a decline in production east of the Mississippi River. All major coal-producing States in this region had lower coal production levels led by West Virginia, which produced 5 million short tons less coal. The principal reasons for the overall drop in coal output compared to a year earlier were: A decrease in demand for US coal in foreign markets; a slower rate of producer/distributor stock build-up; and a drawn-down of electric utility coal stocks. Distribution of US coal in the first quarter of 1993 was 10 million short tons lower than in the first quarter of 1992, with 5 million short tons less distributed to both electric utilities and overseas markets. The average price of coal delivered to electric utilities during the first quarter of 1993 was $28.65 per short ton, the lowest value since the first quarter of 1980. Coal consumption in the first quarter of 1993 was 230 million short tons, 4 percent higher than in the first quarter of 1992, due primarily to a 5-percent increase in consumption at electric utility plants. Total consumer stocks, at 153 million short tons, and electric utility stocks, at 144 million short tons, were at their lowest quarterly level since the end of 1989. US. coal exports totaled 19 million short tons, 6 million short tons less than in the first quarter of 1992, and the lowest quarterly level since 1988. The decline was primarily due to a 1-million-short-ton drop in exports to each of the following destinations: Italy, France, Belgium and Luxembourg, and Canada

  13. A quarter century of stimulated Raman scattering

    International Nuclear Information System (INIS)

    Bloembergen, N.

    1987-01-01

    To round out a quarter century of SRS the timing of this writing (1986) requires a look ahead of only one year into the future. The proceedings of the 10th International Conference on Raman Spectroscopy present a picture of current activity. Further progress will be made in time-resolved spectroscopy with subpicosecond resolution, in the study of hyper-Raman and other higher order effects with CARS, in extension of resonant Raman excitation in the UV region of spectrum, and in the development of Raman laser sources. During past few years extensive theoretical investigations have been made for four-wave light mixing in the case of one or more very strong light beams. The perturbation approach for those fields ceases to be valid. If only one light field is strong, the usual approach is to make a transformation to a rotating coordinate system so that the strong Hamiltonian for this light field becomes time-independent. Very recently these techniques have been extended to the case of two or more strong fields. CARS-type experiments with strong beams are likely to receive more attention. Extrapolation of the current activities instills confidence in the vitality of stimulated Raman scattering for the foreseeable future

  14. Trend chart: biogas. Forth quarter 2016

    International Nuclear Information System (INIS)

    Cavaud, Denis

    2017-02-01

    This publication presents the biogas industry situation of continental France and overseas territories during the forth quarter 2016: total connected load of biogas power plants, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus power and type, evolution forecasts of biogas power generation, detailed regional results, biomethane injection in natural gas distribution systems, methodology used

  15. Trend chart: biogas. Second quarter 2016

    International Nuclear Information System (INIS)

    Cavaud, Denis

    2016-08-01

    This publication presents the biogas industry situation of continental France and overseas territories during the Second quarter 2016: total connected load of biogas power plants, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus power and type, evolution forecasts of biogas power generation, detailed regional results, biomethane injection in natural gas distribution systems, methodology used

  16. Trend chart: biogas. Third quarter 2016

    International Nuclear Information System (INIS)

    Cavaud, Denis

    2016-11-01

    This publication presents the biogas industry situation of continental France and overseas territories during the third quarter 2016: total connected load of biogas power plants, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus power and type, evolution forecasts of biogas power generation, detailed regional results, biomethane injection in natural gas distribution systems, methodology used

  17. Trend chart: biogas. First quarter 2016

    International Nuclear Information System (INIS)

    Cavaud, Denis

    2016-05-01

    This publication presents the biogas industry situation of continental France and overseas territories during the first quarter 2016: total connected load of biogas power plants, new connected facilities, regional distribution of facilities, evolution of quarterly production, distribution of facilities versus power and type, evolution forecasts of biogas power generation, detailed regional results, biomethane injection in natural gas distribution systems, methodology used

  18. United States housing, second quarter 2013

    Science.gov (United States)

    Delton Alderman

    2017-01-01

    The U.S. housing market’s quarter two results were disap¬pointing compared with the first quarter. Although overall expected gains did not materialize, certain sectors improved slightly. Housing under construction, completions, and new and existing home sales exhibited slight increases. Overall permit data declined, and the decrease in starts was due primarily to a...

