Unit: Plants, Inspection Pack, National Trial Print.

Science.gov (United States)

Australian Science Education Project, Toorak, Victoria.

This is a National Trial Print of a unit on plants produced as a part of the Australian Science Education Project. The unit consists of an information booklet for students, a booklet for recording student data, and a teacher's guide. The material, designed for use with students in the upper elementary grades, takes from 15 to 20 forty-minute…

Mobile power plant units

Energy Technology Data Exchange (ETDEWEB)

Radtke, R

1979-10-05

Diesel engines of the MaK line 282 AK/332 with a cylinder power up to 160 kW are used, either as 6-cylinder or 8-cylinder in-line engine or as 12-cylinder V engine. Fuel consumption is between 207 and 212 g/kW. The engine is mounted on a frame, together with a generator. The fuel reserve in the tank will last for 8 hours. The lubricating system, the cooling water and starting air system, the switchboard system, and the frame are described. The switchboard plant is mounted either on a skid undercarriage or on the undercarriage. The plant can be operated independently or parallel to the network. The unit can be remote-controlled via push buttons or control knobs. A picture is presented of a mobile diesel aggregate which is in service in Libya.

75 FR 66802 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2010-10-29

... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Notice of Withdrawal of...) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC, the licensee, to withdraw its... for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, located in Calvert County, MD. The...

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-12-01

During the second quarter of 1990 the Finnish nuclear plant units Loviisa 1 and 2 and TVO and II were in commercial operation for most of the time. The feedwater pipe rupture at Loviisa 1 and the resulting inspections and repairs at both Loviisa plant units brought about an outage the overall duration of which was 32 days. The annual maintenance outages of the TVO plant units were arranged during the report period and their combined duration was 31.5 days. Nuclear electricity accounted for 35.3% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 83.0%. Three events occurred during the report period which are classified as Level 1 on the International Nuclear Event Scale: feedwater pipe rupture at Loviisa 1, control rod withdrawal at TVO I in a test during an outage when the hydraulic scram system was rendered inoperable and erroneous fuel bundle transfers during control rod drives maintenance at TVO II. Other events during this quarter are classified as Level Zero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. Only small amounts of nuclides originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

Mechanisms of energy transfer and conversion in plant Light-Harvesting Complex II

Energy Technology Data Exchange (ETDEWEB)

Barros, Tiago Ferreira de

2009-09-24

The light-harvesting complex of photosystem II (LHC-II) is the major antenna complex in plant photosynthesis. It accounts for roughly 30% of the total protein in plant chloroplasts, which makes it arguably the most abundant membrane protein on Earth, and binds about half of plant chlorophyll (Chl). The complex assembles as a trimer in the thylakoid membrane and binds a total of 54 pigment molecules, including 24 Chl a, 18 Chl b, 6 lutein (Lut), 3 neoxanthin (Neo) and 3 violaxanthin (Vio). LHC-II has five key roles in plant photosynthesis. It: (1) harvests sunlight and transmits excitation energy to the reaction centres of photosystems II and I, (2) regulates the amount of excitation energy reaching each of the two photosystems, (3) has a structural role in the architecture of the photosynthetic supercomplexes, (4) contributes to the tight appression of thylakoid membranes in chloroplast grana, and (5) protects the photosynthetic apparatus from photo damage by non photochemical quenching (NPQ). A major fraction of NPQ is accounted for its energy-dependent component qE. Despite being critical for plant survival and having been studied for decades, the exact details of how excess absorbed light energy is dissipated under qE conditions remain enigmatic. Today it is accepted that qE is regulated by the magnitude of the pH gradient ({delta}pH) across the thylakoid membrane. It is also well documented that the drop in pH in the thylakoid lumen during high-light conditions activates the enzyme violaxanthin de-epoxidase (VDE), which converts the carotenoid Vio into zeaxanthin (Zea) as part of the xanthophyll cycle. Additionally, studies with Arabidopsis mutants revealed that the photosystem II subunit PsbS is necessary for qE. How these physiological responses switch LHC-II from the active, energy transmitting to the quenched, energy-dissipating state, in which the solar energy is not transmitted to the photosystems but instead dissipated as heat, remains unclear and is the

Experience gathered from the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type

International Nuclear Information System (INIS)

Pastorini, A.; Belinco, C.G.; El Bis, E.D.; Sacchi, M.A.; Mayans, C.O.; Martin Ghiselli, A.; Marcora, G.R.

1990-01-01

This work describes the needs to materialize the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type, under special conditions, from the Fabrication Pilot Plant sited at the Constituyentes Atomic Center and the Ezeiza Atomic Center, for its subsequent analysis at the High Pressure Experimental Loop. The special conditions under which the transport has been made responded to the fact that the prototype presents a fragile adjustment between rods and separators, necessary to be preserved. (Author) [es

Operation of Finnish nuclear power plants. Quarterly report 3rd, quarter 1995

Energy Technology Data Exchange (ETDEWEB)

Sillanpaeae, T [ed.

1996-05-01

Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The Report includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants` production and load factors. Except for the annual maintenance outages of Loviisa plant units and for TVO II`s brief outage to repair a failed component, Finnish nuclear power plant units were in power operation in the third quarter of 1995. The load factor average of all plant units was 90.4 %. Events in this quarter were level 0 on the INES scale. Occupational doses and radioactive releases off-site were below authorised limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.) (4 figs., 4 tabs.).

Environmental Impact Assessment for Olkiluoto 4 Nuclear Power Plant Unit in Finland

International Nuclear Information System (INIS)

Dersten, Riitta; Gahmberg, Sini; Takala, Jenni

2008-01-01

In order to improve its readiness for constructing additional production capacity, Teollisuuden Voima Oyj (TVO) initiated in spring 2007 the environmental impact assessment procedure (EIA procedure) concerning a new nuclear power plant unit that would possibly be located at Olkiluoto. When assessing the environmental impacts of the Olkiluoto nuclear power plant extension project, the present state of the environment was first examined, and after that, the changes caused by the projects as well as their significance were assessed, taking into account the combined impacts of the operations at Olkiluoto. The environmental impact assessment for the planned nuclear power plant unit covers the entire life cycle of the plant unit. (authors)

Environmental Impact Assessment for Olkiluoto 4 Nuclear Power Plant Unit in Finland

Energy Technology Data Exchange (ETDEWEB)

Dersten, Riitta; Gahmberg, Sini; Takala, Jenni [Teollisuuden Voima Oyj, Olkiluoto, FI-27160 Eurajoki (Finland)

2008-07-01

In order to improve its readiness for constructing additional production capacity, Teollisuuden Voima Oyj (TVO) initiated in spring 2007 the environmental impact assessment procedure (EIA procedure) concerning a new nuclear power plant unit that would possibly be located at Olkiluoto. When assessing the environmental impacts of the Olkiluoto nuclear power plant extension project, the present state of the environment was first examined, and after that, the changes caused by the projects as well as their significance were assessed, taking into account the combined impacts of the operations at Olkiluoto. The environmental impact assessment for the planned nuclear power plant unit covers the entire life cycle of the plant unit. (authors)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-02-01

During the third quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. The annual maintenance outages of the Loviisa plant units were held during the report period. All events during this quarter are classified as Level hero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were below authorised limits. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

Economic evaluation of Kori and Wolsong Unit 1 plant life extension

International Nuclear Information System (INIS)

Song, T. H.; Jeong, I. S.

2002-01-01

24 years have been passed since Kori Unit 1 began its commercial operation, and 19 years have been passed since Wolsong Unit 1 began its commercial operation. As the end point of design life become closer, plant life extension and periodic safety assessment is paid more and more attention to by the utility company. In this paper, the methodologies and results of plant lifetime management economic evaluations of both units have been presented in comparison with Korean standard nuclear power plant 10, 20 and 30 year life extension cases respectively. In addition to that, sensitivity analysis and break even point analysis results are presented with the variables of capacity factor, operation and maintenance cost, and discount rate

B Plant treatment, storage, and disposal (TSD) units inspection plan

International Nuclear Information System (INIS)

Beam, T.G.

1996-01-01

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ''Dangerous Waste Regulations'' (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements

Experiences in commissioning and in the first operating cycle of GKN-II

International Nuclear Information System (INIS)

Grauf, E.; Zaiss, W.; Tschannerl, J.

1990-01-01

In 1989, after only four and a half years of construction, the second unit of the Neckar Joint Nuclear Power Station (GKN-II) was commissioned as the third convoy type nuclear power plant. Its gross power of 1314 MWe makes the pressurized water reactor of GKN-II a unit in the highest power category so far of Siemens/KWU. Delivery to the operators ahead of schedule and observance of the budget are conclusive proof of the advantages of the convoy principle. In addition, GKN-II was able to benefit from the experience accumulated in the construction and commissioning of the two earlier convoy plants. This was reflected in the speedy completion, without major disturbances, of the warranty tests and the trial period of operation. It also has an impact on power operation, the first cycle of which showed the plant to have an availability of 100% throughout and is considered to be a full success by the operators. A special feature of GKN-II is the hybrid cooling tower ensuring that no heated cooling water is returned from the plant into the Neckar river. (orig.) [de

Peer review of the Barselina Level 1 probabilistic safety assessment of the Ignalina Nuclear Power Plant, Unit 2

International Nuclear Information System (INIS)

McKay, S.L.; Coles, G.A.

1995-01-01

The Barselina Project is a Swedish-funded, cooperative effort among Lithuania, Russia and Sweden to transfer Western probabilistic safety assessment (PSA) methodology to the designers/operators of Ignalina Nuclear Power Plant (INPP). The overall goal is to use the PSA as a tool for assessing plant operational safety. The INPP is a two-unit, Former Soviet Union-designed nuclear facility located in Lithuania. The results of this PSA will ultimately be used to identify plant-specific improvements in system design and the conduct of facility operations, allowing improved operational safety. Pacific Northwest Laboratory (PNL) was asked to perform an independent expert peer review of the Barselina PSA. This report documents the findings of this review. This review, financed with nuclear safety assistance funds through the US Agency for International Development (USAID) and the US Department of Energy (DOE), satisfies Task II of the PNL peer review of the Barselina project. The objective is to provide an independent, in-proce ss examination of the Barselina Level 1 PSA of Ignalina Nuclear Power Plant, Unit 2. The review consisted of an investigation of the project documentation, interviews, and extensive discussions with the PSA staff during critical stages of the project. PNL assessed the readability, completeness, consistency, validity, and applicability of the PSA. The major aspects explored were its purpose, major assumptions, analysis/modeling, results, and interpretation. It was not within the scope of this review to perform plant walkdowns or to review material other than the PSA documentation

Nuclear power plant life extension in the United Kingdom

International Nuclear Information System (INIS)

Goodison, D.; Seddon, J.W.; Pape, E.M.

1991-01-01

The safety cases for the United Kingdom's older nuclear power plant have been reviewed by their utilities in order to justify continued operation of the reactors up to an age of at least 30 year. These 'long term safety reviews' have identified worthwhile plant modifications and aspects where further studies or plant inspections are required. As the plants approach the age of 30 years, 'life extension reviews' are now being undertaken, concentrating on management of ageing, to support operation to at least 40 years. (author)

Potential safety enhancements to nuclear plant control: proof testing at EBR-II

International Nuclear Information System (INIS)

Lindsay, R.W.; Chisholm, G.H.

1984-01-01

Future changes in nuclear plant control and protective systems will reflect an evolutionary improvement through increased use of computers coupled with a better integration of man and machine. Before improvements can be accepted into the licensed commercial plant environment, significant testing must be accomplished to answer safety questions and to prove the worth of new ideas. The Experimental Breeder Reactor-II (EBR-II) is being used as a test-bed for both in-house development and testing for others in a DOE sponsored Man-Machine Integration program. The ultimate result of the development and testing would be a control system for which safety credit could be taken in the licensing process

Structure and membrane organization of photosystem II in green plants

NARCIS (Netherlands)

Hankamer, B; Barber, J; Boekema, EJ

1997-01-01

Photosystem II (PSII) is the pigment protein complex embedded in the thylakoid membrane of higher plants, algae, and cyanobacteria that uses solar energy to drive the photosynthetic water-splitting reaction. This chapter reviews the primary, secondary, tertiary, and quaternary structures of PSII as

Construction and analysis of the transgenic carrot and celery plants expressing the recombinant thaumatin II protein

Directory of Open Access Journals (Sweden)

Luchakivska Yu. S.

2015-08-01

Full Text Available Aim To obtain the transgenic carrot and celery plants able to express recombinant thaumatin II in order to increase plant stress tolerance. Methods. Agrobacterium-mediated transformation of the carrot and celery seedlings was used for obtaining the transgenic plants. Presence and transcription of the transgene in plant tissues were proved by PCR and RT-PCR analysis. The plants were tested for the biotic stress tolerance by in vitro antifungal and antibacterial activity assays and for the salinity and osmotic stress tolerance by plant survival test in presence of NaCl and PEG in different concentrations. Results. Transgenic plants able to express recombinant thaumatin II gene (transcription proved for 60–100 % were obtained by agrobacterial transformation. The transgenic carrot plant extracts inhibited the growth of the studied phytopathogenic bacteria strains but exhibited no antifungal activity. Survival level of transgenic plants under the salinity and osmotic stress effect was definitely higher comparing to the untransgenic ones. The analysis of the photosynthetic pigment content in the transgenic carrot plants showed no significant difference of this parameter under salinity stress that may indicate a possible protective activity of the recombinant protein. Conclusions. The obtained in our study transgenic carrot and celery plants able to express the recombinant thaumatin II gene were characterized by antibacterial activity and increased tolerance to salinity and osmotic stress factors.

Primary water chemistry control at units of Paks Nuclear Power Plant

International Nuclear Information System (INIS)

Schunk, J.; Patek, G.; Pinter, T.; Tilky, P.; Doma, A.; Osz, J.

2010-01-01

The primary water chemistry of the four identical units of Paks Nuclear Power Plant has been developed based on Western-type PWR units, taking into consideration some Soviet-Russian modifications. The political changes in 90s have also influenced the water chemistry specifications and directions. At PWR units the transition operational modes have been developed while in case of VVER units - in lack of central uniform regulation - this question has become the competence and responsibility of each individual plant. This problem has resulted in separate water chemistry developments with a considerable time delay. The needs for life-time extensions all over the World have made the development of start-up and shut-down chemistry procedures extremely important, since they considerably influence the long term and safe operation of plants. The uniformly structured limit value system, the principles applied for the system development, and the logic schemes for actions to be taken are discussed in the paper, both for normal operation and transition modes. (author)

Primary Water Chemistry Control at Units of Paks Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Schunk, J.; Pinter, G. Patek T.; Tilky, P.; Doma, A. [Paks Nuclear Power Plant Co. Ltd., Paks (Hungary); Osz, J. [Budapest University of Technology and Economics, Budapest (Hungary)

2013-03-15

The primary water chemistry of the four identical units of Paks Nuclear Power Plant has been developed based on Western type PWR units, taking into consideration some Russian modifications. The political changes in the 1990s have also influenced the water chemistry specifications and directions. At PWR units the transition operational modes have been developed while in case of WWER units - in lack of central uniform regulation - this question has become the competence and responsibility of each individual plant. This problem has resulted in separate water chemistry developments with a considerable time delay. The need for lifetime extensions worldwide has made the development of startup and shutdown chemistry procedures extremely important, since they considerably influence the long term and safe operation of plants. The uniformly structured limit value system, the principles applied for the system development, and the logic schemes for actions to be taken are discussed in the paper, both for normal operation and transition modes. (author)

Electrochemical Microsensors for the Detection of Cadmium(II and Lead(II Ions in Plants

Directory of Open Access Journals (Sweden)

Olga Krystofova

2010-05-01

Full Text Available Routine determination of trace metals in complex media is still a difficult task for many analytical instruments. The aim of this work was to compare three electro-chemical instruments [a standard potentiostat (Autolab, a commercially available miniaturized potentiostat (PalmSens and a homemade micropotentiostat] for easy-to-use and sensitive determination of cadmium(II and lead(II ions. The lowest detection limits (hundreds of pM for both metals was achieved by using of the standard potentiostat, followed by the miniaturized potentiostat (tens of nM and the homemade instrument (hundreds of nM. Nevertheless, all potentiostats were sensitive enough to evaluate contamination of the environment, because the environmental limits for both metals are higher than detection limits of the instruments. Further, we tested all used potentiostats and working electrodes on analysis of environmental samples (rainwater, flour and plant extract with artificially added cadmium(II and lead(II. Based on the similar results obtained for all potentiostats we choose a homemade instrument with a carbon tip working electrode for our subsequent environmental experiments, in which we analyzed maize and sunflower seedlings and rainwater obtained from various sites in the Czech Republic.

CNSS plant concept, capital cost, and multi-unit station economics

Energy Technology Data Exchange (ETDEWEB)

1984-07-01

United Engineers and Constructors (UE and C) and the Babcock and Wilcox Company (B and W) have performed several studies over the last eight years related to small integral pressurized water reactors. These reactors include the 365 MWt (100 MWe) Consolidated Nuclear Steam Generator (CNSG) and the 1200 MWt Consolidated Nuclear Steam System (CNSS). The studies, mostly performed under contract to the Oak Ridge National Laboratory, have led to a 1250 MWt (400 MWe) Consolidated Nuclear Steam System (CNSS) plant concept, with unique design and cost features. This report contains an update of earlier studies of the CNSS reactor and balance-of-plant concept design, capital costs, and multi-unit plant economics incorporating recent design developments, improvements, and post-TMI-2 upgrades. The economic evaluation compares the total system economic impact of a phased, three stage 400 MWe CNSS implementation program, i.e., a three-unit station, to the installation of a single 1200 MWe Pressurized Water Reactor (PWR) into a typical USA utility system.

CNSS plant concept, capital cost, and multi-unit station economics

International Nuclear Information System (INIS)

1984-07-01

United Engineers and Constructors (UE and C) and the Babcock and Wilcox Company (B and W) have performed several studies over the last eight years related to small integral pressurized water reactors. These reactors include the 365 MWt (100 MWe) Consolidated Nuclear Steam Generator (CNSG) and the 1200 MWt Consolidated Nuclear Steam System (CNSS). The studies, mostly performed under contract to the Oak Ridge National Laboratory, have led to a 1250 MWt (400 MWe) Consolidated Nuclear Steam System (CNSS) plant concept, with unique design and cost features. This report contains an update of earlier studies of the CNSS reactor and balance-of-plant concept design, capital costs, and multi-unit plant economics incorporating recent design developments, improvements, and post-TMI-2 upgrades. The economic evaluation compares the total system economic impact of a phased, three stage 400 MWe CNSS implementation program, i.e., a three-unit station, to the installation of a single 1200 MWe Pressurized Water Reactor (PWR) into a typical USA utility system

Optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 with an optimized cost perspective

International Nuclear Information System (INIS)

Jinil Mok; Poong Hyun Seong

1996-01-01

In this work, a model for determining the optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 is developed, which is to minimize economic loss caused by inadvertent trip and the system failure. This model uses cost benefit analysis method and the part for optimal inspection period considers the human error. The model is based on three factors as follows: (i) The cumulative failure distribution function of the safety system, (ii) The probability that the safety system does not operate due to failure of the system or human error when the safety system is needed at an emergency condition and (iii) The average probability that the reactor is tripped due to the failure of system components or human error. The model then is applied to evaluate the safety system in Wolsung Nuclear Power Plant Unit 1. The optimal replacement periods which are calculated with proposed model differ from those used in Wolsung NPP Unit 1 by about a few days or months, whereas the optimal inspection periods are in about the same range. (author)

Knowledge acquisition for nuclear power plant unit diagnostic system

International Nuclear Information System (INIS)

Li Xiaodong; Xi Shuren

2003-01-01

The process of acquiring knowledge and building a knowledge base is critical to realize fault diagnostic system at unit level in a nuclear power plant. It directly determines whether the diagnostic system can be applied eventually in a commercial plant. A means to acquire knowledge and its procedures was presented in this paper for fault diagnostic system in a nuclear power plant. The work can be carried out step by step and it is feasible in a commercial nuclear power plant. The knowledge base of the fault diagnostic system for a nuclear power plant can be built after the staff finish the tasks according to the framework presented in this paper

Evaluation of Watts Bar Nuclear Plant Unit 1 Technical Specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-08-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Watts Bar Nuclear Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumption of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Watts Bar T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Watts Bar Nuclear Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Pengaruh Curah Hujan Dan Hari Hujan Terhadap Produksi Kelapa Sawit Berumur 12,15,18 Tahun Di PTPN II Unit Sawit Seberang – Babalan Kecamatan Sawit Seberang Kabupaten Langkat

OpenAIRE

Depari, Cecilia Natalenta; Irsal, Irsal; Ginting, Jonis

2015-01-01

The climate factor is very influential to the growth and productivity of palm oil. Rainfall is animportant climatic element observed. Where the palm oil is a plant that requires large amounts ofwater than other crops. Purpose of this research was to determine the effect of rainfall and rain dayas well as the correlation of both on palm oil production in plants aged 12, 15 and 18 years. Thisresearch was held at PTPN II Unit Sawit Seberang–Babalan Sub-district Sawit Seberang DistrictLangkat Pro...