  19. Research and development for the declassification productivity initiative. Quarterly report, January 1997--August 1997

    Energy Technology Data Exchange (ETDEWEB)

    Bessonet, C.G. de

    1997-03-05

    The highlight for the first quarter was the presentation of research progress and findings at the DPI Symposium on March 5, 1997. Since that presentation, additional progress was slowed down due to the decreased budget funding for year two, and consequently, the decrease in time-effort of the principal investigators. This report summarizes the progress in each of the topical areas to date. A research article has been prepared for publication for the Optical Character Recognition project; two progress reports are included for the Logical Analysis project; and two progress reports for the Knowledge Representation project. Research activities for the Tipster Technology project will resume this fall.

  20. Weldon Spring Site Remedial Action Project quarterly environmental data summary (QEDS) for fourth quarter 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-02-01

    This report contains the Quarterly Environmental Data Summary (QEDS) for the fourth quarter of 1998 in support of the Weldon Spring Site Remedial Action Project Federal Facilities Agreement. The data, except for air monitoring data and site KPA generated data (uranium analyses) were received from the contract laboratories, verified by the Weldon Spring Site verification group, and merged into the database during the fourth quarter of 1998. KPA results for on-site total uranium analyses performed during fourth quarter 1998 are included. Air monitoring data presented are the most recent complete sets of quarterly data.

  1. Idaho National Laboratory Quarterly Occurrence Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 85 reportable events (18 from the 4th Qtr FY-15 and 67 from the prior three reporting quarters), as well as 25 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (8 from this quarter and 17 from the prior three quarters).

  2. The AMTEX Partnership{trademark}. Fourth quarter report, September 1994

    Energy Technology Data Exchange (ETDEWEB)

    Lemon, D.K.; Quisenberry, R.K.

    1994-06-01

    The AMTEX Partnership{trademark} is a collaborative research and development program among the US Integrated Textile Industry, the Department of Energy (DOE), the DOE laboratories, other federal agencies and laboratories, and universities. The goal of AMTEX is to strengthen the competitiveness of this vital industry, thereby preserving and creating US jobs. The operational and program management of the AMTEX Partnership is provided by the Program Office. This report is produced by the Program Office on a quarterly basis and provides information on the progress, operations, and project management of the partnership.

  3. The AMTEX Partnership. Second quarter report, Fiscal Year 1995

    Energy Technology Data Exchange (ETDEWEB)

    Lemon, D.K.; Quisenberry, R.K. [AMTEX Partnership (United States)

    1995-03-01

    The AMTEX Partnership{trademark} is a collaborative research and development program among the US Integrated Textile Industry, the Department of Energy (DOE), the national laboratories, other federal agencies and laboratories, and universities. The goal of AMTEX is to strengthen the competitiveness of this vital industry, thereby reserving and creating US jobs. The operations and program management of the AMTEX Partnership is provided by the Program Office. This report is produced by the Program Office on a quarterly basis and provides information on the progress, operations, and project management of the partnership.

  4. Econometric Methods within Romanian Quarterly National Accounts

    Directory of Open Access Journals (Sweden)

    Livia Marineta Drăguşin

    2013-04-01

    Full Text Available The aim of the present paper is to synthesise the main econometric methods (including the mathematical and statistical ones used in the Romanian Quarterly National Accounts compilation, irrespectively of Quarterly Gross Domestic Product (QGDP. These methods are adapted for a fast manner to operatively provide information about the country macroeconomic evolution to interested users. In this context, the mathematical and econometric methods play an important role in obtaining quarterly accounts valued in current prices and in constant prices, in seasonal adjustments and flash estimates of QGDP.