Functional architecture of higher plant photosystem II supercomplexes

OpenAIRE

Caffarri, Stefano; Kouřil, Roman; Kereïche, Sami; Boekema, Egbert J; Croce, Roberta

2009-01-01

Photosystem II (PSII) is a large multiprotein complex, which catalyses water splitting and plastoquinone reduction necessary to transform sunlight into chemical energy. Detailed functional and structural studies of the complex from higher plants have been hampered by the impossibility to purify it to homogeneity. In this work, homogeneous preparations ranging from a newly identified particle composed by a monomeric core and antenna proteins to the largest C2S2M2 supercomplex were isolated. Ch...

China's Propaganda in the United States during World War II.

Science.gov (United States)

Tsang, Kuo-jen

Drawing data from a variety of sources, a study was undertaken to place China's propaganda activities in the United States during World War II into a historical perspective. Results showed that China's propaganda efforts consisted of official and unofficial activities and activities directed toward overseas Chinese. The official activities were…

FITOHORMONII – MODULATORI AI ACTIVITĂŢII ENZIMELOR ANTIOXIDANTE LA PLANTE ÎN CONDIŢII DE SECETĂ

Directory of Open Access Journals (Sweden)

Anastasia ŞTEFÎRŢĂ

2016-02-01

Full Text Available În experienţe realizate în diferite condiţii de umiditate s-a demonstrat că deshidratarea plantelor de Ph.vulgaris L., cauzată de secetă, este asociată cu intensificarea formării speciilor reactive de oxigen (SRO şi a destrucţiei oxidative a structurilor celulare. Utilizarea exogenă a fitohormonilor (AIA, CK, GA3 minimizează producerea SRO şi reduce oxi­darea peroxidică a lipidelor din membranele celulare. Optimizarea capacităţii de protecţie de la stresul oxidativ sub in­fluenţa fitohormonilor este o consecinţă a ameliorării statusului apei şi a intensificării activităţii enzimelor antioxidante. THE PHYTOHORMONES – MODULATORS OF PLANTS ANTIOXIDANT ENZYMES ACTIVITY IN DROUGHT CONDITIONSIn experiments conducted under different conditions of moisture has been demonstrated, that dehydration plant Ph. vulgaris L. caused by drought, is associated with intensification of reactive oxygen species formation (ROS and oxidative cell destruction. The use of exogenous phytohormones (IAA, CK, GA3 minimizes the production of ROS and of peroxide oxidation lipids. The optimization of antioxidant protection by the exogenous phytohormones is a consequence of improving the water status and enhancing of the antioxidant enzymes activity. 

Plutonium Finishing Plant (PFP) Treatment and Storage Unit Waste Analysis Plan

International Nuclear Information System (INIS)

PRIGNANO, A.L.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Plutonium Finishing Plant Treatment and Storage Unit (PFP Treatment and Storage Unit) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (4)(a) and (5). The PFP Treatment and Storage Unit is an interim status container management unit for plutonium bearing mixed waste radiologically managed as transuranic (TRU) waste. TRU mixed (TRUM) waste managed at the PFP Treatment and Storage Unit is destined for the Waste Isolation Pilot Plant (WIPP) and therefore is not subject to land disposal restrictions [WAC 173-303-140 and 40 CFR 268]. The PFP Treatment and Storage Unit is located in the 200 West Area of the Hanford Facility, Richland Washington (Figure 1). Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

System and Software Design for the Plant Protection System for Shin-Hanul Nuclear Power Plant Units 1 and 2

International Nuclear Information System (INIS)

Hwang, In Seok; Kim, Young Geul; Choi, Woong Seock; Sohn, Se Do

2015-01-01

The Reactor Protection System(RPS) protects the core fuel design limits and reactor coolant system pressure boundary for Anticipated Operational Occurrences (AOOs), and provides assistance in mitigating the consequences of Postulated Accidents (PAs). The ESFAS sends the initiation signals to Engineered Safety Feature - Component Control System (ESF-CCS) to mitigate consequences of design basis events. The Common Q platform Programmable Logic Controller (PLC) was used for Shin-Wolsung Nuclear Power Plant Units 1 and 2 and Shin-Kori Nuclear Power Plant Units 1, 2, 3 and 4 since Digital Plant Protection System (DPPS) based on Common Q PLC was applied for Ulchin Nuclear Power Plant Units 5 and 6. The PPS for Shin-Hanul Nuclear Power Plant Units 1 and 2 (SHN 1 and 2) was developed using POSAFE-Q PLC for the first time for the PPS. The SHN1 and 2 PPS was delivered to the sites after completion of Man Machine Interface System Integrated System Test (MMIS-IST). The SHN1 and 2 PPS was developed to have the redundancy in each channel and to use the benefits of POSAFE-Q PLC, such as diagnostic and data communication. The PPS application software was developed using ISODE to minimize development time and human errors, and to improve software quality, productivity, and reusability

System and Software Design for the Plant Protection System for Shin-Hanul Nuclear Power Plant Units 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Hwang, In Seok; Kim, Young Geul; Choi, Woong Seock; Sohn, Se Do [KEPCO EnC, Daejeon (Korea, Republic of)

2015-10-15

The Reactor Protection System(RPS) protects the core fuel design limits and reactor coolant system pressure boundary for Anticipated Operational Occurrences (AOOs), and provides assistance in mitigating the consequences of Postulated Accidents (PAs). The ESFAS sends the initiation signals to Engineered Safety Feature - Component Control System (ESF-CCS) to mitigate consequences of design basis events. The Common Q platform Programmable Logic Controller (PLC) was used for Shin-Wolsung Nuclear Power Plant Units 1 and 2 and Shin-Kori Nuclear Power Plant Units 1, 2, 3 and 4 since Digital Plant Protection System (DPPS) based on Common Q PLC was applied for Ulchin Nuclear Power Plant Units 5 and 6. The PPS for Shin-Hanul Nuclear Power Plant Units 1 and 2 (SHN 1 and 2) was developed using POSAFE-Q PLC for the first time for the PPS. The SHN1 and 2 PPS was delivered to the sites after completion of Man Machine Interface System Integrated System Test (MMIS-IST). The SHN1 and 2 PPS was developed to have the redundancy in each channel and to use the benefits of POSAFE-Q PLC, such as diagnostic and data communication. The PPS application software was developed using ISODE to minimize development time and human errors, and to improve software quality, productivity, and reusability.

Evaluation of Perry Nuclear Power Plant Unit 1 technical specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-11-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Perry Nuclear Power Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Perry T/S. Several discrepancies were identified and subsequently resolved through telephone conversations with the staff reviewer and the utility representative. Pending completion of the resolutions noted in Parts 3 and 4 of this report, the Perry Nuclear Power Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Revitalization of Tuzla Thermal Power Plant's Unit 3 (100 MW)

International Nuclear Information System (INIS)

Sakovic, A.; Praso, N.

1998-01-01

Power Plant Revitalization is a highly ranged concept essentially aimed at continued operations of the generating unit at, or near, rated capacities for the rest of the economic life of the plant or even for an extended life. In essence, the need to rehabilitate may arise due to reasons such as low availability factor, low efficiency, increasing operating and maintenance costs, loss of reliability, drop in safety of plant and personnel, poor maintainability or environmental requirements. The term revitalization is therefore normally used in the context to cover the range of activities including repairing components, replacing equipment, modifying systems, adding new system and equipment and perhaps restoration to rated capacities. This exercise on already complex power generation process will naturally require the application of various technologies in order to ensure a safe and efficient installation of electricity supply. In normal conditions of producing and consumption of electricity (load demands) in order to answer the question of what kind of revitalization to undertake it is necessary to state at the very beginning: - whether it is necessary, from the point of equipment wear-out, to revitalize all equipment at once (one-phase revitalization), or - whether it is possible to postpone the revitalization of a part of equipment for the next period (phased revitalization). Both concepts have some specific advantages and disadvantages. In essence the decision-making process between these two approaches, three basic conditions should be considered: technical-technological adequacy, energy-economy adequacy and financial adequacy. This paper covers general considerations, approach and methodology implemented during the revitalization the Tuzla Thermal Power Plant's Unit 3 (100MW) which was imposed by urgent demands of the Power System, the war conditions and financial possibilities including: - General data on TPP Tuzla and Unit 3 - Scope of work and economic effects

Subsequent flue gas desulfurization of coal-fired power plant units

International Nuclear Information System (INIS)

Willibal, U.; Braun, Gy.

1998-01-01

The presently operating coal-fired power plant in Hungary do not satisfy the pollution criteria prescribed by the European Union norms. The main polluting agent is the sulfur dioxide emitted by some of the power plants in Hungary in quantities over the limit standards. The power plant units that are in good operating state could be made competitive by using subsequent desulfurization measures. Various flue gas desulfurization technologies are presented through examples that can be applied to existing coal-fired power plants. (R.P.)

77 FR 29701 - Impact of Construction (Under a Combined License) of New Nuclear Power Plant Units on Operating...

Science.gov (United States)

2012-05-18

... New Nuclear Power Plant Units on Operating Units at Multi-Unit Sites AGENCY: Nuclear Regulatory... construct and operate new nuclear power plants (NPPs) on multi-unit sites to provide an evaluation of the... License) of New Nuclear Power Plants on Operating Units at Multi-Unit Sites (Package). ML112630039 Federal...

Non-native plant invasions of United States National parks

Science.gov (United States)

Allen, J.A.; Brown, C.S.; Stohlgren, T.J.

2009-01-01

The United States National Park Service was created to protect and make accessible to the public the nation's most precious natural resources and cultural features for present and future generations. However, this heritage is threatened by the invasion of non-native plants, animals, and pathogens. To evaluate the scope of invasions, the USNPS has inventoried non-native plant species in the 216 parks that have significant natural resources, documenting the identity of non-native species. We investigated relationships among non-native plant species richness, the number of threatened and endangered plant species, native species richness, latitude, elevation, park area and park corridors and vectors. Parks with many threatened and endangered plants and high native plant species richness also had high non-native plant species richness. Non-native plant species richness was correlated with number of visitors and kilometers of backcountry trails and rivers. In addition, this work reveals patterns that can be further explored empirically to understand the underlying mechanisms. ?? Springer Science+Business Media B.V. 2008.

Reactor building design of nuclear power plant ATUCHA II, Argentina

International Nuclear Information System (INIS)

Rufino, R.E.; Hermann, E.R.; Richter, E.

1984-01-01

It is presented the civil engineering project carried out by the joint venture Hochtief - Techint-Bignoli (HTB) for the reactor building at the Atucha II power plant (PHWR of 745 MWe) in Buenos Aires. All the other civil projects at Atucha II are also being carried out by HTB. This building has the same general characteristics of the PWR plants developed by KWU in Germany, known for the spherical steel containment 56m in diameter. Nevertheless, it differs from those principally in the equipment lay-out and the remarkable foundation depth. From the basic engineering provided by ENACE, the joint venture has had to face the challenge of designing a tridimensional structure of large size. This has necessitated using simplified models which had to be superimposed, since the use of only one spatial mode would be highly inadequate, lacking the flexibility necessary to absorb the numerous modifications that this type of project undergoes during construction. In addition, this procedure has eliminated resorting to numerous and costly computer processings. (Author) [pt

Development of regulatory requirements/guides for desalination unit coupled with nuclear plant

International Nuclear Information System (INIS)

Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik

2005-10-01

The basic design of System-integrated Modular Advanced Reactor (SMART), a small-to-medium sized integral type pressurized water reactor (PWR) with the capacity of 330MWth, has been developed in Korea. In order to demonstrate the safety and performance of the SMART design, 'Development Project of SMART-P (SMART-Pilot Plant)' has been being performed as one of the 'National Mid and Long-term Atomic Energy R and D Programs', which includes design, construction, and start-up operation of the SMART-P with the capacity of 65MWth, a 1/5 scaled-down design of the SMART. At the same time, a study on the development of regulatory requirements/guides for the desalination unit coupled with nuclear plant has been carried out by KINS in order to prepare for the forthcoming SMART-P licensing. The results of this study performed from August of 2002 to October of 2005 can be summarized as follows: (1) The general status of desalination technologies has been survey. (2) The design of the desalination plant coupled with the SMART-P has been investigated. (3) The regulatory requirements/guides relevant to a desalination unit coupled with a nuclear plant have been surveyed. (4) A direction on the development of domestic regulatory requirements/guides for a desalination unit has been established. (5) A draft of regulatory requirements/guides for a desalination unit has been developed. (6) Expert technical reviews have been performed for the draft regulatory requirements/guides for a desalination unit. The draft regulatory requirements/guides developed in this study will be finalized and can be applied directly to the licensing of the SMART-P and SMART. Furthermore, it will be also applied to the licensing of the desalination unit coupled with the nuclear plant

Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Abbott, L [ed.

1985-09-01

An evaluation of the risk to the Calvert Cliffs Unit 1 nuclear power plant due to pressurized thermal shock (PTS) has been completed by Oak Ridge National Laboratory (ORNL) with the assistance of several other organizations. This evaluation was part of a Nuclear Regulatory Commission program designed to study the PTS risk to three nuclear plants, the other two plants being Oconee Unit 1 and H.B. Robinson Unit 2. The specific objectives of the program were to (1) provide a best estimate of the frequency of a through-the-wall crack in the pressure vessel at each of the three plants, together with the uncertainty in the estimated frequency and its sensitivity to the variables used in the evaluation; (2) determine the dominant overcooling sequences contributing to the estimated frequency and the associated failures in the plant systems or in operator actions; and (3) evaluate the effectiveness of potential corrective measures.

Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant

International Nuclear Information System (INIS)

Abbott, L.

1985-09-01

An evaluation of the risk to the Calvert Cliffs Unit 1 nuclear power plant due to pressurized thermal shock (PTS) has been completed by Oak Ridge National Laboratory (ORNL) with the assistance of several other organizations. This evaluation was part of a Nuclear Regulatory Commission program designed to study the PTS risk to three nuclear plants, the other two plants being Oconee Unit 1 and H.B. Robinson Unit 2. The specific objectives of the program were to (1) provide a best estimate of the frequency of a through-the-wall crack in the pressure vessel at each of the three plants, together with the uncertainty in the estimated frequency and its sensitivity to the variables used in the evaluation; (2) determine the dominant overcooling sequences contributing to the estimated frequency and the associated failures in the plant systems or in operator actions; and (3) evaluate the effectiveness of potential corrective measures

Experience in connecting the power generating units of thermal power plants to automatic secondary frequency regulation within the united power system of Russia

International Nuclear Information System (INIS)

Zhukov, A. V.; Komarov, A. N.; Safronov, A. N.; Barsukov, I. V.

2009-01-01

The principles of central control of the power generating units of thermal power plants by automatic secondary frequency and active power overcurrent regulation systems, and the algorithms for interactions between automatic power control systems for the power production units in thermal power plants and centralized systems for automatic frequency and power regulation, are discussed. The order of switching the power generating units of thermal power plants over to control by a centralized system for automatic frequency and power regulation and by the Central Coordinating System for automatic frequency and power regulation is presented. The results of full-scale system tests of the control of power generating units of the Kirishskaya, Stavropol, and Perm GRES (State Regional Electric Power Plants) by the Central Coordinating System for automatic frequency and power regulation at the United Power System of Russia on September 23-25, 2008, are reported.

Designing a nuclear power plant with 1000 MW WWER-type units

Energy Technology Data Exchange (ETDEWEB)

Berkovich, V; Kaloshin, J; Tatarnikov, V; Shenderovich, A

1977-06-01

A brief description is presented of a WWER-1000 nuclear power plant also considering its environmental impact and the problem of core poisoning. The following indicators are graphically shown in relation to the reactor output: turbogenerator unit outputs, efficiency, specific capital costs and own costs of electric power generated by the Voronezh nuclear power plant. Also listed are the specific consumption of metal and concrete, specific equipment weight and the specific volume of the buildings of the main generating unit as well as the cross section thereof.

Integrated plant safety assessment: Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206): Final report

International Nuclear Information System (INIS)

1986-12-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of San Onofre Nuclear Generating Station, Unit 1, operated by Southern California Edison Company. The San Onofre plant is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. This report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the draft report issued in April 1985

50 CFR 17.8 - Import exemption for threatened, CITES Appendix-II wildlife.

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 2 2010-10-01 2010-10-01 false Import exemption for threatened, CITES Appendix-II wildlife. 17.8 Section 17.8 Wildlife and Fisheries UNITED STATES FISH AND WILDLIFE SERVICE..., EXPORTATION, AND IMPORTATION OF WILDLIFE AND PLANTS (CONTINUED) ENDANGERED AND THREATENED WILDLIFE AND PLANTS...

Simulator of nuclear power plant with WWER-440 units

International Nuclear Information System (INIS)

Krcek, V.

1985-01-01

The use is discussed of simulators in the training of qualified personnel for the construction and operation of nuclear power plants. Simulators are used for training all activities and thinking processes related to the control of a nuclear reactor in the course of quasi-steady and non-steady states. The development and implementation is summed up of the construction of such a simulator for WWER-440 nuclear power plants. The main parts of the simulator include the unit control room, the computer system, the teacher's workplace and the interface system. The possibility of simulating the functions of the unit for personnel training is based on the description of the behaviour of the simulated object in form of mathematical models of its basic technological subsystems and their interrelations within the range of operating patterns. (J.C.)

Designing a nuclear power plant with 1000 MW WWER-type units

International Nuclear Information System (INIS)

Berkovich, V.; Kaloshin, J.; Tatarnikov, V.; Shenderovich, A.

1977-01-01

A brief description is presented of a WWER-1000 nuclear power plant also considering its environmental impact and the problem of core poisoning. The following indicators are graphically shown in relation to the reactor output: turbogenerator unit outputs, efficiency, specific capital costs and own costs of electric power generated by the Voronezh nuclear power plant. Also listed are the specific consumption of metal and concrete, specific equipment weight and the specific volume of the buildings of the main generating unit as well as the cross section thereof. (J.B.)

Predictive value of SAPS II and APACHE II scoring systems for patient outcome in a medical intensive care unit

Directory of Open Access Journals (Sweden)

Amina Godinjak

2016-11-01

Full Text Available Objective. The aim is to determine SAPS II and APACHE II scores in medical intensive care unit (MICU patients, to compare them for prediction of patient outcome, and to compare with actual hospital mortality rates for different subgroups of patients. Methods. One hundred and seventy-four patients were included in this analysis over a oneyear period in the MICU, Clinical Center, University of Sarajevo. The following patient data were obtained: demographics, admission diagnosis, SAPS II, APACHE II scores and final outcome. Results. Out of 174 patients, 70 patients (40.2% died. Mean SAPS II and APACHE II scores in all patients were 48.4±17.0 and 21.6±10.3 respectively, and they were significantly different between survivors and non-survivors. SAPS II >50.5 and APACHE II >27.5 can predict the risk of mortality in these patients. There was no statistically significant difference in the clinical values of SAPS II vs APACHE II (p=0.501. A statistically significant positive correlation was established between the values of SAPS II and APACHE II (r=0.708; p=0.001. Patients with an admission diagnosis of sepsis/septic shock had the highest values of both SAPS II and APACHE II scores, and also the highest hospital mortality rate of 55.1%. Conclusion. Both APACHE II and SAPS II had an excellent ability to discriminate between survivors and non-survivors. There was no significant difference in the clinical values of SAPS II and APACHE II. A positive correlation was established between them. Sepsis/septic shock patients had the highest predicted and observed hospital mortality rate.

AMERICAN ELECTRIC POWER'S CONESVILLE POWER PLANT UNIT NO.5 CO2 CAPTURE RETROFIT STUDY

Energy Technology Data Exchange (ETDEWEB)

Carl R. Bozzuto; Nsakala ya Nsakala; Gregory N. Liljedahl; Mark Palkes; John L. Marion

2001-06-30

ALSTOM Power Inc.'s Power Plant Laboratories (ALSTOM) has teamed with American Electric Power (AEP), ABB Lummus Global Inc. (ABB), the US Department of Energy National Energy Technology Laboratory (DOE NETL), and the Ohio Coal Development Office (OCDO) to conduct a comprehensive study evaluating the technical feasibility and economics of alternate CO{sub 2} capture and sequestration technologies applied to an existing US coal-fired electric generation power plant. The motivation for this study was to provide input to potential US electric utility actions concerning GHG emissions reduction. If the US decides to reduce CO{sub 2} emissions, action would need to be taken to address existing power plants. Although fuel switching from coal to natural gas may be one scenario, it will not necessarily be a sufficient measure and some form of CO{sub 2} capture for use or disposal may also be required. The output of this CO{sub 2} capture study will enhance the public's understanding of control options and influence decisions and actions by government, regulators, and power plant owners in considering the costs of reducing greenhouse gas CO{sub 2} emissions. The total work breakdown structure is encompassed within three major reports, namely: (1) Literature Survey, (2) AEP's Conesville Unit No.5 Retrofit Study, and (3) Bench-Scale Testing and CFD Evaluation. The report on the literature survey results was issued earlier by Bozzuto, et al. (2000). Reports entitled ''AEP's Conesville Unit No.5 Retrofit Study'' and ''Bench-Scale Testing and CFD Evaluation'' are provided as companion volumes, denoted Volumes I and II, respectively, of the final report. The work performed, results obtained, and conclusions and recommendations derived therefrom are summarized.

Interaction of amatoxins with plant cells and RNA polymerases II: selection of amanitin-resistant cell lines and synthesis of amanitin-based affinity ligands

International Nuclear Information System (INIS)

Little, M.C.

1984-01-01

A series of experiments directed toward deriving basic information regarding plant RNA polymerase II is presented. The experiments described relate to the potential of isolating RNA polymerase II mutants in plants, using carrot cell cultures as models. Additionally, the synthesis of amanitin-based affinity ligands to immobilize isolated plant RNA polymerase II and associated transcriptional complexes is described. RNA polymerase II activities have been isolated from suspension cultures of carrot and compared to other plant RNA polymerases II with respect to subunit analysis and inhibition with α-amanitin. RNA polymerase II purified by polymin P absorption, DE52, phosphocellulose, and RNA-agarose chromatography is shown to copurify with proteins of 175 (and 200), 135, 70, 43, 28, 22, and 17 kdaltons apparent molecular weights. Conditions for accurate determination of amanitin inhibition of the enzyme are established using 3 H-amanitin and are presented for the first time for plant RNA polymerase II; RNA polymerase II from these cultures is shown to be inhibited by 50% at 3-5 nM by α-amanitin, a value 10-50 times lower than previously reported

Mathematical models of power plant units with once-through steam generators

International Nuclear Information System (INIS)

Hofmeister, W.; Kantner, A.

1977-01-01

An optimization of effective control functions with the current complex control loop structures and control algorithms is practically not possible. Therefore computer models are required which may be optimized with the process and plant data known before start-up of thermal power plants. The application of process computers allows additional predictions on the control-dynamic behavior of a thermal power plant unit. (TK) [de

Cross-connected onsite emergency A.C. power supplies for multi-unit nuclear power plant sites

International Nuclear Information System (INIS)

Martore, J.A.; Voss, J.D.; Duncil, B.

1987-01-01

Recently, utility management, both at the corporate and plant operations levels, have reinforced their commitment to assuring increased plant reliability and availability. One means of achieving this objective involves an effective preventive maintenance program with technical specifications which allow implementation of certain preventive maintenance without plant shutdown. To accomplish this, Southern California Edison Company (SCE) has proposed a design change for San Onofre nuclear generating station (SONGS) units 2 and 3 to permit on emergency diesel generator for one unit to perform as an available AC power source for both units. Technical specifications for SCE's SONGS units 2 and 3, as at most nuclear power plants, currently require plant shutdown should one of the two dedicated onsite emergency AC power sources (diesel generators) become inoperable for more than 72 hours. This duration hinders root cause failure analysis, tends to limit the flexibility of preventive maintenance and precludes plant operation in the event of component failure. Therefore, this proposed diesel generator cross-connect design change offers an innovative means for averting plant shutdown should a single diesel generator become inoperable for longer than 72 hours. (orig./GL)

Revision of documents guide to obtain the renovation of licence of the nuclear power plant of Laguna Verde, Units I and II

International Nuclear Information System (INIS)

Jarvio C, G.; Fernandez S, G.

2008-01-01

Unquestionably the renovation of license of the nuclear power plants , it this converting in a promising option to be able to gather in sure, reliable form and economic those requests about future energy in the countries with facilities of this type. This work it analyzes four documents guide and their application for the determination of the renovation of it licenses in nuclear plants that will serve of base for their aplication in the Nuclear Power Plant of Laguna Verde Units I and 2. The four documents in question are: the one Inform Generic of Learned Lessons on the Aging (NUREG - 1801), the Standard Revision Plan for the Renovation of License (NUREG - 1800), the Regulatory Guide for Renovation of License (GR-1.188), and the NEI 95-10, developed by the Institute of Nuclear Energy that is an Industrial Guide to Implement the Requirements of the 1OCFR Part 54-the Rule of Renovation of It licenses. (Author)

Operation of Finnish nuclear power plants. Quarterly report, 2nd quarter, 1995

Energy Technology Data Exchange (ETDEWEB)

Tossavainen, K. [ed.

1995-10-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Fasety improvements at the plants are also described. The report includes a summary of the radiation safety of plant personnel and of the evironment and tabulated data on the plants` production and load factors. Except for the annual maintenance outages of the TVO plant units and for TVO II`s Midsummer outage which was due to low electricity demand, the Finnish nuclear power plants were in power operation during the second quarter of 1995. The load factor average of all four plant units was 91.2 %. Events during the second annual quarter were level 0 on the INES scale. Occupational doses and radioactive releases off-site were below authorized limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (4 figs., 4 tabs.).

Mega akku in the Alps. Pumped-storage power plant Limberg II in Kaprun; Mega-Akku in den Alpen. Pumpspeicherwerk Limberg II in Kaprun

Energy Technology Data Exchange (ETDEWEB)

Steyrer, Peter [POEYRY Energy GmbH, Salzburg (Austria). Konstruktiver Wasserbau

2011-05-15

Since the 1920ies, the Kaprun valley and the area around the Grossglockner are a subject for project planning of hydropower plants. The power plant group Glockner-Kaprun with upper and main stage was completed in 1955. Since 1970, various options for expansion were examined by a pumped storage plant. The result of these investigations is the project Limberg II, which is realized since 2007 and completed this year.

New nuclear power plant unit in Finland accepted by the Finnish Parliament

International Nuclear Information System (INIS)

Kaetkae, M.

2002-01-01

The nuclear option has been included in Finland's energy strategy since late 1990's. Based on TVO's application the Finnish Parliament accepted in May 2002 the decision in principle to build a new nuclear power plant unit. The main arguments were the growth of electricity demand, reduction of CO 2 emissions, security of energy supply and reasonable as well as predictable electricity price. TVO's intention is to get the new power plant unit into commercial operation at the end of this decade.(author)

He II Heat Exchanger Test Unit for the LHC Inner Triplet

CERN Document Server

Blanco-Viñuela, E; Huang, Y; Nicol, T H; Peterson, T; Van Weelderen, R

2002-01-01

The Inner Triplet Heat Exchanger Test Unit (IT-HXTU) is a 30-m long thermal model designed at Fermilab, built in US industry, fully automated and tested at CERN as part of the US LHC program to develop the LHC Interaction Region quadrupole system. The cooling scheme of the IT-HXTU is based on heat exchange between stagnant pressurized He II in the magnet cold mass and saturated He II (two-phase) flowing in a heat exchanger located outside of and parallel to the cold mass. The purposes of this test are, among others, to validate the proposed cooling scheme and to define an optimal control strategy to be implemented in the future LHC accelerator. This paper discusses the results for the heat exchanger test runs and emphasizes the thermal and hydraulic behavior of He II for the inner triplet cooling scheme.

Nuclear emergency buildings of Asco and Vandellos II nuclear power plants; Centros alternativos de emergencias de las centrales nucleares de Asco y Vandellos II

Energy Technology Data Exchange (ETDEWEB)

Massuet, J.; Sabater, J.; Mirallas Esteban, S.

2016-08-01

The Nuclear Emergency Buildings sited at Asco and Vandellos II Nuclear Power Plants (NPP) are designed to safety manage emergencies in extreme situations, beyond the design basis of the Nuclear Power Plants. Designed in accordance with the requirements of the Spanish Nuclear Regulator (Consejo de Seguridad Nuclear-CSN) these buildings are ready to operate over a period of 72 hours without external assistance and ensure habitability for crews of 120 and 70 people respectively. This article describes the architectural conception, features and major systems of the Nuclear Emergency Buildings sited at Asco and Vandellos II. (Author)

75 FR 80547 - Carolina Power & Light Company, Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption

Science.gov (United States)

2010-12-22

..., Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption 1.0 Background Carolina Power & Light Company... operation of the Shearon Harris Nuclear Power Plant (HNP), Unit 1. The license provides, among other things... request to generically extend the rule's compliance date for all operating nuclear power plants, but noted...

Survey of fish impingement at power plants in the United States. Volume II. Inland waters

International Nuclear Information System (INIS)

Freeman, R.F. III; Sharma, R.K.

1977-03-01

Impingement of fish at cooling-water intakes of 33 power plants located on inland waters other than the Great Lakes has been surveyed and data are presented. Descriptions of site, plant, and intake design and operation are provided. Reports in this volume summarize impingement data for individual plants in tabular and histogram formats. Information was available from differing sources such as the utilities themselves, public documents, regulatory agencies, and others. Thus, the extent of detail in the reports varies greatly from plant to plant. Histogram preparation involved an extrapolation procedure that has inadequacies. The reader is cautioned in the use of information presented in this volume to determine intake-design acceptability or intensity of impacts on ecosystems. No conclusions are presented herein; data comparisons are made in Volume IV

Completion of high-efficiency BWR turbine plant 'Hamaoka unit No. 4'

International Nuclear Information System (INIS)

Tsuji, Kunio; Hamaura, Norikazu; Shibashita, Naoaki; Kazama, Seiichi

1995-01-01

Accompanying the increase of capacity of nuclear power plants in Japan, the plants having heightened economical efficiency, which are supported by the improvement of thermal efficiency and the reduction of dose, are demanded. Hitachi Ltd. has completed No. 4 turbine unit of 1137 MW output in Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., which is the largest capacity machine in Japanese BWR plants. In this unit, the moisture separator heater, the steam turbine with high efficiency, and the hollow thread film condensate filter which treats the total flow rate of condensate are used as the reheating type BWR plant for the first time in Japan, and the plan of heightened economy and operation was adopted. It was confirmed by the trial for about 10 months that the planned performance was sufficiently satisfied, and the commercial operation was started in September, 1993. The features of the 1137 MW turbine unit are explained. The turbine is of tandem six-flow exhaust condensation type. Diffuser type low pressure turbine exhaust chambers, butterfly type combination intermediate valve are adopted. The stages with the blades having moisture-separating grooves were corrected. The reliability of the shaft system was improved. The adoption of the moisture separator heater and the application of the hollow thread film type condensate filter are explained. (K.I.)

Seismic design criteria and their application to major hazard plant within the United Kingdom

International Nuclear Information System (INIS)

Alderson, M.A.H.G.

1982-12-01

The nature of seismic motions and the implications are briefly described and the development of seismic design criteria for nuclear power plants in various countries is described including possible future developments. The seismicity of the United Kingdom is briefly reviewed leading to the present position on seismic design criteria for nuclear power plants within the United Kingdom. Damage from past destructive earthquakes is reviewed and the existing codes of practice and standards are described. Finally the effect of earthquakes on major hazard plant is discussed in general terms including the seismic analysis of a typical plant item. (author)

Multifrequency tests in the EBR-II reactor plant

International Nuclear Information System (INIS)

Feldman, E.E.; Mohr, D.; Gross, K.C.

1989-01-01

A series of eight multifrequency tests was conducted on the Experimental Breeder Reactor II. In half of the tests a control rod was oscillated and in the other half the controller input voltage to the intermediate-loop-sodium pump was perturbed. In each test the input disturbance consisted of several superimposed single-frequency sinusoidal harmonics of the same fundamental. The tests are described along with the theoretical and practical aspects of their development and design. Samples of measured frequency responses are also provided for both the reactor and the power plant. 22 refs., 5 figs., 2 tabs

Plants lacking the main light-harvesting complex retain photosystem II macro-organization

NARCIS (Netherlands)

Ruban, A.V.; Wentworth, M.; Yakushevska, A.E.; Andersson, J.; Lee, P.J.; Keegstra, W.; Dekker, J.P.; Boekema, E.J.; Jansson, S.; Horton, P.

2003-01-01

Photosystem II (PSII) is a key component of photosynthesis, the process of converting sunlight into the chemical energy of life. In plant cells, it forms a unique oligomeric macrostructure in membranes of the chloroplasts. Several light-harvesting antenna complexes are organized precisely in the

Plants lacking the main light-harvesting complex retain photosystem II macro-organization

NARCIS (Netherlands)

Ruban, AV; Wentworth, M; Yakushevska, AE; Andersson, J; Lee, PJ; Keegstra, W; Dekker, JP; Boekema, EJ; Jansson, S; Horton, P

2003-01-01

Photosystem II (PSII) is a key component of photosynthesis, the process of converting sunlight into the chemical energy of life. In plant cells, it forms a unique oligomeric macrostructure in membranes of the chloroplasts(1). Several light-harvesting antenna complexes are organized precisely in the

1170-MW(t) HTGR-PS/C plant application study report: SRC-II process application

International Nuclear Information System (INIS)

Rao, R.; McMain, A.T. Jr.

1981-05-01

The solvent refined coal (SRC-II) process is an advanced process being developed by Gulf Mineral Resources Ltd. (a Gulf Oil Corporation subsidiary) to produce a clean, non-polluting liquid fuel from high-sulfur bituminous coals. The SRC-II commercial plant will process about 24,300 tonnes (26,800 tons) of feed coal per stream day, producing primarily fuel oil plus secondary fuel gases. This summary report describes the integration of a high-temperature gas-cooled reactor operating in a process steam/cogeneration mode (HTGR-PS/C) to provide the energy requirements for the SRC-II process. The HTGR-PS/C plant was developed by General Atomic Company (GA) specifically for industries which require energy in the form of both steam and electricity. General Atomic has developed an 1170-MW(t) HTGR-PS/C design which is particularly well suited to industrial applications and is expected to have excellent cost benefits over other sources of energy

MHD repowering of a 250 MWe unit of the TVA Allen Steam Plant

International Nuclear Information System (INIS)

Chapman, J.N.; Attig, R.C.

1992-01-01

In this paper coal fired MHD repowering is considered for the TVA Allen Steam Plant. The performance of the repowered plant is presented. Cost comparisons are made of the cost of repowering with MHD versus the cost of meeting similar standards by installing scrubbers and selective catalytic NO x reduction (SCNR). For repowering of a single 250 MW e unit, the costs favor scrubbing and SCNR. If one considers a single repowering of all three 250 MW e units by a single MHD topping cycle and boiler, MHD repowering is more economical. Environmental emissions from the repowered plant are estimated

Nuclear power plant simulators for operator licensing and training. Part I. The need for plant-reference simulators. Part II. The use of plant-reference simulators

International Nuclear Information System (INIS)

Rankin, W.L.; Bolton, P.A.; Shikiar, R.; Saari, L.M.

1984-05-01

Part I of this report presents technical justification for the use of plant-reference simulators in the licensing and training of nuclear power plant operators and examines alternatives to the use of plant-reference simulators. The technical rationale is based on research on the use of simulators in other industries, psychological learning and testing principles, expert opinion and user opinion. Part II discusses the central considerations in using plant-reference simulators for licensing examination of nuclear power plant operators and for incorporating simulators into nuclear power plant training programs. Recommendations are presented for the administration of simulator examinations in operator licensing that reflect the goal of maximizing both reliability and validity in the examination process. A series of organizational tasks that promote the acceptance, use, and effectiveness of simulator training as part of the onsite training program is delineated

Optimization of Boiler Control to Improve the Load-following Capability of Power-plant Units

DEFF Research Database (Denmark)

Mortensen, J. H.; Mølbak, T.; Andersen, Palle

The capability to perform fast load changes has been an important issue in the power market, and will become increasingly more so due to the incresing commercialisation of the European power market. An optimizing control system for improving the load-following capability of power-plant units has...... tests on a 265 MW coal-fired power-plant unit reveals that the maximum allowable load gradient that can be imposed on the plant, can be increased from 4 MW/min. to 8 MW/min....

Optimization of Boiler Control to Improve the Load-following Capability of Power-plant Units

DEFF Research Database (Denmark)

Mortensen, J. H.; Mølbak, T.; Andersen, Palle

1998-01-01

The capability to perform fast load changes has been an important issue in the power market, and will become increasingly more so due to the incresing commercialisation of the European power market. An optimizing control system for improving the load-following capability of power-plant units has...... tests on a 265 MW coal-fired power-plant unit reveals that the maximum allowable load gradient that can be imposed on the plant, can be increased from 4 MW/min. to 8 MW/min....

Uptake of Cd(II) and Pb(II) by microalgae in presence of colloidal organic matter from wastewater treatment plant effluents

International Nuclear Information System (INIS)

Worms, Isabelle A.M.; Traber, Jacqueline; Kistler, David; Sigg, Laura; Slaveykova, Vera I.

2010-01-01

The present study addresses the key issue of linking the chemical speciation to the uptake of priority pollutants Cd(II) and Pb(II) in the wastewater treatment plant effluents, with emphasis on the role of the colloidal organic matter (EfOM). Binding of Cd(II) and Pb(II) by EfOM was examined by an ion exchange technique and flow field-flow fractionation coupled to inductively coupled plasma mass spectrometry in parallel to bioassays with green microalga Chlorella kesslerii in ultrafiltrate (<1 kDa) and colloidal isolates (1 kDa to 0.45 μm). The uptake of Cd by C. kesslerii was consistent with the speciation analysis and measured free metal ion concentrations, while Pb uptake was much greater than that expected from the speciation measurement. Better understanding of the differences in the effects of the EfOM on Cd(II) and Pb(II) uptake required to take into account the size dependence of metal binding by EfOM. - Colloids isolated from WWTP effluents decrease Cd uptake, but increase Pb uptake by microalga Chlorella kesslerii.

Uptake of Cd(II) and Pb(II) by microalgae in presence of colloidal organic matter from wastewater treatment plant effluents

Energy Technology Data Exchange (ETDEWEB)

Worms, Isabelle A.M. [Environmental Biophysical Chemistry, IIE-ENAC, Ecole Polytechnique Federale de Lausanne (EPFL), Station 2, CH-1015 Lausanne (Switzerland); Traber, Jacqueline; Kistler, David; Sigg, Laura [Eawag, Swiss Federal Institute of Aquatic Science and Technology, P.O. Box 611, CH-8600 Duebendorf (Switzerland); Slaveykova, Vera I., E-mail: vera.slaveykova@epfl.c [Environmental Biophysical Chemistry, IIE-ENAC, Ecole Polytechnique Federale de Lausanne (EPFL), Station 2, CH-1015 Lausanne (Switzerland)

2010-02-15

The present study addresses the key issue of linking the chemical speciation to the uptake of priority pollutants Cd(II) and Pb(II) in the wastewater treatment plant effluents, with emphasis on the role of the colloidal organic matter (EfOM). Binding of Cd(II) and Pb(II) by EfOM was examined by an ion exchange technique and flow field-flow fractionation coupled to inductively coupled plasma mass spectrometry in parallel to bioassays with green microalga Chlorella kesslerii in ultrafiltrate (<1 kDa) and colloidal isolates (1 kDa to 0.45 mum). The uptake of Cd by C. kesslerii was consistent with the speciation analysis and measured free metal ion concentrations, while Pb uptake was much greater than that expected from the speciation measurement. Better understanding of the differences in the effects of the EfOM on Cd(II) and Pb(II) uptake required to take into account the size dependence of metal binding by EfOM. - Colloids isolated from WWTP effluents decrease Cd uptake, but increase Pb uptake by microalga Chlorella kesslerii.