  5. Nondestructive analysis of the gold quarter liras

    International Nuclear Information System (INIS)

    Cakir, C.; Guerol, A.; Demir, L.; Sahin, Y.

    2009-01-01

    In this study, we have prepared seven Au-Cu standards in the concentration range of 18-24 (as carat) for nondestructive control of gold quarter liras. Some calibration curves for quantitative analysis of Au in the gold quarter liras that commercially present in Turkey have been plotted using these standard samples. The characteristic X-rays of Au and Cu emitted from these standard samples and the test sample with known composition are recorded by using a Ge(Li) detector. These calibration curves provide a nondestructive analysis of gold quarter liras with the uncertainties about 1.18%. (author)

  6. EDIN-USVI Clean Energy Quarterly: Volume 2, Issue 1, June 2012 (Newsletter)

    Energy Technology Data Exchange (ETDEWEB)

    2012-06-01

    This quarterly newsletter provides timely news and information about the plans and progress of the Energy Development in Island Nations-U.S. Virgin Islands pilot project, including significant events and milestones, work undertaken by each of the working groups, and project-related technology deployment efforts.

  7. Basalt waste isolation project. Quarterly report, April 1, 1981-June 30, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Deju, R.A.

    1981-08-01

    This document reports progress made in the Basalt Waste Isolation Project during the third quarter of fiscal year 1981. Efforts are described for the following programs of the project work breakdown structure: systems; waste package; site; repository; regulatory and institutional; test facilities; in situ test facilities.

  8. EDIN-USVI Clean Energy Quarterly: Volume 1, Issue 3, September 2011 (Newsletter)

    Energy Technology Data Exchange (ETDEWEB)

    2011-09-01

    This quarterly newsletter provides timely news and information about the plans and progress of the Energy Development in Island Nations-U.S. Virgin Islands pilot project, including significant events and milestones, work undertaken by each of the five working groups, and project-related renewable energy and energy efficiency educational outreach and technology deployment efforts.

  9. F-Area Seepage Basins groundwater monitoring report, fourth quarter 1991 and 1991 summary

    International Nuclear Information System (INIS)

    1992-03-01

    This progress report for fourth quarter 1991 and 1991 summary fro the Savannah River Plant includes discussion on the following topics: description of facilities; hydrostratigraphic units; monitoring well nomenclature; integrity of the monitoring well network; groundwater monitoring data; analytical results exceeding standards; tritium, nitrate, and pH time-trend data; water levels; groundwater flow rates and directions; upgradient versus downgradient results

  10. Oak Ridge Reservation Federal Facility Agreement. Quarterly report for the Environmental Restoration Program. Volume 4, July 1995--September 1995

    International Nuclear Information System (INIS)

    1995-10-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation Federal Facility Agreement (FFA) established between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA), and the Tennessee Department of Environment and Conservation (TDEC). The reporting period covered herein is July through September 1995 (fourth quarter of FY 1995). Sections 1.1 and 1.2 provide respectively the milestones scheduled for completion during the reporting period and a list of documents that have been proposed for transmittal during the following quarter but have not been approved as FY 1995 commitments

  11. Idaho National Laboratory Quarterly Occurrence Analysis for the 1st Quarter FY2017

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 82 reportable events (13 from the 1st quarter (Qtr) of fiscal year (FY) 2017 and 68 from the prior three reporting quarters), as well as 31 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (seven from this quarter and 24 from the prior three quarters).

  12. Idaho National Laboratory Quarterly Occurrence Analysis 4th Quarter FY 2016

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System, as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 84 reportable events (29 from the 4th quarter fiscal year 2016 and 55 from the prior three reporting quarters), as well as 39 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (two from this quarter and 37 from the prior three quarters).

  13. Quarterly coal report, January--March 1992

    International Nuclear Information System (INIS)

    Young, P.