Phase I and II feasibility study report for the 300-FF-5 operable unit

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-12-31

The purpose of this Phase I/II feasibility study is to assemble and screen a list of alternatives for remediation of the 300-FF-5 operable site on the Hanford Reservation. This screening is based on information gathered in the Phase I Remedial Investigation (RI) and on currently available information on remediation technologies. The alternatives remaining after screening provide a range of response actions for remediation. In addition, key data needs are identified for collection during a Phase II RI (if necessary). This Phase I/II FS represents a primary document as defined by the Tri-Party Agreement, but will be followed by a Phase III FS that will further develop the alternatives and provide a detailed evaluation of them. The following remedial action objectives were identified for the 300-FF-5 operable unit: Limit current human exposure to contaminated groundwater in the unit; Limit discharge of contaminated groundwater to the Columbia River; Reduce contaminant concentrations in groundwater below acceptable levels by the year 2018.

Phase I and II feasibility study report for the 300-FF-5 operable unit

International Nuclear Information System (INIS)

1993-01-01

The purpose of this Phase I/II feasibility study is to assemble and screen a list of alternatives for remediation of the 300-FF-5 operable site on the Hanford Reservation. This screening is based on information gathered in the Phase I Remedial Investigation (RI) and on currently available information on remediation technologies. The alternatives remaining after screening provide a range of response actions for remediation. In addition, key data needs are identified for collection during a Phase II RI (if necessary). This Phase I/II FS represents a primary document as defined by the Tri-Party Agreement, but will be followed by a Phase III FS that will further develop the alternatives and provide a detailed evaluation of them. The following remedial action objectives were identified for the 300-FF-5 operable unit: Limit current human exposure to contaminated groundwater in the unit; Limit discharge of contaminated groundwater to the Columbia River; Reduce contaminant concentrations in groundwater below acceptable levels by the year 2018

The modernization of the nuclear power plants of Asco and Vandellos II

International Nuclear Information System (INIS)

Martinez Anton, L.

2011-01-01

Since the beginning of their commercial operation, the nuclear power plants of Asco and Vandellos have made design modifications aimed at improving the safety, reliability and operation of the plants. From the moment the management of the three plants was brought together within the Association Nuclear Asco-Vandellos II, and within the assets management process, joint strategic modernisation and improvement plans have been developed on the basis of the status of equipment, the evaluation of their ageing, obsolesce, degradations, manufacturers recommendations and/or the application of new regulations. The article lists the mos important actions already carried out or in the project phase for the 3 plants in the primary and secondary system, electrical and instrumentation systems and auxiliary systems, highlighting the problems and the solutions adopted in the most relevant modifications. (Author)

Plant species invasions along the latitudinal gradient in the United States

Science.gov (United States)

Thomas J. Stohlgren; David Barnett; Curtis Flather; John Kartesz; Bruce Peterjohn

2005-01-01

It has been long established that the richness of vascular plant species and many animal taxa decreases with increasing latitude, a pattern that very generally follows declines in actual and potential evapotranspiration, solar radiation, temperature, and thus, total productivity. Using county-level data on vascular plants from the United States (3000 counties in the...

Exergetic performance analysis of a Dora II geothermal power plant in Turkey

Energy Technology Data Exchange (ETDEWEB)

Ganjehsarabi, Hadi; Gungor, Ali [Department of Mechanical Engineering, Faculty of Engineering, Ege University (Turkey); Dincer, Ibrahim [Faculty of Engineering and Applied Science, University of Ontario (Canada)

2011-07-01

In the energy sector there is an urgent need to produce energy from renewable energy sources due to the rising demand, the depletion of fossil fuels and their effects on the environment. Geothermal power is a well-established energy resource and the aim of this research was to examine the energetic performance of a geothermal power plant. The studied power plant, Dora II, has a 9.5 MW power output and is situated in Aydin, Turkey. An evaluation of the plant's performance was carried out using an exergy analysis method on each of the plant's components. Results showed that the highest exergy destruction occurs in brine re-injection while the preheater had the best exergy efficiency; the plant had an overall exergetic efficiency of 29.6%. This study highlighted the components where significant exergy destructions take place so actions could be taken to improve the overall efficiency.

Plutonium Finishing Plant Treatment and Storage Unit Dangerous Waste Training Plan

International Nuclear Information System (INIS)

ENTROP, G.E.

2000-01-01

The training program for personnel performing waste management duties pertaining to the Plutonium Finishing Plant (PFP) Treatment and Storage Unit is governed by the general requirements established in the Plutonium Finishing Plant Dangerous Waste Training Plan (PFP DWTP). The PFP Treatment and Storage Unit DWTP presented below incorporates all of the components of the PFP DWTP by reference. The discussion presented in this document identifies aspects of the training program specific to the PFP Treatment and Storage Unit. The training program includes specifications for personnel instruction through both classroom and on-the-job training. Training is developed specific to waste management duties. Hanford Facility personnel directly involved with the PFP Treatment and Storage Unit will receive training to container management practices, spill response, and emergency response. These will include, for example, training in the cementation process and training pertaining to applicable elements of WAC 173-303-330(1)(d). Applicable elements from WAC 173-303-330(1)(d) for the PFP Treatment and Storage Unit include: procedures for inspecting, repairing, and replacing facility emergency and monitoring equipment; communications and alarm systems; response to fires or explosions; and shutdown of operations

Operation of Finnish nuclear power plants. Quarterly report, 2nd quarter 1996

International Nuclear Information System (INIS)

Sillanpaeae, T.

1996-11-01

Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The report also includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. In the second quarter of 1996, the Finnish nuclear power plant units were in power operation except for the annual maintenance outages of TVO plant units and the Midsummer shutdown at TVO II which was due to low electricity demand, a turbine generator inspection and repairs. The load factor average of all plant units was 88.9 %. Events in the second quarter of 1996 were classified level 0 on the International Nuclear Event Scale (INES)

Summary revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce

International Nuclear Information System (INIS)

Sarvaic, I.; Miskolci, M.

1998-01-01

The document contents stage revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce. Test results of the stage of energetic start-up are summarized in the document, valuation of important systems and block devices as well as fulfilling the operation limits and conditions has been performed. On that base conclusions and recommendations for start-up the unit 2 and for commercial operation of the unit 1 are elaborated. The valuation has been elaborated by a scientific management for start-up nuclear power plant Mochovce of nuclear safety of nuclear power facilities. Scientific management for start-up of nuclear power plant Mochovce performed continuous valuation of individual power levels after ending of each individual level and it gave its valuation to energy power level with recommendations and conditions for further start-up process and operation. Scientific management finished its activity at the unit 1 of nuclear power plant Mochovce according to a statute of scientific management for start-up after successful completion of conclusive block run. Scientific management group was founded in February 1998 at nuclear power plant Mochovce. Its members are experts from Slovak, Czech, Russian and French organizations which are participating in power plant completion. Members are listed in a supplement No. 2

Removal of Copper(II) Ions in Aqueous Solutions Using Tannin-Rich Plants as Natural Bio-Adsorbents

Science.gov (United States)

Paksamut, J.; Boonsong, P.

2018-03-01

In this study, the purpose of our interest is to investigatethe adsorption behavior of copper (II) ions in aqueous solution using some tannin-rich plants as natural bio-adsorbents such as mangosteen peels (Garciniamangostana L.), cassava leaves (Manihotesculenta Crantz) and Thai copper pod leaves (Sennasiamea (Lam.)) as powder form in different dosage of adsorbent plant materials.The adsorption capacities at different pH of solution and contact time were performed.All the experiments in this studywere chosen at room temperature by batch technique. From the experimental results showed that cassava leaves gave better adsorbent properties than mangosteen peels and Thai copper pod leaves. The increasing dosage of all adsorbents and contact time have been found to increase adsorption capacities. In this respect, the adsorption capacities depend crucially on the adsorbents and contact time. The optimum pH of copper (II) ions adsorption was pH4. According to this work, it was observed that bioadsorbent materials from tannin-rich plants could be used to remove copper (II) ions from aqueous solutions.

Communication and surrounding of Asco and Vandellos II nuclear power plants

International Nuclear Information System (INIS)

2004-01-01

The Asco and Vandellos-II power plants have always been integrated into the regions where they are located, and they take an active part in the development of surrounding towns through quality employment provided by our facilities, social and cultural support and aid to development promoted by regional councils. Communication to media is a corporate priority defined in our strategic plant, to ensure openness, rigour and punctuality. We also attend to the visitors who want to learn more about our facilities in the visitor center, and we have agreements with agrarian institutions in the area so that students can de practical training in the farms we own for agricultural production. (Author)

Modification of EBR-II plant to conduct loss-of-flow-without-scram tests

Energy Technology Data Exchange (ETDEWEB)

Messick, N C; Betten, P R; Booty, W F; Christensen, L J; Fryer, R M; Mohr, D; Planchon, H P; Radtke, W H

1987-04-01

This paper describes the details of and the philosophy behind changes made to the EBR-II plant in order to conduct loss-of-flow-without-scram tests. No changes were required to conduct loss-of-heat-sink-without-scram tests.

Modification of EBR-II plant to conduct loss-of-flow-without-scram tests

International Nuclear Information System (INIS)

Messick, N.C.; Betten, P.R.; Booty, W.F.; Christensen, L.J.; Fryer, R.M.; Mohr, D.; Planchon, H.P.; Radtke, W.H.

1987-01-01

This paper describes the details of and the philosophy behind changes made to the EBR-II plant in order to conduct loss-of-flow-without-scram tests. No changes were required to conduct loss-of-heat-sink-without-scram tests. (orig.)

Inventory of power plants in the United States, 1993

International Nuclear Information System (INIS)

1994-12-01

The Inventory of Power Plants in the United States is prepared annually by the Survey Management Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), U.S. Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). The publication also provides a 10-year outlook of future generating unit additions. Data summarized in this report are useful to a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended

Inventory of power plants in the United States, 1993

Energy Technology Data Exchange (ETDEWEB)

1994-12-01

The Inventory of Power Plants in the United States is prepared annually by the Survey Management Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), U.S. Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). The publication also provides a 10-year outlook of future generating unit additions. Data summarized in this report are useful to a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended.

Functional architecture of higher plant photosystem II supercomplexes.

Science.gov (United States)

Caffarri, Stefano; Kouril, Roman; Kereïche, Sami; Boekema, Egbert J; Croce, Roberta

2009-10-07

Photosystem II (PSII) is a large multiprotein complex, which catalyses water splitting and plastoquinone reduction necessary to transform sunlight into chemical energy. Detailed functional and structural studies of the complex from higher plants have been hampered by the impossibility to purify it to homogeneity. In this work, homogeneous preparations ranging from a newly identified particle composed by a monomeric core and antenna proteins to the largest C(2)S(2)M(2) supercomplex were isolated. Characterization by biochemical methods and single particle electron microscopy allowed to relate for the first time the supramolecular organization to the protein content. A projection map of C(2)S(2)M(2) at 12 A resolution was obtained, which allowed determining the location and the orientation of the antenna proteins. Comparison of the supercomplexes obtained from WT and Lhcb-deficient plants reveals the importance of the individual subunits for the supramolecular organization. The functional implications of these findings are discussed and allow redefining previous suggestions on PSII energy transfer, assembly, photoinhibition, state transition and non-photochemical quenching.

Compact sodium cooled nuclear power plant with fast core (KNK II- Karlsruhe), Safety Report

International Nuclear Information System (INIS)

1977-09-01

After the operation of the KNK plant with a thermal core (KNK I), the installation of a fast core (KNK II) had been realized. The planning of the core and the necessary reconstruction work was done by INTERATOM. Owner and customer was the Nuclear Research Center Karlsruhe (KfK), while the operating company was the Kernkraftwerk-Betriebsgesellschaft mbH (KBG) Karlsruhe. The main goals of the KNK II project and its special experimental test program were to gather experience for the construction, the licensing and operation of future larger plants, to develop and to test fuel and absorber assemblies and to further develop the sodium technology and the associated components. The present safety report consists of three parts. Part 1 contains the description of the nuclear plant. Hereby, the reactor and its components, the handling facilities, the instrumentation with the plant protection, the design of the plant including the reactor core and the nominal operation processes are described. Part 2 contains the safety related investigation and measures. This concerns the reactivity accidents, local cooling perturbations, radiological consequences with the surveillance measures and the justification of the choice of structural materials. Part three finally is the appendix with the figures, showing the different buildings, the reactor and its components, the heat transfer systems and the different auxiliary facilities [de

Transport of Zn (II by TDDA-Polypropylene Supported Liquid Membranes and Recovery from Waste Discharge Liquor of Galvanizing Plant of Zn (II

Directory of Open Access Journals (Sweden)

Hanif Ur Rehman

2017-01-01

Full Text Available The facilitated passage of Zn (II across flat sheet supported liquid membrane saturated with TDDA (tri-n-dodecylamine in xylene membrane phase has been investigated. The effect of acid and metal ion concentration in the feed solution, the carrier concentration in membrane phase, stripping agent concentration in stripping phase, and coions on the extraction of Zn (II was investigated. The stoichiometry of the extracted species, that is, complex, was investigated on slope analysis method and it was found that the complex (LH2·Zn(Cl2 is responsible for transport of Zn (II. A mathematical model was developed for transport of Zn (II, and the predicted results strongly agree with experimental ones. The mechanism of transport was determined by coupled coion transport mechanism with H+ and Cl− coupled ions. The optimized SLM was effectively used for elimination of Zn (II from waste discharge liquor of galvanizing plant of Zn (II.

LAND JUDGING AND PLANT NUTRITION, A PROGRAMMED INSTRUCTION UNIT, REPORT NUMBER 13.

Science.gov (United States)

LONG, GILBERT A.

A UNIT OF PROGRAMED LEARNING MATERIALS WAS PRESENTED ON THE PRINCIPLES AND PROCEDURES OF LAND JUDGING AND PLANT NUTRITION. IN HIS PREPARATION, THE AUTHOR FIRST IDENTIFIED PRINCIPLES AND FACTS NECESSARY FOR EFFECTIVE LAND CLASSIFICATION AND PLANT NUTRITION BY EXAMINING RELEVANT SCIENTIFIC REPORTS. USING THIS INFORMATION, HE THEN FORMED A TEAM OF 16…

Investigations of the unit generation costs of the nuclear power plants

International Nuclear Information System (INIS)

Guntay, S.

1977-01-01

An extensive study has been carried out to investigate the unit generation costs of different reactor types. The study analyzes the following: i) development of capital costs, ii) Fuel cycle costs, iii) operation and maintenance costs, iv) local and foreign finance requirements for an arbitrary reactor type

Operation of Finnish nuclear power plants. Quarterly report 3rd, quarter 1995

International Nuclear Information System (INIS)

Sillanpaeae, T.

1996-05-01

Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The Report includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. Except for the annual maintenance outages of Loviisa plant units and for TVO II's brief outage to repair a failed component, Finnish nuclear power plant units were in power operation in the third quarter of 1995. The load factor average of all plant units was 90.4 %. Events in this quarter were level 0 on the INES scale. Occupational doses and radioactive releases off-site were below authorised limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.) (4 figs., 4 tabs.)

Fe uptake from meso and D,L-racemic Fe(o,o-EDDHA) isomers by strategy I and II plants.

Science.gov (United States)

Cerdán, Mar; Alcañiz, Sara; Juárez, Margarita; Jordá, Juana D; Bermúdez, Dolores

2006-02-22

One of the most efficient fertilizers to correct Fe deficiency in calcareous soils and waters with high bicarbonate content is based on ferric ethylenediamine-N,N'-bis(o-hydroxyphenylacetic) acid [Fe(o,o-EDDHA)]. Fe(o,o-EDDHA) forms two groups of geometric isomers known as meso and D,L-racemic. To determine the Fe uptake from meso and D,L-racemic Fe(o,o-EDDHA), four iron-efficient plants, two plants representative of strategy I (tomato and pepper) and two plants representative of strategy II (wheat and oats), were grown in hydroponic culture. Results indicated that strategy II plants took up iron from both Fe(o,o-EDDHA) isomers equally. However, strategy I plants took mainly the iron associated with the meso form (the lowest stability isomer).

78 FR 16705 - Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/Fish Screen Facility Protection...

Science.gov (United States)

2013-03-18

...-FF08RSRC00] Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/ Fish Screen Facility Protection... removal and management of invasive plant species would occur at the Riparian Sanctuary. No active... impact statement and environmental impact report (EIS/EIR) for the Llano Seco Riparian Sanctuary Unit...

77 FR 26569 - Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/Fish Screen Facility Protection...

Science.gov (United States)

2012-05-04

...-FF08RSRC00] Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/ Fish Screen Facility Protection... would occur at the Riparian Sanctuary. No active restoration of native plants would occur. Maintenance... statement and environmental impact report (EIS/EIR) for the Llano Seco Riparian Sanctuary Unit Restoration...

Potato type I and II proteinase inhibitors: modulating plant physiology and host resistance.

Science.gov (United States)

Turra, David; Lorito, Matteo

2011-08-01

Serine protease inhibitors (PIs) are a large and complex group of plant proteins. Members of the potato type I (Pin1) and II (Pin2) proteinase inhibitor families are among the first and most extensively characterized plant PIs. Many insects and phytopathogenic microorganisms use intracellular and extracellular serine proteases playing important roles in pathogenesis. Plants, however, are able to fight these pathogens through the activation of an intricate defence system that leads to the accumulation of various PIs, including Pin1 and Pin2. Several transgenic plants over-expressing members of the Pin1 and Pin2 families have been obtained in the last twenty years and their enhanced defensive capabilities demonstrated against insects, fungi and bacteria. Furthermore, Pin1 and Pin2 genetically engineered plants showed altered regulation of different plant physiological processes (e.g., dehydratation response, programmed cell death, plant growth, trichome density and branching), supporting an endogenous role in various plant species in addition to the well established defensive one. This review summarizes the current knowledge about Pin1 and Pin2 structure, the role of these proteins in plant defence and physiology, and their potential exploitation in biotechnology.

MOBIL CONTAINER UNIT FOR SEWAGE SLUDGE UTILIZATION FROM SMALL AND MEDIUM WASTWATER TREATMENT PLANTS

Directory of Open Access Journals (Sweden)

Stanisław Ledakowicz

2016-06-01

Full Text Available The most wastewater treatment plants in Poland are small and medium plants of flow capacity below 1000 m3/d. These plants are not able to build sludge incineration plants and the transportation costs to the nearest plants increase the total costs of wastewater treatment. Polish company Metal Expert together with the French company ETIA and Lodz University of Technology proposed mobile unit for integrated drying and pyrolysis of sewage sludge in a pilot bench scale with capacity of 100 kg/h of dewatered sludge. The pilot plant was mounted in a typical mobile container which could provide service to small and medium wastewater treatment plants offering thermal processing of sewage sludge. This unit consists of KENKI contact dryer and „Spirajoule”® pyrolyser supplied with electricity utilizing the Joule effect, and a boiler, wherein the pyrolysis gases and volatile products are burned producing steam sent to the contact dryer. The bio-char produced during sludge pyrolysis could be utilized for agriculture purposes. During preliminary experiments and short-term exploitation of the unit at Elbląg Wastewater Treatment Plant the obtained results allowed us to make a mass and energy balance depended on the process conditions in the pyrolysis temperature range of 400÷800 °C. Based on the obtained results a calculator was created in the Excel , which enables assessment of pyrolysis products content and making mass and energy balances depended on process parameters such as initial moisture of sludge, pyrolysis temperature and installation output.

The United States nuclear plant reliability data program: Its description and status

International Nuclear Information System (INIS)

Wise, M.J.

1975-01-01

The American National Standards Institute Subcommittee N18-20 has developed and implemented the United States Nuclear Plant Reliability Data System (NPRDS). The NPRDS is designed to accumulate, store, analyse, and report reliability and failure statistics on systems and components of nuclear power plants related to nuclear safety. Input data to the NPRDS consist of engineering, operating, and failure information submitted on a voluntary basis by participating utilities. Prior to entry into the computerized data base, the data are thoroughly checked for accuracy by both the submitting organizations and the NPRDS operating contractor. The data base is the source of various periodic output reports to the nuclear power industry and is utilized to produce special reports upon request. The present data base represents data accumulated from about thirty nuclear units with additional units expected to begin submitting data immediately. The objective is to have essentially all operating nuclear units in the United States of America participating in the program by the end of 1975. The first NPRDS annual reports containing meaningful reliability and failure statistics are expected to be produced following the end of 1975. (author)

Nuclear power plants: 2004 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2005-01-01

In late 2004, nuclear power plants were available for power supply or were under construction in 32 countries worldwide. A total of 441 nuclear power plants, i.e. two plants more than in late 2003, were in operation with an aggregate gross power of approx. 386 GWe and an aggregate net power, respectively, of 362 GWe, in 31 countries. The available capacity of nuclear power plants increased by approx. 5 GWe as a result of the additions by the six units newly commissioned: Hamaoka 5 (Japan), Ulchin 6 (Korea), Kalinin 3 (Russia), Khmelnitski 2 (Ukraine), Qinshan II-2 (People's Republic of China), and Rowno 4 (Ukraine). In addition, unit 3 of the Bruce A nuclear power plant in Canada with a power of 825 MWe was restarted after an outage of many years. Contrary to earlier plans, a recommissioning program was initiated for the Bruce A-1 and A-2 units, which are also down at present. Five plants were decommissioned for good in 2004; Chapelcross 1 to 4 with 50 MWe each in the United Kingdom, and Ignalina 1 with 1 300 MWe in Lithuania. 22 nuclear generating units with an aggregate gross power of 19 GWe in nine countries were under construction in late 2004. In India, construction work was started on a new project, the 500 MWe PFBR prototype fast breeder reactor. In France, the EDF utility announced its intention to build an EPR on the Flamanville site beginning in 2007. (orig.)

User's manual for the BNW-II optimization code for dry/wet-cooled power plants

International Nuclear Information System (INIS)

Braun, D.J.; Bamberger, J.A.; Braun, D.J.; Faletti, D.W.; Wiles, L.E.

1978-05-01

The User's Manual describes how to operate BNW-II, a computer code developed by the Pacific Northwest Laboratory (PNL) as a part of its activities under the Department of Energy (DOE) Dry Cooling Enhancement Program. The computer program offers a comprehensive method of evaluating the cost savings potential of dry/wet-cooled heat rejection systems. Going beyond simple ''figure-of-merit'' cooling tower optimization, this method includes such items as the cost of annual replacement capacity, and the optimum split between plant scale-up and replacement capacity, as well as the purchase and operating costs of all major heat rejection components. Hence the BNW-II code is a useful tool for determining potential cost savings of new dry/wet surfaces, new piping, or other components as part of an optimized system for a dry/wet-cooled plant

Sunflower Plants as Bioindicators of Environmental Pollution with Lead (II Ions

Directory of Open Access Journals (Sweden)

Radka Opatrilova

2009-06-01

Full Text Available In this study, the influence of lead (II ions on sunflower growth and biochemistry was investigated from various points of view. Sunflower plants were treated with 0, 10, 50, 100 and/or 500 µM Pb-EDTA for eight days. We observed alterations in growth in all experimental groups compared with non-treated control plants. Further we determined total content of proteins by a Bradford protein assay. By the eighth day of the experiment, total protein contents in all treated plants were much lower compared to control. Particularly noticeable was the loss of approx. 8 µg/mL or 15 µg/mL in shoots or roots of plants treated with 100 mM Pb-EDTA. We also focused our attention on the activity of alanine transaminase (ALT, aspartate transaminase (AST and urease. Activity of the enzymes increased with increasing length of the treatment and applied concentration of lead (II ions. This increase corresponds well with a higher metabolic activity of treated plants. Contents of cysteine, reduced glutathione (GSH, oxidized glutathione (GSSG and phytochelatin 2 (PC2 were determined by high performance liquid chromatography with electrochemical detection. Cysteine content declined in roots of plants with the increasing time of treatment of plants with Pb-EDTA and the concentration of toxic substance. Moreover, we observed ten times higher content of cysteine in roots in comparison with shoots. The observed reduction of cysteine content probably relates with its utilization for biosynthesis of GSH and phytochelatins, because the content of GSH and PC2 was similar in roots and shoots and increased with increased treatment time and concentration of Pb-EDTA. Moreover, we observed oxidative stress caused by Pb-EDTA in roots where the GSSG/GSH ratio was about 0.66. In shoots, the oxidative stress was less distinctive, with a GSSG/GSH ratio 0.14. We also estimated the rate of phytochelatin biosynthesis from the slope of linear equations plotted with data measured in the

Sunflower Plants as Bioindicators of Environmental Pollution with Lead (II) Ions

Science.gov (United States)

Krystofova, Olga; Shestivska, Violetta; Galiova, Michaela; Novotny, Karel; Kaiser, Jozef; Zehnalek, Josef; Babula, Petr; Opatrilova, Radka; Adam, Vojtech; Kizek, Rene

2009-01-01

In this study, the influence of lead (II) ions on sunflower growth and biochemistry was investigated from various points of view. Sunflower plants were treated with 0, 10, 50, 100 and/or 500 μM Pb-EDTA for eight days. We observed alterations in growth in all experimental groups compared with non-treated control plants. Further we determined total content of proteins by a Bradford protein assay. By the eighth day of the experiment, total protein contents in all treated plants were much lower compared to control. Particularly noticeable was the loss of approx. 8 μg/mL or 15 μg/mL in shoots or roots of plants treated with 100 mM Pb-EDTA. We also focused our attention on the activity of alanine transaminase (ALT), aspartate transaminase (AST) and urease. Activity of the enzymes increased with increasing length of the treatment and applied concentration of lead (II) ions. This increase corresponds well with a higher metabolic activity of treated plants. Contents of cysteine, reduced glutathione (GSH), oxidized glutathione (GSSG) and phytochelatin 2 (PC2) were determined by high performance liquid chromatography with electrochemical detection. Cysteine content declined in roots of plants with the increasing time of treatment of plants with Pb-EDTA and the concentration of toxic substance. Moreover, we observed ten times higher content of cysteine in roots in comparison with shoots. The observed reduction of cysteine content probably relates with its utilization for biosynthesis of GSH and phytochelatins, because the content of GSH and PC2 was similar in roots and shoots and increased with increased treatment time and concentration of Pb-EDTA. Moreover, we observed oxidative stress caused by Pb-EDTA in roots where the GSSG/GSH ratio was about 0.66. In shoots, the oxidative stress was less distinctive, with a GSSG/GSH ratio 0.14. We also estimated the rate of phytochelatin biosynthesis from the slope of linear equations plotted with data measured in the particular

Definition of sampling units begets conclusions in ecology: the case of habitats for plant communities

Directory of Open Access Journals (Sweden)

Martin A. Mörsdorf

2015-03-01

Full Text Available In ecology, expert knowledge on habitat characteristics is often used to define sampling units such as study sites. Ecologists are especially prone to such approaches when prior sampling frames are not accessible. Here we ask to what extent can different approaches to the definition of sampling units influence the conclusions that are drawn from an ecological study? We do this by comparing a formal versus a subjective definition of sampling units within a study design which is based on well-articulated objectives and proper methodology. Both approaches are applied to tundra plant communities in mesic and snowbed habitats. For the formal approach, sampling units were first defined for each habitat in concave terrain of suitable slope using GIS. In the field, these units were only accepted as the targeted habitats if additional criteria for vegetation cover were fulfilled. For the subjective approach, sampling units were defined visually in the field, based on typical plant communities of mesic and snowbed habitats. For each approach, we collected information about plant community characteristics within a total of 11 mesic and seven snowbed units distributed between two herding districts of contrasting reindeer density. Results from the two approaches differed significantly in several plant community characteristics in both mesic and snowbed habitats. Furthermore, differences between the two approaches were not consistent because their magnitude and direction differed both between the two habitats and the two reindeer herding districts. Consequently, we could draw different conclusions on how plant diversity and relative abundance of functional groups are differentiated between the two habitats depending on the approach used. We therefore challenge ecologists to formalize the expert knowledge applied to define sampling units through a set of well-articulated rules, rather than applying it subjectively. We see this as instrumental for progress in

Definition of sampling units begets conclusions in ecology: the case of habitats for plant communities.

Science.gov (United States)

Mörsdorf, Martin A; Ravolainen, Virve T; Støvern, Leif Einar; Yoccoz, Nigel G; Jónsdóttir, Ingibjörg Svala; Bråthen, Kari Anne

2015-01-01

In ecology, expert knowledge on habitat characteristics is often used to define sampling units such as study sites. Ecologists are especially prone to such approaches when prior sampling frames are not accessible. Here we ask to what extent can different approaches to the definition of sampling units influence the conclusions that are drawn from an ecological study? We do this by comparing a formal versus a subjective definition of sampling units within a study design which is based on well-articulated objectives and proper methodology. Both approaches are applied to tundra plant communities in mesic and snowbed habitats. For the formal approach, sampling units were first defined for each habitat in concave terrain of suitable slope using GIS. In the field, these units were only accepted as the targeted habitats if additional criteria for vegetation cover were fulfilled. For the subjective approach, sampling units were defined visually in the field, based on typical plant communities of mesic and snowbed habitats. For each approach, we collected information about plant community characteristics within a total of 11 mesic and seven snowbed units distributed between two herding districts of contrasting reindeer density. Results from the two approaches differed significantly in several plant community characteristics in both mesic and snowbed habitats. Furthermore, differences between the two approaches were not consistent because their magnitude and direction differed both between the two habitats and the two reindeer herding districts. Consequently, we could draw different conclusions on how plant diversity and relative abundance of functional groups are differentiated between the two habitats depending on the approach used. We therefore challenge ecologists to formalize the expert knowledge applied to define sampling units through a set of well-articulated rules, rather than applying it subjectively. We see this as instrumental for progress in ecology as only rules

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-09-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost all the time in the first quarter of 1992. The load factor average was 99.8%. All events which are classified on the International Nuclear Event Scale were level 0/below scale on the Scale. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure, originating from the nuclear power plants, were detected in samples collected in the vicinity of the nuclear power plants

Inventory of Power Plants in the United States, October 1992

Energy Technology Data Exchange (ETDEWEB)

1993-10-27

The Inventory of Power Plants in the United States is prepared annually by the Survey Management Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). The publication also provides a 10-year outlook of future generating unit additions. Data summarized in this report are useful to a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. The report is organized into the following chapters: Year in Review, Operable Electric Generating Units, and Projected Electric Generating Unit Additions. Statistics presented in these chapters reflect the status of electric generating units as of December 31, 1992.

(EFB) for mercury [Hg(II)] removal from aqueous solution

African Journals Online (AJOL)

GREGORY

2011-12-16

Dec 16, 2011 ... United Nations are coal-burning power plants and waste incinerators. They account for approximately .... of 100 rpm, the barrier between the solid-liquid phases was overcome. Agitation at this speed led ... tance at the boundary layer between solid-liquid phases. Effect of contact time on the uptake of Hg(II) ...

Alien plant invasion in mixed-grass prairie: effects of vegetation type, stochiasticity, and anthropogenic disturbance in two park units

Science.gov (United States)

Larson, Diane L.; Anderson, Patrick J.; Newton, Wesley E.

2001-01-01

The ability of alien plant species to invade a region depends not only on attributes of the plant, but on characteristics of the habitat being invaded. Here, we examine characteristics that may influence the success of alien plant invasion in mixed-grass prairie at Theodore Roosevelt National Park, in western North Dakota, USA. The park consists of two geographically separate units with similar vegetation types and management history, which allowed us to examine the effects of native vegetation type, anthropogenic disturbance, and the separate park units on the invasion of native plant communities by alien plant species common to counties surrounding both park units. If matters of chance related to availability of propagules and transient establishment opportunities determine the success of invasion, park unit and anthropogenic disturbance should better explain the variation in alien plant frequency. If invasibility is more strongly related to biotic or physical characteristics of the native plant communities, models of alien plant occurrence should include vegetation type as an explanatory variable. We examined >1300 transects across all vegetation types in both units of the park. Akaike's Information Criterion (AIC) indicated that the fully parameterized model, including the interaction among vegetation type, disturbance, and park unit, best described the distribution of both total number of alien plants per transect and frequency of alien plants on transects where they occurred. Although all vegetation types were invaded by alien plants, mesic communities had both greater numbers and higher frequencies of alien plants than did drier communities. A strong element of stochasticity, reflected in differences in frequencies of individual species between the two park units, suggests that prediction of risk of invasion will always involve uncertainty. In addition, despite well-documented associations between anthropogenic disturbance and alien plant invasion, five of

Integrated Plant Safety Assessment: Systematic Evaluation Program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245. Final report

International Nuclear Information System (INIS)

1983-02-01

This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in November 1982

Unit commitment and investment valuation of flexible biogas plants in German power markets

Energy Technology Data Exchange (ETDEWEB)

Hochloff, Patrick

2017-07-01

Biogas plants contribute a significant share of renewable energy sources (RES) to the electricity system. Most of them are designed to supply constant power generation. In the future biogas plants will most likely become more flexible, scheduling their power generation with respect to market prices. For this purpose power units need extended electrical capacity to convert the continuously produced gas as well as the gas held in storage. When constructing extended capacity at biogas plants, the flexibility premium is the main focus for about 8000 plants which were constructed before August 2014. Additional incomes as a result of selling at higher market prices have been considered, too. However, their relationship to the electrical capacity and storage size of biogas plants was unknown as was the impact on investment valuation. This work has shown how biogas plants with extended capacity can be analyzed when they are operated in power markets, in particular the power spot market and the control reserve markets. Models on the basis of unit commitment have been developed in order to obtain optimized schedules and financial parameters, such as gross income and net present value (NPV), when biogas plants with extended capacity capitalize on prices in each market. The models developed consider several use cases that describe possible ways of participating in German power markets, switching between static and variable gas supply, providing secondary and tertiary control reserve, and claiming the market and flexibility premium. Mixed integer linear programs (MILP) have been developed for the unit commitment of each use case. The model for the unit commitment of providing control reserve with biogas plants made significant progress compared to the state of the art and has been published in (Hochloff, Braun 2014). There are two ways to make use of this model. First of all, the model could be applied to plan daily schedules for the operation of gas plants located at a gas

Unit commitment and investment valuation of flexible biogas plants in German power markets

International Nuclear Information System (INIS)

Hochloff, Patrick

2017-01-01

Biogas plants contribute a significant share of renewable energy sources (RES) to the electricity system. Most of them are designed to supply constant power generation. In the future biogas plants will most likely become more flexible, scheduling their power generation with respect to market prices. For this purpose power units need extended electrical capacity to convert the continuously produced gas as well as the gas held in storage. When constructing extended capacity at biogas plants, the flexibility premium is the main focus for about 8000 plants which were constructed before August 2014. Additional incomes as a result of selling at higher market prices have been considered, too. However, their relationship to the electrical capacity and storage size of biogas plants was unknown as was the impact on investment valuation. This work has shown how biogas plants with extended capacity can be analyzed when they are operated in power markets, in particular the power spot market and the control reserve markets. Models on the basis of unit commitment have been developed in order to obtain optimized schedules and financial parameters, such as gross income and net present value (NPV), when biogas plants with extended capacity capitalize on prices in each market. The models developed consider several use cases that describe possible ways of participating in German power markets, switching between static and variable gas supply, providing secondary and tertiary control reserve, and claiming the market and flexibility premium. Mixed integer linear programs (MILP) have been developed for the unit commitment of each use case. The model for the unit commitment of providing control reserve with biogas plants made significant progress compared to the state of the art and has been published in (Hochloff, Braun 2014). There are two ways to make use of this model. First of all, the model could be applied to plan daily schedules for the operation of gas plants located at a gas

Inventory of power plants in the United States 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-18

The Inventory of Power Plants in the US provides year-end statistics on generating units operated by electric utilities in the US (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of December 31, 1994. The publication also provides a 10-year outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress, Federal, and State agencies; the electric utility industry; and the general public. This is a report of electric utility data; in cases where summary data of nonutility capacity are presented, it is specifically noted as such.

The History of the Construction and Operation of the German KNK II Fast Breeder Power Plant

International Nuclear Information System (INIS)

Marth, W.

1994-11-01

The report gives a historical review of the German KNK fast breeder project, from its beginnings in 1957 up to permanent plant shutdown in 1991. The original design was for the sodium cooled thermal reactor KNK I, which was commissioned on the premises of the Karlsruhe Nuclear Research Center. The conversion into a fast nuclear power plant however was a process, which had to overcome considerable licensing difficulties. KNK II attained high fuel element burnups, and the completion of the fuel cycle was achieved. Various technical problems encountered in specific components are described in detail. After the termination of the SNR 300 fast breeder project in Kalkar for political reasons, KNK II was shutdown in August 1991

Reducing water freshwater consumption at coal-fired power plants : approaches used outside the United States.

Energy Technology Data Exchange (ETDEWEB)

Elcock, D. (Environmental Science Division)

2011-05-09

Coal-fired power plants consume huge quantities of water, and in some water-stressed areas, power plants compete with other users for limited supplies. Extensive use of coal to generate electricity is projected to continue for many years. Faced with increasing power demands and questionable future supplies, industries and governments are seeking ways to reduce freshwater consumption at coal-fired power plants. As the United States investigates various freshwater savings approaches (e.g., the use of alternative water sources), other countries are also researching and implementing approaches to address similar - and in many cases, more challenging - water supply and demand issues. Information about these non-U.S. approaches can be used to help direct near- and mid-term water-consumption research and development (R&D) activities in the United States. This report summarizes the research, development, and deployment (RD&D) status of several approaches used for reducing freshwater consumption by coal-fired power plants in other countries, many of which could be applied, or applied more aggressively, at coal-fired power plants in the United States. Information contained in this report is derived from literature and Internet searches, in some cases supplemented by communication with the researchers, authors, or equipment providers. Because there are few technical, peer-reviewed articles on this topic, much of the information in this report comes from the trade press and other non-peer-reviewed references. Reducing freshwater consumption at coal-fired power plants can occur directly or indirectly. Direct approaches are aimed specifically at reducing water consumption, and they include dry cooling, dry bottom ash handling, low-water-consuming emissions-control technologies, water metering and monitoring, reclaiming water from in-plant operations (e.g., recovery of cooling tower water for boiler makeup water, reclaiming water from flue gas desulfurization [FGD] systems), and

Inspection of licensed nuclear power plants in the United States

International Nuclear Information System (INIS)

Thornburg, H. D.

1977-01-01

Inspection of licensed nuclear power plants in the United States is performed by the Office of Inspection and Enforcement (IE), United States Nuclear Regulatory Commission. IE has several key functions : a) Inspection of licensees and investigation of incidents, occurrences and allegations. b) Detection and correction of safety and security problems. c) Enforcement of rules, regulations, and Commission orders. d) Feedback to the industry and others regarding safety experience. e) Informing the public and others. Major enforcement actions and events involving operating power reactors for the past several years will be summarized. (author)

Concept and structure of instrumentation and control of the Atucha II nuclear power plant

International Nuclear Information System (INIS)

Garzon, D.; Roca, J.L.

1987-01-01

The general structure of instrumentation and control of Atucha II nuclear power plant as well as the technologies used, are described: concepts of functional decentralization and physical centralization; concept of functional group and functional complex; description of the technologies used (physical support) in the project of plant instrumentation and control; description of the different automation levels on the basis of concepts of control interface, automatism, regulation, group and subgroup controls; principles of signal conditioning; concept of announcement of alarms and state: supervisory computer, description of HAS (Hard wired Alarm System) and CAS (Computer Alarm System); application of the above mentioned structure to the project of another type of plants. (Author)

Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (RMIEP)

International Nuclear Information System (INIS)

Payne, A.C. Jr.; Eide, S.A.; LaChance, J.C.; Whitehead, D.W.

1992-10-01

This volume presents the results of the initiating event and accident sequence delineation analyses of the LaSalle Unit II nuclear power plant performed as part of the Level III PRA being performed by Sandia National Laboratories for the Nuclear Regulatory Commission. The initiating event identification included a thorough review of extant data and a detailed plant specific search for special initiators. For the LaSalle analysis, the following initiating events were defined: eight general transients, ten special initiators, four LOCAs inside containment, one LOCA outside containment, and two interfacing LOCAs. Three accident sequence event trees were constructed: LOCA, transient, and ATWS. These trees were general in nature so that a tree represented all initiators of a particular type (i.e., the LOCA tree was constructed for evaluating small, medium, and large LOCAs simultaneously). The effects of the specific initiators on the systems and the different success criteria were handled by including the initiating events directly in the system fault trees. The accident sequence event trees were extended to include the evaluation of containment vulnerable sequences. These internal event accident sequence event trees were also used for the evaluation of the seismic, fire, and flood analyses

The modernization of the nuclear power plants of Asco and Vandellos II; Modernizacion de las centrales nucleares de Asco y Vandellos II

Energy Technology Data Exchange (ETDEWEB)

Martinez Anton, L.