    1992-01-01

    The United States produced 257 million short tons of coal in the first quarter of 1992. This was the second highest quarterly production level ever recorded. US coal exports in January through March of 1992 were 25 million short tons, the highest first quarter since 1982. The leading destinations for US coal exports were Japan, Italy, France, and the Netherlands, together receiving 46 percent of the total. Coal exports for the first quarter of 1992 were valued at $1 billion, based on an average price of $42.28 per short ton. Steam coal exports totaled 10 million short tons, an increase of 34 percent over the level a year earlier. Metallurgical coal exports amounted to 15 million short tons, about the same as a year earlier. US coal consumption for January through March 1992 was 221 million short tons, 2 million short tons more than a year earlier (Table 45). All sectors but the residential and commercial sector reported increased coal consumption

  14. Quarterly Fishery Surveys - Salton Sea [ds428

    Data.gov (United States)

    California Natural Resource Agency — In the spring of 2003, California Department of Fish and Game (CDFG) personnel began quarterly sampling of Salton Sea fish at fourteen stations around the sea, as...

  15. NSA Diana Wueger Published in Washington Quarterly

    OpenAIRE

    Grant, Catherine L.

    2016-01-01

    National Security Affairs (NSA) News NSA Faculty Associate for Research Diana Wueger has recently had an article titled “India’s Nuclear-Armed Submarines: Deterrence or Danger?” published in the Washington Quarterly.

  16. Environmental Hazards Assessment Program. Quarterly report, July 1994--September 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The objectives of the Environmental Hazards Assessment Program (EHAP) stated in the proposal to DOE are as follows: Development of a holistic, national basis for risk assessment, risk management, and risk communication that recognizes the direct impact of environmental hazards on the health and well-being of all; development of a pool of talented scientist and experts in cleanup activities, especially in human health aspects; identification of needs and development of programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health oriented aspects of environmental restoration and waste management. This is a progress report of the first quarter of the third year of the grant. It reports progress against these grant objectives and the Program Implementation Plan (published at the end of the first year of the grant)

  17. The AMTEX Partnership{trademark}. Fourth quarter FY95 report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The AMTEX Partnership{trademark} is a collaborative research and development program among the US Integrated Textile Industry, the Department of Energy (DOE), the national laboratories, other federal agencies and laboratories, and universities. The goal of AMTEX is to strengthen the competitiveness of this vital industry, thereby preserving and creating US jobs. The operations and program management of the AMTEX Partnership{trademark} is provided by the Program Office. This report is produced by the Program Office on a quarterly basis and provides information on the progress, operations, and project management of the partnership. Progress is reported on the following projects: computer-aided fabric evaluation; cotton biotechnology; demand activated manufacturing architecture; electronic embedded fingerprints; on-line process control for flexible fiber manufacturing; rapid cutting; sensors for agile manufacturing; and textile resource conservation.

  18. Environmental Hazards Assessment Program. Quarterly report, July--September 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-31

    This report describes activities and reports on progress for the first quarter (July--September) of the fourth year of the grant to support the Environmental Hazards Assessment Program (EHAP) at the Medical University of South Carolina. It reports progress against the grant objectives and the Program Implementation Plan published at the end of the first year of the grant. The objectives of EHAP stated in the proposal to DOE are to: (1) develop a holistic, national basis for risk assessment, risk management, and risk communication that recognizes the direct impact of environmental hazards on the health and well-being of all; (2) develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects; and (3) identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health-oriented aspects of environmental restoration and waste management.

  19. BWR and ABWR operating experience

    International Nuclear Information System (INIS)

    Nagai, Kimio; Takayama, Yoshito; Shimizu, Shunichi

    1998-01-01

    The first commercial operation of a nuclear power plant in Japan was in 1969. At present, there are 52 nuclear power plants operating in the country, accounting for about 35% of the total electricity generated and about 20 % of the total capacity of electricity generation facilities in Japan. Moreover, Japan has had the highest facility utilization rate, which is an indicator of operational safety, among the top four nuclear-generation countries (U.S.A., France, Germany, and Japan) every year since 1993, and has maintained a utilization rate of more than 80% since 1995. Toshiba has supported plant operation and maintenance in 19 nuclear power plants. The overall facility utilization rate of these plants attained a record of 86.4% in fiscal 1996. Furthermore, the averaged rates over the past three fiscal years from 1995 to 1997 have been the highest in the world among plant constructors such as GE, WH, and Siemens. (author)