2011-07-01

Since the beginning of their commercial operation, the nuclear power plants of Asco and Vandellos have made design modifications aimed at improving the safety, reliability and operation of the plants. From the moment the management of the three plants was brought together within the Association Nuclear Asco-Vandellos II, and within the assets management process, joint strategic modernisation and improvement plans have been developed on the basis of the status of equipment, the evaluation of their ageing, obsolesce, degradations, manufacturers recommendations and/or the application of new regulations. The article lists the mos important actions already carried out or in the project phase for the 3 plants in the primary and secondary system, electrical and instrumentation systems and auxiliary systems, highlighting the problems and the solutions adopted in the most relevant modifications. (Author)

Regional approaches to power plant siting in the United States of America

International Nuclear Information System (INIS)

DiNunno, J.J.

1975-01-01

The selection and evaluation of sites for power plants in the United States of America have become increasingly difficult in recent years as pressures from various societal segments have resulted in governmental restraints on selection and burning of fossil fuels, methods of heat dissipation, acquisition of transmission rights of way, and on environmental impact of industrialization in general. New legislation at both Federal and state levels has been enacted that influences power plant siting. In addition to environmental requirements that must be satisfied, implementing procedures require documented justification for sites chosen and public disclosure of the basis for selection. Some states have consolidated their regulatory activities in the power plant siting area to provide for a more unified approach to these problems. Although nuclear plants have by far the most rigorous requirements for documentation of site selection and plant design, the application of the same general philosophies to fossil plants has been made in several states and can be anticipated elsewhere. Individual site-related investigations have not so much changed in basics as they have been enlarged in scope. Whereas in the past the search for siting alternatives was frequently confined to a utility's service area, the additional siting constraints represented in environmental laws, the economies of size of nuclear power plants, and the sharing of plant capacities among utilities have contributed to a widening of the search area. Several states have assumed the responsibility for site search and investigation and their efforts extend state-wide. This paper discusses applications of regional approaches to power plant siting in the United States of America using case studies made by NUS Corporation, an engineering/environmental consulting firm. The universality of these approaches is indicated, leaving to national policies and goals the importance of values assigned to the basic siting factors

MOBIL CONTAINER UNIT FOR SEWAGE SLUDGE UTILIZATION FROM SMALL AND MEDIUM WASTWATER TREATMENT PLANTS

OpenAIRE

Stanisław Ledakowicz; Paweł Stolarek; A. Malinowski

2016-01-01

The most wastewater treatment plants in Poland are small and medium plants of flow capacity below 1000 m3/d. These plants are not able to build sludge incineration plants and the transportation costs to the nearest plants increase the total costs of wastewater treatment. Polish company Metal Expert together with the French company ETIA and Lodz University of Technology proposed mobile unit for integrated drying and pyrolysis of sewage sludge in a pilot bench scale with capacity of 100 kg/h ...

China, Japan, and the United States in World War II: The Relinquishment of Unequal Treaties in 1943

Directory of Open Access Journals (Sweden)

Xiaohua Ma

2015-08-01

Full Text Available This paper aims to examine how the United States transformed its foreign policy to promote China as an “equal state” in international politics during World War II, with focus on the process of the American relinquishment of its unequal treaties with China in 1943. In particular, it concentrates on analyzing the conflicts between the United States and Japan in the process of relinquishment. By examining the rivalry between the United States and Japan in the social warfare – propaganda – we can see that the relinquishment of the unequal treaties in 1943 not only marked a historical turning point in America’s China policy, but also had a great impact on the transformation of East Asian politics in World War II and its influence in the world politics.

75 FR 82414 - Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption

Science.gov (United States)

2010-12-30

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2010-0062] Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption 1.0 Background Carolina Power & Light... authorizes operation of the H.B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The license provides, among...

75 FR 11579 - Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption

Science.gov (United States)

2010-03-11

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2010-0062] Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption 1.0 Background Carolina Power & Light... of the H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The license provides, among other things...

Upgrading of fire safety in Indian nuclear power plants

International Nuclear Information System (INIS)

Agarwal, N.K.

1998-01-01

Indian nuclear power programme started with the installation of 2 nos. of Boiling Water Reactor (BWR) at Tarapur (TAPS I and II) of 210 MWe each commissioned in the year 1996. The Pressurized Heavy Water Reactor (PHWR) programme in the country started with the installation of 2x220 MWe stations at Rawatbhatta near Kota (RAPS I and II) in the State of Rajasthan in the sixties. At the present moment, the country has 10 stations in operation. Construction is going on for 4 more units of 220 MWe where as work on two more 500 MWe units is going to start soon. Fire safety systems for the earlier units were engineered as per the state-of-art knowledge available then. The need for review of fire protection systems in the Indian nuclear power plants has also been felt since long almost after Brown's Ferry fire in 1975 itself. Task forces consisting of fire experts, systems design engineers, O and M personnel as well as the Fire Protection engineers at the plant were constituted for each plant to review the existing fire safety provisions in details and highlight the upgradation needed for meeting the latest requirements as per the national as well as international practices. The recommendations made by three such task forces for the three plants are proposed to be reviewed in this paper. The paper also highlights the recommendations to be implemented immediately as well as on long-term basis over a period of time

Manganese Loading and Photosystem II Stability are Key Components of Manganese Efficiency in Plants

DEFF Research Database (Denmark)

Schmidt, Sidsel Birkelund

Manganese (Mn) deficiency constitutes a major plant nutritional problem in commercial crop production of winter cereals. In plants, Mn has an indispensable role in the oxygen evolving complex (OEC) of photosystem II (PSII). Hence, the consequences of Mn deficiency are reduced plant growth......, and eventually substantial yield losses. It is well known, that genotypes within plant species differ considerably in tolerance to growth under Mn limiting conditions, a phenomenon designated as Mn efficiency. However, the physiological responses reflecting the underlying mechanisms of Mn efficiency are still...... not fully understood. In this PhD study, a new method for determination and characterization of metal binding in size-fractionated photosynthetic protein complexes from barley thylakoids was established. The applicability of the method was shown by quantification of Mn binding in PSII from thylakoids of two...

Transgenic rice plants harboring an introduced potato proteinase inhibitor II gene are insect resistant.

Science.gov (United States)

Duan, X; Li, X; Xue, Q; Abo-el-Saad, M; Xu, D; Wu, R

1996-04-01

We introduced the potato proteinase inhibitor II (PINII) gene (pin2) into several Japonica rice varieties, and regenerated a large number of transgenic rice plants. Wound-inducible expression of the pin2 gene driven by its own promoter, together with the first intron of the rice actin 1 gene (act1), resulted in high-level accumulation of the PINII protein in the transgenic plants. The introduced pin2 gene was stably inherited in the second, third, and fourth generations, as shown by molecular analyses. Based on data from the molecular analyses, several homozygous transgenic lines were obtained. Bioassay for insect resistance with the fifth-generation transgenic rice plants showed that transgenic rice plants had increased resistance to a major rice insect pest, pink stem borer (Sesamia inferens). Thus, introduction of an insecticidal proteinase inhibitor gene into cereal plants can be used as a general strategy for control of insect pests.

Operation of Finnish nuclear power plants. Quarterly report, 3rd quarter 1996

International Nuclear Information System (INIS)

Sillanpaeae, T.

1997-02-01

Quarterly Reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety (STUK) considers safety significant. Safety improvements at the plants are also described. The Report also includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. In the third quarter of 1996, the Finnish nuclear power plant units were in power operation except for the annual maintenance outages of Loviisa plant units and a shutdown at Olkiluoto 1 to identify and repair malfunctions of a high pressure turbine control valve. The load factor average of all plant units was 77.2%. Events in the third quarter of 1996 were classified level 0 on the International Nuclear Event Scale. Occupational doses and radioactive releases off-site were below authorised limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. The names of Teollisuuden Voima Oy's plant units have changed. Olkiluoto 1 and Olkiluoto 2 now replace the names TVO I and TVO II previously used in quarterly reports. (orig.)

A novel dinuclear Ru(II) complex having a bridging ligand of a rigid and extended structure. Incorporation of an anthraquinone unit and efficient emission quenching

International Nuclear Information System (INIS)

Mishra, L.; Choi, Chang-Shik; Araki, Koji

1997-01-01

Dinuclear Ru(II) complex having extended conjugation within the bridging ligand was prepared by coupling of the Ru(II) polypyridyl complex having a benzoyl-substituted phenazine unit with diaminoanthraquinone in one step, in which emission from the excited Ru(II) center was efficiently quenched through the anthraquinone unit. (author)

Performance of Canadian commercial nuclear units and heavy water plants

International Nuclear Information System (INIS)

Woodhead, L.W.; Ingolfsrud, L.J.

The operating history of Canadian commercial CANDU type reactors, i.e. Pickering generating station-A, is described. Capacity factors and unit energy costs are analyzed in detail. Equipment performance highlights are given. The performance of the two Canadian heavy water plants is described and five more are under construction or planned. (E.C.B.)

Development of a new USDA plant hardiness zone map for the United States

Science.gov (United States)

C. Daly; M.P. Widrlechner; M.D. Halbleib; J.I. Smith; W.P. Gibson

2012-01-01

In many regions of the world, the extremes of winter cold are a major determinant of the geographic distribution of perennial plant species and of their successful cultivation. In the United States, the U.S. Department of Agriculture (USDA) Plant Hardiness Zone Map (PHZM) is the primary reference for defining geospatial patterns of extreme winter cold for the...

78 FR 49305 - Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2013-08-13

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-445 and 50-446; NRC-2013-0182] Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Application for Amendment to Facility... Operating License Nos. NPF-87 and NPF-89 for the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

Conversion of nuclear power plants into natural gas plant: dismaking the disinformation

International Nuclear Information System (INIS)

Lima Porto, M.S.P. de.

1990-05-01

This work was presented by the Brasilian Nuclear Energy Association - ABEN during the meeting of May 9th of the GT Pronen-Grupo de trabalho do Programa Nacional de Energia Nuclear created by the decret 99194 of March 27, 90. The political subject named convertion of nuclear power plants into natural gas plants is analysed. The conclusion calls for the total technical impossibility of such 'convertion'. The term reconstruction is sugested in substitution to the term convertion. Complete and actual data with figures of the reconstruction, in USA, of the Midland units I and II is presented. The case of Montalto Di Castro plant, in Italy, where no work at all was performed is analysed. Considerations concerning the use of natural gas in the brasilian energy matrix is also presented. (author)

Ab initio calculations of the Fe(II) and Fe(III) isotopic effects in citrates, nicotianamine, and phytosiderophore, and new Fe isotopic measurements in higher plants

Science.gov (United States)

Moynier, Frédéric; Fujii, Toshiyuki; Wang, Kun; Foriel, Julien

2013-05-01

Iron is one of the most abundant transition metal in higher plants and variations in its isotopic compositions can be used to trace its utilization. In order to better understand the effect of plant-induced isotopic fractionation on the global Fe cycling, we have estimated by quantum chemical calculations the magnitude of the isotopic fractionation between different Fe species relevant to the transport and storage of Fe in higher plants: Fe(II)-citrate, Fe(III)-citrate, Fe(II)-nicotianamine, and Fe(III)-phytosiderophore. The ab initio calculations show firstly, that Fe(II)-nicotianamine is ˜3‰ (56Fe/54Fe) isotopically lighter than Fe(III)-phytosiderophore; secondly, even in the absence of redox changes of Fe, change in the speciation alone can create up to ˜1.5‰ isotopic fractionation. For example, Fe(III)-phytosiderophore is up to 1.5‰ heavier than Fe(III)-citrate2 and Fe(II)-nicotianamine is up to 1‰ heavier than Fe(II)-citrate. In addition, in order to better understand the Fe isotopic fractionation between different plant components, we have analyzed the iron isotopic composition of different organs (roots, seeds, germinated seeds, leaves and stems) from six species of higher plants: the dicot lentil (Lens culinaris), and the graminaceous monocots Virginia wild rye (Elymus virginicus), Johnsongrass (Sorghum halepense), Kentucky bluegrass (Poa pratensis), river oat (Uniola latifolia), and Indian goosegrass (Eleusine indica). The calculations may explain that the roots of strategy-II plants (Fe(III)-phytosiderophore) are isotopically heavier (by about 1‰ for the δ56Fe) than the upper parts of the plants (Fe transported as Fe(III)-citrate in the xylem or Fe(II)-nicotianamine in the phloem). In addition, we suggest that the isotopic variations observed between younger and older leaves could be explained by mixing of Fe received from the xylem and the phloem.

A large economic liquid metal reactor for United States utilities

International Nuclear Information System (INIS)

Rodwell, E.

1985-01-01

The United States has demonstrated its ability to build and operate small and medium sized liquid metal reactors and continues to operate the Experimental Breeder Reactor II and the Fast Flux Test Facility to demonstrate long life fuel designs. Similar-sized liquid metal reactors in Europe have been followed by a step-up to the 1200 MWe capacity of the Superphenix plant. To permit the United States to make a similar step-up in capacity, a 1320 MWe liquid metal reactor plant has been designed with the main emphasis on minimizing the specific capital cost in order to be competitive with light water reactor plant and fossil plant alternatives. The design is based on a four parallel heat transport loops arrangement and complies with current regulatory requirements. The primary heat transport loops are now being integrated into the reactor vessel to achieve further reduction in the capital cost

Start up and commercial operation of Laguna Verde nuclear power plant. Unit 1

International Nuclear Information System (INIS)

Torres Ramirez, J.F.

1991-01-01

Prior to start up of Laguna Verde nuclear power plant preoperational tests and start tests were performed and they are described in its more eminent aspects. In relation to commercial operation of nuclear station a series of indicator were set to which allow the measurement of performance in unit 1, in areas of plant efficiency and personal safety. Antecedents. Laguna Verde station is located in Alto Lucero municipality in Veracruz state, 70 kilometers north-northeast from port of Veracruz and a 290 kilometers east-northeast from Mexico city. The station consist of two units manufactured by General Electric, with a nuclear system of vapor supply also called boiling water (BWR/5), and with a system turbine-generator manufactured by Mitsubishi. Each unit has a nominal power of 1931 MWt and a level design power of 675 Mwe and a net power of 654 Electric Megawatts

On economic efficiency of nuclear power unit life extension using steam-gas topping plant

International Nuclear Information System (INIS)

Kuznetsov, Y.N.; Lisitsa, F.D.; Smirnov, V.G.

2001-01-01

The different options for life extension of the operating nuclear power units have been analyzed in the report with regard for their economic efficiency. A particular attention is given to the option envisaging the reduction of reactor power output and its subsequent compensation with a steam-gas topping plant. Steam generated at its heat-recovery boilers is proposed to be used for the additional loading of the nuclear plant turbine so as to reach its nominal output. It would be demonstrated that the implementation of this option allows to reduce total costs in the period of power plant life extension by 24-29% as compared with the alternative use of the replacing steam-gas unit and the saved resources could be directed, for instance, for decommissioning of a reactor facility. (authors)

Cernavoda NPP Unit 1 - a plant of several generations

International Nuclear Information System (INIS)

Rotaru, I.; Metes, M.; Anghelescu, M.S.

2001-01-01

The paper reflects some key aspects related to the shift of generations during the project's development, including the present stage. Further, the place of Cernavoda NPP Unit 1 in the Romanian power sector and among other nuclear stations in the world is presented. The operational performances achieved 'in service' up to the end of 1999, with reference to the performance indicators for electrical energy production, nuclear safety, radiation protection, radioactive wastes and nuclear fuel are illustrated. For all of these items, comparisons are performed with similar indicators reported by other worldwide nuclear power plants, in order to assess our results. Finally, some comments about Cernavoda NPP Unit 2 project status and need to completion and commissioning it are included. (authors)

The xanthophylls in light-harvesting complex II of higher plants: light harvesting and triplet quenching.

NARCIS (Netherlands)

Peterman, E.J.G.; Gradinaru, C.C.; Calkoen, F.; Borst, J.C.; van Grondelle, R.; van Amerongen, H.

1997-01-01

A spectral and functional assignment of the xanthophylls in monomeric and trimeric light-harvesting complex II of green plants has been obtained using HPLC analysis of the pigment composition, laser-flash induced triplet- minus-singlet, fluorescence excitation, and absorption spectra. It is shown

AKUT-II: an experimental plant for purifying the HTR loop of combustion waste gas

Energy Technology Data Exchange (ETDEWEB)

Beaujean, H.; Vygen, H.

1976-02-15

A plant for the separation of aerosols, krypton and tritium (AKUT) used for purifying the head end of the reprocessing of thorium-containing fuel elements from combustion waste gases is described. Data are to be collected to enable a process engineer to plan and construct a large-scale plant, and the correctness and practicability of the concept adopted is to be proved in conjunction with the JUPITER plant. It is true that the tests on the AKUT I plant confirmed that the flow scheme was basically correct, but the actual experimental operation was considerably limited by a fixed and rigid coupling to the combustion furnace. Some operational conditions were encountered which did not meet the design values. Part of the plant (krypton separation) is being tested in the USA. The German concept was taken over in the early stages of tests and adapted to existing apparatuses, the result inevitably being different experimental conditions. The AKUT II plant can now be used for consideration of the economic and safety conditions, and comparisons can be made.

The comparison of license management procedure for nuclear power plant in China and United States

International Nuclear Information System (INIS)

Yu Zusheng

2006-01-01

'Tow steps' license management procedure for nuclear power plant has been performed bas- ted on the requirement of 10CFR Part50-DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES in United States since last century fifties. In order to ulterior reduce the risk of investment and technical for new construction nuclear power plants, new regulations 'One step' license management procedure-10CFR Part52-EARLY SITE PERMITS; STANDARD DESIGN CERTIFICATIONS; AND COMBINED LICENSES FOR NUCLEAR POWER PLANTS issued in 1989. The new regulations has been adopted by new design of nuclear power plant, for example AP1000. ‘The similar tow steps’ license management procedure for nuclear power plant has been performed basted on the requirement of HAFO01/01 Rules for the Implementation of Regulations on the Safety Regulation for Civilian Nuclear Installations of the People's Re- public of China Part One: Application and Issuance of Safety License for Nuclear Power Plant (December 1993) in China since last century nineties. This article introduces and compares the requirements and characteristics of above license management procedure for nuclear power plant in China and United States. (author)

Operable Unit 3-13, Group 3, Other Surface Soils (Phase II) Field Sampling Plan

Energy Technology Data Exchange (ETDEWEB)

G. L. Schwendiman

2006-07-27

This Field Sampling Plan describes the Operable Unit 3-13, Group 3, Other Surface Soils, Phase II remediation field sampling activities to be performed at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory Site. Sampling activities described in this plan support characterization sampling of new sites, real-time soil spectroscopy during excavation, and confirmation sampling that verifies that the remedial action objectives and remediation goals presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13 have been met.

Plants lacking the main light-harvesting complex retain photosystem II macro-organization

OpenAIRE

Ruban, AV; Wentworth, M; Yakushevska, AE; Andersson, J; Lee, PJ; Keegstra, W; Dekker, JP; Boekema, EJ; Jansson, S; Horton, P

2003-01-01

Photosystem II (PSII) is a key component of photosynthesis, the process of converting sunlight into the chemical energy of life. In plant cells, it forms a unique oligomeric macrostructure in membranes of the chloroplasts(1). Several light-harvesting antenna complexes are organized precisely in the PSII macrostructure-the major trimeric complexes (LHCII)(2) that bind 70% of PSII chlorophyll and three minor monomeric complexes(3)-which together form PSII supercomplexes(4-6). The antenna comple...

Analysis and Prototyping of the United States Marine Corps Total Force Administration System (TFAS), Echelon II - A Web Enabled Database for the Small Unit Leader

National Research Council Canada - National Science Library

Simmons, Steven

2002-01-01

...), Echelon II - A Web Enabled Database for The Small Unit Leader. The analysis consisted of researching the characteristics of the current manpower system, MCTFS, and the conceptual tenets of the TFAS program...