  20. Memphis State University Center for Nuclear Studies progress report

    International Nuclear Information System (INIS)

    1976-01-01

    This quarterly report outlines the progress made by the Center for Nuclear Studies at Memphis State University in the development of specialized educational programs for the nuclear industry through the month of February, 1976

  1. Decontamination Systems Information and Research Program: Quarterly report, July--September 1994

    International Nuclear Information System (INIS)

    1994-11-01

    West Virginia University (WVU) and the US DOE Morgantown Energy Technology Center (METC) entered into a Cooperative Agreement on August 29, 1992 entitled ''Decontamination Systems Information and Research Programs'' (DOE Instrument No.: DE-FC21-92MC29467). Stipulated within the Agreement is the requirement that WVU submit to METC a series of Technical Progress Reports on a quarterly basis. This report comprises the eighth Quarterly Technical Progress Report for the Agreement. This report reflects the progress and/or efforts performed on the 16 technical projects encompassed by the Agreement for the period of July 1 through September 30, 1994. These projects focus on the following: Bio-remediation of organic compounds, heavy metals, and radionuclides; miscellaneous remediation technologies; instrumentation; and technology assessments

  2. Idaho National Laboratory Quarterly Occurrence Analysis - 3rd Quarter FY-2016

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-09-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 73 reportable events (23 from the 3rd Qtr FY-16 and 50 from the prior three reporting quarters), as well as 45 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (16 from this quarter and 29 from the prior three quarters).

  3. Idaho National Laboratory Quarterly Occurrence Analysis - 1st Quarter FY 2016

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-03-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 74 reportable events (16 from the 1st Qtr FY-16 and 58 from the prior three reporting quarters), as well as 35 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (15 from this quarter and 20 from the prior three quarters).

  4. Federal Facility Agreement progress report

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    The (SRS) Federal Facility Agreement (FFA) was made effective by the US. Environmental Protection Agency Region IV (EPA) on August 16, 1993. To meet the reporting requirements in Section XXV of the Agreement, the FFA Progress Report was developed. The FFA Progress Report is the first of a series of quarterly progress reports to be prepared by the SRS. As such this report describes the information and action taken to September 30, 1993 on the SRS units identified for investigation and remediation in the Agreement. This includes; rubble pits, runoff basins, retention basin, seepage basin, burning pits, H-Area Tank 16, and spill areas.

  5. Federal Facility Agreement progress report

    International Nuclear Information System (INIS)

    1993-10-01

    The (SRS) Federal Facility Agreement (FFA) was made effective by the US. Environmental Protection Agency Region IV (EPA) on August 16, 1993. To meet the reporting requirements in Section XXV of the Agreement, the FFA Progress Report was developed. The FFA Progress Report is the first of a series of quarterly progress reports to be prepared by the SRS. As such this report describes the information and action taken to September 30, 1993 on the SRS units identified for investigation and remediation in the Agreement. This includes; rubble pits, runoff basins, retention basin, seepage basin, burning pits, H-Area Tank 16, and spill areas

  6. Idaho National Laboratory Quarterly Performance Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 60 reportable events (23 from the 4th Qtr FY14 and 37 from the prior three reporting quarters) as well as 58 other issue reports (including not reportable events and Significant Category A and B conditions) identified at INL from July 2013 through October 2014. Battelle Energy Alliance (BEA) operates the INL under contract DE AC07 051D14517.

  7. Quarterly coal statistics of OECD countries

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-27

    These quarterly statistics contain data from the fourth quarter 1990 to the fourth quarter 1991. The first set of tables (A1 to A30) show trends in production, trade, stock change and apparent consumption data for OECD countries. Tables B1 to B12 show detailed statistics for some major coal trade flows to and from OECD countries and average value in US dollars. A third set of tables, C1 to C12, show average import values and indices. The trade data have been extracted or derived from national and EEC customs statistics. An introductory section summarizes trends in coal supply and consumption, deliveries to thermal power stations; electricity production and final consumption of coal and tabulates EEC and Japanese steam coal and coking coal imports to major countries.

  8. ER Consolidated Quarterly Report October 2014

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-10-01

    This Environmental Restoration Operations (ER) Consolidated Quarterly Report (ER Quarterly Report) provides the status of ongoing corrective actions and related Long- Term Stewardship (LTS) activities being implemented by Sandia National Laboratories, New Mexico (SNL/NM) ER for the April, May, and June 2014 quarterly reporting period. Section 2.0 provides the status of ER Operations activities including closure activities for the Mixed Waste Landfill (MWL), project management and site closure, and hydrogeologic characterizations. Section 3.0 provides the status of LTS activities that relate to the Chemical Waste Landfill (CWL) and the associated Corrective Action Management Unit (CAMU). Section 4.0 provides the references noted in Section I of this report.

  9. Quarterly report for the electricity market. 2. quarter of 2012; Kvartalsrapport for kraftmarknaden. 2. kvartal 2012

    Energy Technology Data Exchange (ETDEWEB)

    Eliston, Anton Jaynand; Holmqvist, Erik; Lund, Per Tore Jensen; Magnussen, Ingrid; Viggen, Kjerstin Dahl; Willumsen, Mats Oeivind; Guren, Ingrid; Ulriksen, Margit Iren

    2012-07-01

    Fourth quarter of 2011 was unusually mild and wet, resulting in high energy inflow to the Norwegian reservoirs. Total inflow for the year was 149.2 TWh, 26.7 TWh more than normal. This ensured record-high 80.3 percent load factor at the end of the quarter.The stored energy amount in the reservoirs was thus 29.5 TWh greater than at the end of 2010/2011. Norway had a power consumption of 34.1 TWh in the fourth quarter. Compared with the same quarter of 2010, a decrease of 4.2 TWh, which can be connected to the mild weather development. The total Norwegian electricity consumption in 2011 was 125.1 TWh, or 6.9 TWh less than in 2010. Electricity production in the fourth quarter of 2011 was 38.3 GWh, an increase of 3.7 TWh from the same quarter the year before. The production increase were a result of the large volume of water in the system. Power production for the year 2011 was 128.1 TWh, an increase of 3.7 TWh from 2010. Kraft surplus was therefore large, and it was Norwegian net export of 4.2 TWh in the fourth quarter, and 3.0 TWh total for the year. In comparison, in the fourth quarter of 2010 Norwegian net import of 0.8 TWh and 7.5 TWh annually. The good resource combined with the low consumption gave a unusually low price levels in the wholesale market for electricity. On average for fourth quarter, the price of power in the East and South-East Norway Nok 264 / MWh, in western Norway Nok 260 / MWh, in Central Norway Nok 270 / MWh (eb)

  10. Quarterly report for the electricity market. 1. quarter of 2012; Kvartalsrapport for kraftmarknaden. 1. kvartal 2012

    Energy Technology Data Exchange (ETDEWEB)

    Pettersen, Finn Erik Ljaastad; Eliston, Anton Jaynanand; Guren, Ingri; Homqvist, Erik; Lund, Per Tore Jensen; Magnussen, Ingrid; Rasmussen, Kristian; Ulriksen, Margit Iren