Standardization of nuclear power plants in the United States: recent regulatory developments

International Nuclear Information System (INIS)

Cowan, B.Z.; Tourtellotte, J.R.

1992-01-01

On April 18, 1989, the United States (U.S.) Nuclear Regulatory Commission (NRC) amended the regulations governing the process for licensing nuclear power plants in the United States to provide for issuance of early site permits, standard design certifications and combined construction permits and operating licenses for nuclear power reactors. The new regulations are designed to achieve early resolution of licensing issues and facilitate standardization of nuclear power plants in the United States. The program for design standardization is central to efforts mounted by the U.S. government and industry to ensure that there will be a next generation of nuclear power facilities in the U.S. The most significant changes are provisions for certification of standard designs and for issuance prior to start of construction of combined licenses which incorporate a construction permit and an operating license with conditions. Such certifications and combined licenses must contain tests, inspections and analyses, and acceptance criteria, which are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will operate in accordance with the combined license. A number of significant implementation issues have arisen. In addition a major court case brought by several anti-nuclear groups is pending, challenging NRC authority to issue combined licenses. It is the goal of the U.S. nuclear industry to have the first of the next generation of standardized nuclear power plants ordered, licensed, constructed and on-line by the year 2000. (author)

Large-Scale Combined Heat and Power (CHP) Generation at Loviisa Nuclear Power Plant Unit 3

International Nuclear Information System (INIS)

Bergroth, N.

2010-01-01

Fortum has applied for a Decision in Principle concerning the construction of a new nuclear power plant unit (Loviisa 3) ranging from 2800-4600 MWth at its site located at the southern coast of Finland. An attractive alternative investigated is a co-generation plant designed for large-scale district heat generation for the Helsinki metropolitan area that is located approximately 75 km west of the site. The starting point is that the district heat generation capacity of 3 unit would be around 1 000 MWth.The possibility of generating district heat for the metropolitan area by Loviisa's two existing nuclear power plant units was investigated back in the 1980s, but it proved unpractical at the time. With the growing concern of the climate change and the subsequent requirements on heat and power generation, the idea is much more attractive today, when recognising its potential to decrease Finland's carbon dioxide emissions significantly. Currently the district heat generation in metropolitan area is based on coal and natural gas, producing some five to seven million tonnes of carbon dioxide emissions annually. Large-scale combined heat and power (CHP) generation at the 3 unit could cut this figure by up to four million tonnes. This would decrease carbon dioxide emissions by as much as six percent. In addition, large-scale CHP generation would increase the overall efficiency of the new unit significantly and hence, reduce the environmental impact on the local marine environment by cutting heat discharges into the Gulf of Nuclear energy has been used for district heating in several countries both in dedicated nuclear heating plants and in CHP generation plants. However, the heat generation capacity is usually rather limited, maximum being around 250 MWth per unit. Set against this, the 3 CHP concept is much more ambitious, not only because of the much larger heat generation output envisaged, but also because the district heating water would have to be transported over a

Data handling at EBR-II [Experimental Breeder Reactor II] for advanced diagnostics and control work

International Nuclear Information System (INIS)

Lindsay, R.W.; Schorzman, L.W.

1988-01-01

Improved control and diagnostics systems are being developed for nuclear and other applications. The Experimental Breeder Reactor II (EBR-II) Division of Argonne National Laboratory has embarked on a project to upgrade the EBR-II control and data handling systems. The nature of the work at EBR-II requires that reactor plant data be readily available for experimenters, and that the plant control systems be flexible to accommodate testing and development needs. In addition, operational concerns require that improved operator interfaces and computerized diagnostics be included in the reactor plant control system. The EBR-II systems have been upgraded to incorporate new data handling computers, new digital plant process controllers, and new displays and diagnostics are being developed and tested for permanent use. In addition, improved engineering surveillance will be possible with the new systems

Small Diameter Bomb Increment II (SDB II)

Science.gov (United States)

2015-12-01

Selected Acquisition Report (SAR) RCS: DD-A&T(Q&A)823-439 Small Diameter Bomb Increment II (SDB II) As of FY 2017 President’s Budget Defense... Bomb Increment II (SDB II) DoD Component Air Force Joint Participants Department of the Navy Responsible Office References SAR Baseline (Production...Mission and Description Small Diameter Bomb Increment II (SDB II) is a joint interest United States Air Force (USAF) and Department of the Navy

MRP II (material requirements planning): one year later.

Science.gov (United States)

Tull, W L; Norman, R L

1994-08-01

This article addresses the continued need for the behavior change process that must be managed long after materiel requirements planning (MRP II) implementation. Mason & Hanger, Pantex Plant is the final assembly and dismantlement facility for all United States nuclear weapons. On October 1, 1990, Mason & Hanger implemented a full production cutover to MRP II. One year later, following class A certification, the MRP II implementation team is still actively managing the change process through education and training programs and overall continuous improvement initiatives. Actual behavior change problems are identified together with the proven solutions implemented in a government-owned, contractor-operated facility environment. Performance measurements ranging from senior management planning to shop floor accomplishments and cost variance reports are shown as normal management tools used to identify target improvement areas.

Critical area planting in the United States of America | G | African ...

African Journals Online (AJOL)

The importance of vegetation on disturbed or critical areas of the United States of America has long been evident. A wide range of climatic, soil and environmental conditions has resulted in a search for suitable grass species and methods for their establishment. Plant material centres have done considerable work in ...

User's manual for the BNW-II optimization code for dry/wet-cooled power plants

Energy Technology Data Exchange (ETDEWEB)

Braun, D.J.; Bamberger, J.A.; Braun, D.J.; Faletti, D.W.; Wiles, L.E.

1978-05-01

The User's Manual describes how to operate BNW-II, a computer code developed by the Pacific Northwest Laboratory (PNL) as a part of its activities under the Department of Energy (DOE) Dry Cooling Enhancement Program. The computer program offers a comprehensive method of evaluating the cost savings potential of dry/wet-cooled heat rejection systems. Going beyond simple ''figure-of-merit'' cooling tower optimization, this method includes such items as the cost of annual replacement capacity, and the optimum split between plant scale-up and replacement capacity, as well as the purchase and operating costs of all major heat rejection components. Hence the BNW-II code is a useful tool for determining potential cost savings of new dry/wet surfaces, new piping, or other components as part of an optimized system for a dry/wet-cooled plant.

Inventory of power plants in the United States as of January 1, 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the US (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1998. The publication also provides a 10-year outlook for generating unit additions and generating unit changes. This report is prepared annually by the Energy Information Administration (EIA). Data summarized in this report are useful to a wide audience. This is a report of electric utility data; in cases where summary data or nonconfidential data of nonutilities are presented, it is specifically noted as nonutility data. 19 figs., 36 tabs.

Safety philosophy in upgrading the EBR-II plant protection system

International Nuclear Information System (INIS)

Sackett, J.I.

1976-01-01

The EBR-II plant protection system (PPS) has been substantially modified, upgrading its performance to more fully comply with modern safety philosophy and criteria. The upgrading effort required that the total reactor system be evaluated for possible faults and that a PPS be designed to accommodate them. The result was deletion of a number of existing trip functions and upgrading of others. Particular attention was given to loss of primary pumping power and reactivity insertion events. The design and performance criteria for the PPS has been more firmly established, understanding of the PPS function has been improved and the reactor has been subjected to fewer spurious trips, improving operational reliability

Thiolato-bridged RuIIAgIRuII trinuclear complex composed of bis(bipyridine)ruthenium(II) units with chelating 2-aminoethanethiolate: conversion to a disulfide-bridged RuIIRuII dinuclear complex.

Science.gov (United States)

Tamura, Motoshi; Matsuura, Noriyuki; Kawamoto, Tatsuya; Konno, Takumi

2007-08-20

The reaction of [Ru(solvent)2(bpy)2]2+ (bpy = 2,2'-bipyridine) with Haet (2-aminoethanethiol) in ethanol/water in the presence of Ag+ gave a thiolato-bridged RuIIAgIRuII trinuclear complex, [Ag{Ru(aet)(bpy)2}2]3+, in which two [RuII(aet)(bpy)2]+ units are linked by an AgI atom. When this complex was treated with HCl in acetonitrile/water, a disulfide-bridged RuIIRuII dinuclear complex, [Ru2(cysta)(bpy)4]4+ (cysta = cystamine), was produced as a result of the removal of an AgI atom and the autoxidation of thiolato groups. It was found that the dinuclear structure in [Ru2(cysta)(bpy)4]4+ is reverted back to [Ag{Ru(aet)(bpy)2}2]3+ by treatment with Ag+ assisted by Zn reduction.

Vegetation and plant food reconstruction of lowermost Bed II, Olduvai Gorge, using modern analogs.

Science.gov (United States)

Copeland, Sandi R

2007-08-01

Vegetation and plant foods for hominins of lowermost Bed II, Olduvai Gorge were modeled by examining vegetation in modern habitats in northern Tanzania (Lake Manyara, Ngorongoro, Serengeti) that are analogous to the paleolandscape in terms of climate, land forms, and soil types, as indicated by previous paleoenvironmental studies of Olduvai. Plant species in the modern habitats were identified in a series of sample plots, and those known to be eaten by modern humans, chimpanzees, or baboons were considered potentially edible for early hominins. Within the 50-80 kyr deposition of lowermost Bed II, periods of drier climate were characterized by low lake stands and a broad eastern lacustrine plain containing a mosaic of springs, marsh, woodland, and edaphic grassland. Based on results of this study, plant food diversity in each of those habitats was relatively low, but the mosaic nature of the area meant that hominins could reach several different habitat types within short distances, with access to potential plant foods including marsh plants, grass grains, roots, shrub fruits, edible parts from palms, leafy herbaceous plants, and Acacia pods, flowers, and gum. Based on Manyara analogs, a greater variety of plant foods, such as tree fruits (e.g., Ficus, Trichilia) and the roots and fruits of shrubs (e.g., Cordia, Salvadora) would be expected further east along the rivers in the lacustrine terrace and alluvial fans. Interfluves of the alluvial fans were probably less wooded and offered relatively fewer varieties of plant foods, but there is sparse paleoenvironmental evidence for the character of Olduvai's alluvial fans, making the choice of appropriate modern analogs difficult. In the western side of the basin, based on modern analogs in the Serengeti, riverine habitats provided the greatest variety of edible plant food species (e.g., Acacia, Grewia, Justicia). If the interfluves were grassland, then a large variety of potentially edible grasses and forbs were present

Atucha II nuclear power plant digital simulation

International Nuclear Information System (INIS)

Santome, D.; Rovere, L.A.T.

1987-01-01

This paper describes the start-up of a digital simulation code apt to be performed in real time of Atucha II nuclear power plant, foreseeing its subsequent usage in a Basic Principles Simulator. Adaptability and modification of existing routines and development of modules in order to incorporate the necessary variables dynamics to couple the different modes, were the main tasks. The mathematical model used allows the representation of the following sub-systems: a) a reactor's core point model, which comprehends the neutronic kinetics, fission and decaying powers, thermal transfer and Xe-poisoning calculation; b) pressurizer, which considers two sub-systems that may or may not be in thermodynamic equilibrium, both in two phases; c) coolants and moderators bonds considering separate moderator loops with the aim of introducing asymmetric perturbations; d) secondary sub-subsystem, which includes the feed water loop, pumps, steam generators and control valves; e) steam generators; f) control and safety systems, including power control, steam generators levels, moderator's temperature primary loop system, limitations and protection. (Author)

Radiation effects on resins and zeolites at Three Mile Island Unit II

International Nuclear Information System (INIS)

Reilly, J.K.; Grant, P.J.; Hofstetter, K.J.; Quinn, G.J.; Runion, T.C.

1984-01-01

The March 1979 accident at Three Mile Island created certain waste forms that are not routinely encountered in normal light water reactor plants and were the subject of a research and development program. Fifty EPICOR II organic resin containers were loaded to as much as 2200 Ci (of predominantly cesium plus strontium) in the course of processing contaminated water. Resin samples were taken from two of the EPICOR II vessels and examined. Nineteen zeolite containers loaded with radioactive cesium plus strontium to as much as 55,000 Ci have been analyzed. The makeup and purification system demineralizer resins, highly contaminated by the letdown of reactor coolant, have been radiation surveyed, and gas, liquid, and resin samples have been obtained. On-site sampling and analysis of these wastes indicated that combustible gases (hydrogen and oxygen) were being generated as a result of radiolysis. The results of this work are discussed, compared, and presented

Solvent-refined-coal (SRC) process. Volume II. Sections V-XIV. Final report

Energy Technology Data Exchange (ETDEWEB)

1982-05-01

This report documents the completion of development work on the Solvent Refined Coal Process by The Pittsburgh and Midway Coal Mining Co. The work was initiated in 1966 under Office of Coal Research, US Department of Interior, Contract No. 14-01-0001-496 and completed under US Department of Energy Contract No. DE-AC05-79ET10104. This report discusses work leading to the development of the SRC-I and SRC-II processes, construction of the Fort Lewis Pilot Plant for the successful development of these processes, and results from the operation of this pilot plant. Process design data generated on a 1 ton-per-day Process Development Unit, bench-scale units and through numerous research projects in support of the design of major demonstration plants are also discussed in summary form and fully referenced in this report.

Predictive validity of the Hendrich fall risk model II in an acute geriatric unit.

Science.gov (United States)

Ivziku, Dhurata; Matarese, Maria; Pedone, Claudio

2011-04-01

Falls are the most common adverse events reported in acute care hospitals, and older patients are the most likely to fall. The risk of falling cannot be completely eliminated, but it can be reduced through the implementation of a fall prevention program. A major evidence-based intervention to prevent falls has been the use of fall-risk assessment tools. Many tools have been increasingly developed in recent years, but most instruments have not been investigated regarding reliability, validity and clinical usefulness. This study intends to evaluate the predictive validity and inter-rater reliability of Hendrich fall risk model II (HFRM II) in order to identify older patients at risk of falling in geriatric units and recommend its use in clinical practice. A prospective descriptive design was used. The study was carried out in a geriatric acute care unit of an Italian University hospital. All over 65 years old patients consecutively admitted to a geriatric acute care unit of an Italian University hospital over 8-month period were enrolled. The patients enrolled were screened for the falls risk by nurses with the HFRM II within 24h of admission. The falls occurring during the patient's hospital stay were registered. Inter-rater reliability, area under the ROC curve, sensitivity, specificity, positive and negative predictive values and time for the administration were evaluated. 179 elderly patients were included. The inter-rater reliability was 0.87 (95% CI 0.71-1.00). The administration time was about 1min. The most frequently reported risk factors were depression, incontinence, vertigo. Sensitivity and specificity were respectively 86% and 43%. The optimal cut-off score for screening at risk patients was 5 with an area under the ROC curve of 0.72. The risk factors more strongly associated with falls were confusion and depression. As falls of older patients are a common problem in acute care settings it is necessary that the nurses use specific validate and reliable

Cernavoda NPP Unit 1 - a plant of several generations

International Nuclear Information System (INIS)

Rotaru, I.; Metes, M.; Anghelescu, M.S.

2000-01-01

Cernavoda NPP Unit 1, the first nuclear power unit in Romania, has a long and tormented history. It represents a rather unique case in Eastern Europe. The project started well before 1989 (the construction phase lasted 17 years and generations were involved in its completion), but it is effectively based on western technology (Candu). Meanwhile, the national nuclear program underwent many changes, affecting the lives and careers of Romanian nuclear professionals. Finally, on December 2 nd 1996, the unit began its c ommercial operation , being operated at its nominal power rating of 706 MW e . It now provides a reliable source of electricity for Romanian economy, supplying to the national grid about 10% of the country's average annual demand. The paper reflects some aspects related to the shift of generations during the project's development, including the present stage. The operational performances achieved 'in service' by Cernavoda NPP Unit 1 up to the end of 1999 , are also presented. Reference to the electrical energy production, performance indicators, production costs, nuclear safety, radiation protection, radioactive wastes, nuclear fuel consumption and nuclear fuel performances are included. Comparisons are performed with similar indicators reported by other worldwide nuclear power plants, in order to assess our results. (authors)

75 FR 20867 - DTE Energy; Enrico Fermi Atomic Power Plant, Unit 1

Science.gov (United States)

2010-04-21

... Power Plant, Unit 1 Environmental Assessment and Finding of No Significant Impact for an Exemption From... County, Michigan. Environmental Assessment Identification of Proposed Action The proposed action is in... the Michigan Department of Natural Resources and the Environment, Radiological Protection and Medical...

78 FR 66779 - United States Enrichment Corporation, Paducah Gaseous Diffusion Plant, Including On-Site Leased...

Science.gov (United States)

2013-11-06

... DEPARTMENT OF LABOR Employment and Training Administration [TA-W-82,862] United States Enrichment..., applicable to workers of United States Enrichment Corporation, Paducah Gaseous Diffusion Plant, including on... were engaged in the production of low enrichment uranium. The company reports that workers leased from...

Plants lacking the main light-harvesting complex retain photosystem II macro-organization.

Science.gov (United States)

Ruban, A V; Wentworth, M; Yakushevska, A E; Andersson, J; Lee, P J; Keegstra, W; Dekker, J P; Boekema, E J; Jansson, S; Horton, P

2003-02-06

Photosystem II (PSII) is a key component of photosynthesis, the process of converting sunlight into the chemical energy of life. In plant cells, it forms a unique oligomeric macrostructure in membranes of the chloroplasts. Several light-harvesting antenna complexes are organized precisely in the PSII macrostructure-the major trimeric complexes (LHCII) that bind 70% of PSII chlorophyll and three minor monomeric complexes-which together form PSII supercomplexes. The antenna complexes are essential for collecting sunlight and regulating photosynthesis, but the relationship between these functions and their molecular architecture is unresolved. Here we report that antisense Arabidopsis plants lacking the proteins that form LHCII trimers have PSII supercomplexes with almost identical abundance and structure to those found in wild-type plants. The place of LHCII is taken by a normally minor and monomeric complex, CP26, which is synthesized in large amounts and organized into trimers. Trimerization is clearly not a specific attribute of LHCII. Our results highlight the importance of the PSII macrostructure: in the absence of one of its main components, another protein is recruited to allow it to assemble and function.

Millstone Unit 1 plant vulnerabilities during postulated severe nuclear accidents

International Nuclear Information System (INIS)

Khalil, Y.F.

1993-01-01

Generic Letter 88-20, Supplement No. 1 (Ref. 1), issued by the Nuclear Regulatory Commission (NRC) requested all licensees holding operating licenses and construction permits for nuclear power reactor facilities to perform Individual Plant Examinations (IPE) of their plant(s) for severe accident vulnerabilities and to submit the results to the Commission. This paper summarizes the major Front-End (Level-1 PRA) and Back-End (Level-2 PRA) insights gained from the Millstone Unit 1 (MP-1) IPE study. No major plant vulnerabilities have been identified from a Front-End perspective. The Back-End analysis, however, has identified two potential containment vulnerabilities during postulated events that progress beyond the Design Basis Accidents (DBAs), namely, (1) MP-1 is dominated by early source term releases that would occur within a six-hour time frame from time of accident initiation, or reactor trip, and (2) MP-1 containment is somewhat vulnerable to leak-type failure through the drywell head. As a result of the second finding, a recommendation currently under evaluation, has been made to increase the drywell head bolt's preload from 54 Kips to resist the containment design pressure value (62 psig)

Simulating the Water Use of Thermoelectric Power Plants in the United States: Model Development and Verification

Science.gov (United States)

Betrie, G.; Yan, E.; Clark, C.

2016-12-01

Thermoelectric power plants use the highest amount of freshwater second to the agriculture sector. However, there is scarcity of information that characterizes the freshwater use of these plants in the United States. This could be attributed to the lack of model and data that are required to conduct analysis and gain insights. The competition for freshwater among sectors will increase in the future as the amount of freshwater gets limited due climate change and population growth. A model that makes use of less data is urgently needed to conduct analysis and identify adaptation strategies. The objectives of this study are to develop a model and simulate the water use of thermoelectric power plants in the United States. The developed model has heat-balance, climate, cooling system, and optimization modules. It computes the amount of heat rejected to the environment, estimates the quantity of heat exchanged through latent and sensible heat to the environment, and computes the amount of water required per unit generation of electricity. To verify the model, we simulated a total of 876 fossil-fired, nuclear and gas-turbine power plants with different cooling systems (CS) using 2010-2014 data obtained from Energy Information Administration. The CS includes once-through with cooling pond, once-through without cooling ponds, recirculating with induced draft and recirculating with induced draft natural draft. The results show that the model reproduced the observed water use per unit generation of electricity for the most of the power plants. It is also noticed that the model slightly overestimates the water use during the summer period when the input water temperatures are higher. We are investigating the possible reasons for the overestimation and address it in the future work. The model could be used individually or coupled to regional models to analyze various adaptation strategies and improve the water use efficiency of thermoelectric power plants.