    2012-07-01

    The first quarter of 2012 was unusually mild and wetter than normal. Total inflow was 16.8 TWh, 7.5 TWh more than normal. This ensured a high reservoir levels and at the end of the quarter the filling was 50.5 percent. It is 12.5 percentage points over the normal for the time of year and 32.4 percentage points higher than the same time last year. Norway had a power consumption of 37.5 TWh in the first quarter, which is 2.3 percent less than in the same quarter last year. the past 12 months, consumption has been 124.2 TWh, compared with 129.7 TWh the preceding 12 months. Power production in Norway was 42.3 TWh in the first quarter - an increase of 32.3 percent compared with the same quarter last year. The last 12 months have the Norwegian production been 138.5 TWh compared to 117.7 TWh the the previous 12 months. The production increase is due to milder and wetter weather than normal over the past year. This involvement also high the exports abroad. In the first quarter, Norway had a net export of 4.8 TWh, compared with a net import of 6.4 TWh in the first quarter last year. The good resource, combined with a low consumption gave a low price level in wholesale market for electricity. On average for the fourth quarter was the average spot price in the South and West Norway, Nok 272 and 275 / MWh. In Eastern Norway, the average price of Nok 283 / MWh, while it was Nok 285 / MWh in the Middle and Northern Norway. (Author)

  11. Quarterly report for the electricity market. 2. quarter of 2012; Kvartalsrapport for kraftmarknaden. 2. kvartal 2012

    Energy Technology Data Exchange (ETDEWEB)

    Pettersen, Finn Erik Ljaastad; Eliston, Anton Jayanand; Vaeringstad, Thomas; Lund, Per Tore Jensen; Magnussen, Ingrid; Langseth, Benedicte; Willumsen, Mats Oeivind; Rasmussen, Kristian; Guren, Ingri

    2012-07-01

    Second quarter of 2012 was cold. Total inflow was 47.0 TWh, 8.8 TWh less than normal. At the end of the quarter, the reservoir level 68.4 percent. It is 1.8 percentage points above normal for time of year and 1.2 percentage points higher than the same time last year. Norway had a power consumption of 28.2 TWh in the second quarter, which is 4.2 percent higher than in the same quarter last year. The last 12 months the consumption have been 125.7 TWh, compared with 128.7 TWh the preceding 12 months. The power production in Norway was 33.3 TWh in the second quarter - an increase of 26.1 percent compared with the same quarter last year. The last 12 months the Norwegian production has been 145.8 TWh, compared with 120.9 TWh the preceding 12 months. The production increase is due to that the last year has been much wetter than the preceding. This has also given high export abroad. In the second quarter Norway had a net export of 5.1 TWh, compared with a net import of 0.6 TWh in the second quarter last year. The good resource gave a low price level in the wholesale market for electricity. On average for the second quarter was the average spot price in West, Southwest and Eastern Norway, 201, 202 and 203 Nok / MWh. In Central and Northern Norway, the average price 218 and 213 Nok/ MWh. (eb)

  12. Ocean energy systems. Quarterly report, October-December 1982

    Energy Technology Data Exchange (ETDEWEB)

    1982-12-01

    Research progress is reported on developing Ocean Thermal Energy Conversion (OTEC) systems that will provide synthetic fuels (e.g., methanol), energy-intensive products such as ammonia (for fertilizers and chemicals), and aluminum. The work also includes assessment and design concepts for hybrid plants, such as geothermal-OTEC (GEOTEC) plants. Another effort that began in the spring of 1982 is a technical advisory role to DOE with respect to their management of the conceptual design activity of the two industry teams that are designing offshore OTEC pilot plants that could deliver power to Oahu, Hawaii. In addition, a program is underway in which tests of a different kind of ocean-energy device, a turbine that is air-driven as a result of wave action in a chamber, are being planned. This Quarterly Report summarizes the work on the various tasks as of 31 December 1982.

  13. Coal gasification. Quarterly report, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    The conversion of coal to high-Btu gas requires a chemical and physical transformation of solid coal. However, because coal has widely differing chemical and physical properties, depending on where it is mined, it is difficult to process. Therefore, to develop the most suitable techniques for gasifying coal, ERDA, together with the American Gas Association, is sponsoring the development of several advanced conversion processes. Although the basic coal-gasification chemical reactions are the same for each process, the processes under development have unique characteristics. A number of the processes for converting coal to high Btu and to low Btu gas have reached the pilot plant stage. The responsibility for designing, constructing and operating each of these pilot plants is defined and progress on each during the quarter is described briefly. The accumulation of data for a coal gasification manual and the development of mathematical models of coal gasification processes are reported briefly. (LTN)

  14. Environmental Hazards Assessment Program. Quarterly report, April--June 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-31

    The objectives of this report are to: (1) develop a holistic, national basis for risk assessment, risk management, and risk communication that recognizes the direct impact of environmental hazards, both chemical and radiation, on the health and well-being of all; (2) develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects; and (3) identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health oriented aspects of environmental restoration and waste management. This report describes the progress made this quarter in the following areas: public and professional outreach; science programs; clinical programs; and information support and access systems.

  15. Mineral exploration, Australia, March quarter 1983

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    This publication contains annual and quarterly statistics of exploration for minerals in Australia. Part 1 sets out statistics of exploration for minerals and oil shale for which data are no longer available for separate publication. Part 2 gives details of petroleum exploration.

  16. 39 CFR 243.2 - Quarters.

    Science.gov (United States)

    2010-07-01

    ... UNITED STATES POSTAL SERVICE ORGANIZATION AND ADMINISTRATION CONDUCT OF OFFICES § 243.2 Quarters. (a.... Postal Service, General Accounting Office Building, Washington, DC 20260, with a memorandum of... depositing mail in front of or next to the post office. Show collection time schedules on letterboxes. At...

  17. "The Career Development Quarterly": A Centennial Retrospective

    Science.gov (United States)

    Savickas, Mark L.; Pope, Mark; Niles, Spencer G.

    2011-01-01

    "The Career Development Quarterly" has been the premier journal in the field of vocational guidance and career intervention since its inception 100 years ago. To celebrate its centennial, 3 former editors trace its evolution from a modest and occasional newsletter to its current status as a major professional journal. They recount its history of…

  18. 76 FR 22910 - ACHP Quarterly Business Meeting

    Science.gov (United States)

    2011-04-25

    ... ADVISORY COUNCIL ON HISTORIC PRESERVATION ACHP Quarterly Business Meeting AGENCY: Advisory Council on Historic Preservation. ACTION: Notice. SUMMARY: Notice is hereby given that the Advisory Council... Historic Preservation Working Group IX. New Business X. Adjourn Note: The meetings of the ACHP are open to...

  19. Subject Access Project. Third Quarterly Report.

    Science.gov (United States)

    Atherton, Pauline

    This third quarterly report for the period January to March 1977 describes the production schedule, records, and estimated costs and times in creating the Subject Access Project data base. Plans for on-line use of the data base and search strategy design are outlined. A table of specifications for preparing the data base for on-line searching is…

  20. State of development progress of advanced boiling water reactors

    International Nuclear Information System (INIS)

    Tomono, Katsuya

    1982-01-01

    Advanced BWRs being developed at present are those aiming at the improvement of reliability and safety, the reduction of radiation exposure, the improvement of operation performance and capacity ratio of plants, and the heightening of economical efficiency by concentrating the experience and excellent technology of BWR manufacturers in the world. Now in Japan, the independence with Japanese technology is possible in almost all fields of nuclear power generation, and the improvement and standardization project is in progress to obtain the steady results. However, in order to pursue the most desirable BWRs conceivable at present, five BWR manufacturers in the world organized the Advanced Engineering Team in July, 1978, and performed the feasibility study of advanced BWRs for more than one year. Tokyo Electric Power Co., Inc., evaluated the report on the results, and judged that it is desirable to advance into the next stage aiming at the practical use of advanced BWRs. For the purpose, the electric power common research on advanced BWRs has been in progress, and the A-BWR project is to be examined in the third improvement and standardization project of MITI. The main technical features such as the coolant recirculation system of internal pump type, reinforced concrete containment vessels, fine motion control rod drive, improved core and fuel and others are explained. (Kako, I.)