Variation in MHC class II B genes in marbled murrelets: implications for delineating conservation units

Science.gov (United States)

C. Vásquez-Carrillo; V. Friesen; L. Hall; M.Z. Peery

2013-01-01

Conserving genetic variation is critical for maintaining the evolutionary potential and viability of a species. Genetic studies seeking to delineate conservation units, however, typically focus on characterizing neutral genetic variation and may not identify populations harboring local adaptations. Here, variation at two major histocompatibility complex (MHC) class II...

Beznau II nuclear power plant: Expertise on NOK's request for the removal of the time limitation for the operation licence

International Nuclear Information System (INIS)

2004-03-01

The Federal Agency for the Safety of Nuclear Installations (HSK) is the Swiss authority responsible for nuclear safety and protection against radioactivity in nuclear power plants. It has to examine the request of the North-East Swiss Power Corporation (NOK) concerning the removal of the operational time limitation for the Beznau-II reactor (KKB-II). In the present report HSK reviews the enterprise management and the safety of KKB-II on the basis of the results of the Periodic Safety Review. The Beznau nuclear power plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner. At the same time the plant has been improved and this guarantees that the mechanisms of ageing degradation are systematically identified and that measures can be taken that are possibly necessary. Under such conditions, the safety of KKB-II can be guarantied at all times. As a result of the management of quality, environmental and working safety conditions, the correct application and the continuous improvement of all processes important to safety are ensured. With these measures KKB has shown that safety is given priority over and against all other working goals. The examination by HSK of the Periodic Safety Review has shown that, in the past, KKB has applied modernisation measures independent of the licensing situation of the two reactor blocks. These modernisation measures largely contribute to the fact that the HSK examination did not reveal any significant safety deficiencies. Other improvement measures allow risk reduction or can bee seen as an adaptation to experience gained and to the state of the technological art. In conclusion, HSK states that no safety-relevant facts have been found which could prevent the removal of the time limitation on the operational licence for KKB-II. From the point of view of HSK, KKB-II fulfils the conditions for the safe continuation of operation

Safety review on unit testing of safety system software of nuclear power plant

International Nuclear Information System (INIS)

Liu Le; Zhang Qi

2013-01-01

Software unit testing has an important place in the testing of safety system software of nuclear power plants, and in the wider scope of the verification and validation. It is a comprehensive, systematic process, and its documentation shall meet the related requirements. When reviewing software unit testing, attention should be paid to the coverage of software safety requirements, the coverage of software internal structure, and the independence of the work. (authors)

Summary data for U.S. commercial nuclear power plants in the United States

International Nuclear Information System (INIS)

Heddleson, F.A.

1978-01-01

A compilation of data is presented for all United States commercial nuclear power plants for which a construction permit application was made through the Nuclear Regulatory Commission. The data are compiled in four separate tables with cross-referencing indexes: Table 1--General Data; Table 2--Reactor Data; Table 3--Site Data, and Table 4--Circulating-Water System Data. The power plants are listed in numerical order by docket number in all four tables

Kozloduy nuclear power plant. Units 1-4. Status of safety improvements. Rev. 2

International Nuclear Information System (INIS)

1999-01-01

This paper presents the results of the safety improvements activities carried out by the Kozloduy Nuclear Power Plant (KNPP) within the period 1990-1998. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of russian design developed according to the safety standards in force in USSR in late sixties. Up to now 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short term program was implemented between from 1991 to 1997 owing to strong safety commitment of NEC and KNPP staff as well as broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. In parallel a special assessment process started in 1995 in order to evaluate the level of safety, achieved by Short Term Program, according to current safety standards and to define the measures, which should be implemented by the Utility to complete the process of improving the safety in future

Synthesis and spectroscopic studies of biologically active tetraazamacrocyclic complexes of Mn(II, Co(II, Ni(II, Pd(II and Pt(II

Directory of Open Access Journals (Sweden)

Monika Tyagi

2014-01-01

Full Text Available Complexes of Mn(II, Co(II, Ni(II, Pd(II and Pt(II were synthesized with the macrocyclic ligand, i.e., 2,3,9,10-tetraketo-1,4,8,11-tetraazacycoletradecane. The ligand was prepared by the [2 + 2] condensation of diethyloxalate and 1,3-diamino propane and characterized by elemental analysis, mass, IR and 1H NMR spectral studies. All the complexes were characterized by elemental analysis, molar conductance, magnetic susceptibility measurements, IR, electronic and electron paramagnetic resonance spectral studies. The molar conductance measurements of Mn(II, Co(II and Ni(II complexes in DMF correspond to non electrolyte nature, whereas Pd(II and Pt(II complexes are 1:2 electrolyte. On the basis of spectral studies an octahedral geometry has been assigned for Mn(II, Co(II and Ni(II complexes, whereas square planar geometry assigned for Pd(II and Pt(II. In vitro the ligand and its metal complexes were evaluated against plant pathogenic fungi (Fusarium odum, Aspergillus niger and Rhizoctonia bataticola and some compounds found to be more active as commercially available fungicide like Chlorothalonil.

75 FR 18572 - Supplemental Environmental Impact Statement for Sequoyah Nuclear Plant Units 1 and 2 License...

Science.gov (United States)

2010-04-12

... TENNESSEE VALLEY AUTHORITY Supplemental Environmental Impact Statement for Sequoyah Nuclear Plant... National Environmental Policy Act. TVA will prepare a supplemental environmental impact statement (SEIS) to update information in the 1974 Final Environmental Statement for Sequoyah Nuclear Plant Units 1 and 2...

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-03-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole third quarter of 1991. Longer interruptions in electricity generation were caused by the annual maintenances of the Loviisa plant units. The load factor average was 81.7 %. In a test conducted during the annual maintenance outage of Loviisa 1 it was detected that the check valve of the discharge line of one pressurized emergency make-up tank did not open sufficiently at the tank's hydrostatic pressure. In connection with a 1988 modification, a too tightly dimensioned bearing had been mounted on the valve's axle rod and the valve had not been duly tested after the operation. The event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale). Occupational radiation doses and releases of radioactive material off-site were below authorised limits in this quarter. Only small amounts of radioactive materials originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

Unit for wind power plants and water power. Aggregat fuer Windkraftanlagen und Wasserkraft

Energy Technology Data Exchange (ETDEWEB)

Armonies, H.; Armonies, G.

1983-01-13

The invention concerns the manufacture and process of kinetic thermal units for wind power plants and water power. It is characterized by the fact that the supporting frame of the unit is made so that it carries the unit shaft bearing and also a fixed flange for a hollow body, pump part, unit shaft pushback device and thermal insulation. The unit shaft running in bearings is made so that it can rotate in the two bearings or a double bearing and can also slide between 2 flanges on the unit shaft in the longitudinal direction of the bearings. The end of the unit shaft projecting beyond the supporting frame is made so that the wind blades, rotors or water turbines can be connected to it by flanges. The rotor shaft can be pressed against a hollow body carrying a liquid by a friction disc. A heat resistant liquid pump is also situated on the supporting frame. It is driven by the unit shaft. (HWJ).

Determination of technical and economic parameters of an ionic transport membrane air separation unit working in a supercritical power plant

Directory of Open Access Journals (Sweden)

Kotowicz Janusz

2016-09-01

Full Text Available In this paper an air separation unit was analyzed. The unit consisted of: an ionic transport membrane contained in a four-end type module, an air compressor, an expander fed by gas that remains after oxygen separation and heat exchangers which heat the air and recirculated flue gas to the membrane operating temperature (850 °C. The air separation unit works in a power plant with electrical power equal to 600 MW. This power plant additionally consists of: an oxy-type pulverized-fuel boiler, a steam turbine unit and a carbon dioxide capture unit. Life steam parameters are 30 MPa/650 °C and reheated steam parameters are 6 MPa/670 °C. The listed units were analyzed. For constant electrical power of the power plant technical parameters of the air separation unit for two oxygen recovery rate (65% and 95% were determined. One of such parameters is ionic membrane surface area. In this paper the formulated equation is presented. The remaining technical parameters of the air separation unit are, among others: heat exchange surface area, power of the air compressor, power of the expander and auxiliary power. Using the listed quantities, the economic parameters, such as costs of air separation unit and of individual components were determined. These quantities allowed to determine investment costs of construction of the air separation unit. In addition, they were compared with investment costs for the entire oxy-type power plant.

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-05-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole fourth quarter of 1991. The load factor average was 94.7 % (the whole year 90.9 %). All the events in the last annual quarter, which are classified on the International Nuclear Event Scale, were below scale/level 0. Also the events which occurred in the other quarters of the year 1991 were rated at the scale's lowest levels. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure originating in nuclear power plants were detected in the samples collected in the vicinity of the nuclear power plants

78 FR 14361 - In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units 1 and...

Science.gov (United States)

2013-03-05

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0310; Docket Nos. 50-445 and 50-446; License Nos. NPF-87 and NPF-89] In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units... Nuclear Power Plant, Units 1 and 2 (CPNPP), and its Independent Spent Fuel Storage Installation Facility...

Integrated Level 3 risk assessment for the LaSalle Unit 2 nuclear power plant

International Nuclear Information System (INIS)

Payne, A.C. Jr.; Brown, T.D.; Miller, L.A.

1991-01-01

An integrated Level 3 probabilistic risk assessment (PRA) was performed on the LaSalle County Station nuclear power plant using state-of-the-art PRA analysis techniques. The objective of this study was to provide an estimate of the risk to the offsite population during full power operation of the plant and to include a characterization of the uncertainties in the calculated risk values. Uncertainties were included in the accident frequency analysis, accident progression analysis, and the source term analysis. Only weather uncertainties were included in the consequence analysis. In this paper selected results from the accident frequency, accident progression, source term, consequence, and integrated risk analyses are discussed and the methods used to perform a fully integrated Level 3 PRA are examined. LaSalle County Station is a two-unit nuclear power plant located 55 miles southwest of Chicago, Illinois. Each unit utilizes a Mark 2 containment to house a General Electric 3323 MWt BWR-5 reactor. This PRA, which was performed on Unit 2, included internal as well as external events. External events that were propagated through the risk analysis included earthquakes, fires, and floods. The internal event accident scenarios included transients, transient-induced LOCAs (inadvertently stuck open relief valves), anticipated transients without scram, and loss of coolant accidents

Thermodynamic and exergoeconomic analysis of a cement plant: Part II – Application

International Nuclear Information System (INIS)

Atmaca, Adem; Yumrutaş, Recep

2014-01-01

Highlights: • The overall energy and exergy efficiencies of the plant is found to be 59.37% and 38.99% respectively. • Performance assessment of a cement plant indicates that the calcination process involves the highest portion of energy losses. • The specific exergetic cost cement produced by the cement plant is calculated to be 180.5 USD/GJ. • The specific cement manufacturing cost is found to be 41.84 USD/ton. - Abstract: This paper is Part 2 of the study on the thermodynamic and exergoeconomic analysis of a cement plant. In Part 1, thermodynamic and exergoeconomic formulations and procedure for such a comprehensive analysis are provided while this paper provides an application of the developed formulation that considers an actual cement plant located in Gaziantep, Turkey. The overall energy and exergy efficiencies of the plant is found to be 59.37% and 38.99% respectively. The exergy destructions, exergetic cost allocations, and various exergoeconomic performance parameters are determined by using the exergoeconomic analysis based on specific exergy costing method (SPECO) for the entire plant and its components. The specific unit exergetic cost of the farine, clinker and cement produced by the cement plant are calculated to be 43.77 USD/GJ, 133.72 USD/GJ and 180.5 USD/GJ respectively. The specific manufacturing costs of farine, clinker and cement are found to be 3.8 USD/ton, 33.11 USD/ton and 41.84 USD/ton respectively

Flora of IGCAR campus and PFBR site: II plant diversity analysis

International Nuclear Information System (INIS)

Gajendiran, N.; Ragupathy, S.

2003-09-01

This report highlights the level of plant diversity that prevails in IGCAR and PFBR sites. The stress tolerant sandy-shore flora of natural vegetation adorns the Campus. It is bewitchingly blended with horticultural design and sets the backdrop of the nuclear industries- MAPS I and II and the incumbent PFBR. The floristic analysis points out the genetic richness of the campus (over 650 plant species in a narrow strip of ∼2500 acres), which can also serve as genetic reserve for coastal flora. Based on the study, a digitized inventory of plant resources of Kalpakkam is now made available. Taxonomy, distribution, vernacular name, uses, produces, bio-chemical component, ethnobotany, photograph are featured in the database. The survey highlights the potential of mangroves as bio-fence protecting against cyclone and sand and salt laden wind erosion. Such information may also be useful to understand the flora of east coast, in general. Biodiversity information gains importance for its use in caring the ecosystem and for its wise management at every micro-level down to the back yard of individual institution, which is the need of the hour. The sustainable use and preserving the biological resources maximize the net long-term benefits to mankind. (author)

Cleaning device for steam units in a nuclear power plant

International Nuclear Information System (INIS)

Sasamuro, Takemi.

1978-01-01

Purpose: To prevent radioactive contamination upon dismantling and inspection of steam units such as a turbine to a building containing such units and the peripheral area. Constitution: A steam generator indirectly heated by steam supplied from steam generating source in a separate system containing no radioactivity is provided to produce cleaning steam. A cleaning steam pipe is connected by way of a stop valve between separation valve of a nuclear power plant steam pipe and a high pressure turbine. Upon cleaning, the separation valve is closed, and steam supplied from the cleaning steam pipe is flown into a condenser. The water thus condensated is returned by way of a feed water heater and a condenser to a water storage tank. (Nakamura, S.)

Optimal replacement and inspection periods of safety and control boards in Wolsung nuclear power plant unit 1

International Nuclear Information System (INIS)

Mok, Jin Il

1993-02-01

In nuclear power plants, the safety and control systems are important for operating and maintaining safety of nuclear power plants. Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Since the start of first commercial operation of Kori nuclear power plant (NPP) unit 1, the trips caused by instrument and control systems account for 28% of total trips of NPPs in Korea. Even a single trip of a nuclear power plant causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this work we investigated the optimal replacement periods of the digital control computer's (DCC) and the programmable digital comparator's (PDC) electronic circuit boards of Wolsung nuclear power plant Unit 1. We first derived mathematical models which calculate optimal replacement periods for electronic circuit boards of digital control computer (DCC) and for those of the programmable digital comparator (PDC) in Wolsung NPP unit 1. And we analytically obtained the optimal replacement periods of electronic circuit boards by using these models. We compared these periods with the replacement periods currently used at Wolsung NPP Unit. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained for the electronic circuit boards of DCC and those used in the field shown small difference : the optimal replacement periods analytically obtained for the electronic circuit boards of PDC are shorter than those used in the field in general. The engineered safeguards of Wolsung nuclear power plant unit 1 contains redundant systems of 2-out-of-3 logic which are not operating under normal conditions but they are called

Simulaton of the Avedøreværket Unit 1 Cogeneration Plant with DNA

DEFF Research Database (Denmark)

Elmegaard, Brian; Houbak, Niels

2003-01-01

The simulator contest proposed for the ECOS 2003 conference has been solved using the DNA energy system simulator. The contest concerns the steam process of the Avedøreværket Unit 1 (AVV1) power plant. The plant is a 250 MWCHP plant with a maximum district heat production of 330 MJ/s. The plant has...... a net electric efficiency of 42% and a maximum energy utilization of 92%. In this paper it is demonstrated, that the DNA model of AVV1 can calculate the whole flow sheet balance at any load point, i.e., any possible combination of power production and district heat production. The paper also contains...

Contribution of Anticipated Transients Without Scram (ATWS) to core melt at United States nuclear power plants

International Nuclear Information System (INIS)

Giachetti, R.T.

1989-09-01

This report looks at WASH-1400 and several other Probabilistic Risk Assessments (PRAs) and Probabilistic Safety Studies (PSSs) to determine the contribution of Anticipated Transients Without Scram (ATWS) events to the total core melt probability at eight nuclear power plants in the United States. After considering each plant individually, the results are compared from plant to plant to see if any generic conclusions regarding ATWS, or core melt in general, can be made. 8 refs., 34 tabs

Application of Digital Technology for the Plant Protection System in Ulchin Nuclear Power Plant Units 5 and 6

International Nuclear Information System (INIS)

Deucksoo, Lee; Insik, Kim

2006-01-01

Since the completion of construction of Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3 and 4), the first units of the OPR (Optimized Power Reactor) series, various advanced design features have been incorporated to the following OPRs. The Ulchin Nuclear Power Plant Units 5 and 6(UCN 5 and 6) which started commercial operation in Korea from 2004 and 2005 respectively, are designed to provide improvements in safety, reliability and costs by applying both advanced proven technology and experiences gained from the construction and operation of the previous OPRs. Among those improvements, the digital plant protection system (DPPS) and the digital engineered safety feature actuation system (DESFAS) are the key elements to the UCN 5 and 6 designs. The DPPS and DESFAS utilizing the digital computer technology offer a solution to the obsolescence problem of analog system. These features also provide the potential for additional benefits such as ease of maintenance, increased performance, reduction of internal and external cross channel wiring, improvement of the surveillance testability and flexibility of control logic programming change. During the initial design stage, the Korean regulatory body had evaluated these design concepts intensively and concluded it to be acceptable for the safety point of view. Also, in-depth review on the detailed design and the special evaluation/audit for the software design process has been performed to secure the quality of the software. As a result, every issue raised during licensing review has been clarified and the operating licenses for the UCN 5 and 6 were issued in October, 2003 and October, 2004 respectively, by the government. In this paper, design characteristics of the UCN 5 and 6 are introduced, and advanced design features and implementation process are presented focused on the DPPS/DESFAS with some benefit analysis results. (authors)

The trip status and the reduction countermeasure in Kori nuclear power plant unit 1 and 2

International Nuclear Information System (INIS)

Kim, Jung-Soo

1991-01-01

Nuclear power account for 36% of Korea's total electric capacity and provided over 50% of the net electric power supply by June 1991. These plants supply US with the cheapest and most stable electric supply available. However each units capacity is very large and a plant trip due to failure of a component or a human error has a great influence on the nations electric power supply and drastically decreases the reserve margin. This report will analyze the trip causes and measure the trip frequency from the first commercial operation of Kori unit 1 and 2 to the end of June 1991, reflect to the plant operation, management and facility modification, etc. This will minimize the number of trips or urgent power reductions and thus contribute to an increase in plant capacity factor and safety, and stabilize the electric power demand and supply. The safety and the economy of nuclear power plant have to be secured and raised respectably by increasing the capacity factor. Since the prevention of trips plays an important role in the plant safety and economy, we have to do our best to prevent the unexpected trip

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-03-01

In the Quarterly Reports on the operation of the Finnish nuclear power plants such incidents and observations are described relating to nuclear and radiation safety which the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, considers safety-related. During the third quarter of 1989 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 39.0% of the total Finnish electricity production in this quarter. The load factor average of the nuclear power plant units was 78.9%. At Loviisa 1, two holes were found in the feedwater distributor of one steam generator. Corresponding wall thinning corrosion was also detected in the walls of two other distributors. The holes were found on the feedwater distributor upper surface in the joint of the secondary circuit feedwater pipe. One hole was about 20 mm x 50 mm in size and the other was a pit hole ca 5 mm in diameter. Metal power had entered the primary circuit at TVO I. This was observed during a post-scram plant start-up. Several control rod drive units had become jammed so tight that control rod withdrawal failed. Metal powder did not hamper reactor scram under the prevailing circumstances because the drive units are prone to jamming only after a control rod is almost fully inserted and because the forces which insert a control rod by various means (electrical, hydraulic) are 6-8 fold compared with the withdrawing force

Energy audit and conservation opportunities for pyroprocessing unit of a typical dry process cement plant

International Nuclear Information System (INIS)

Kabir, G.; Abubakar, A.I.; El-Nafaty, U.A.

2010-01-01

Cement production process has been highly energy and cost intensive. The cement plant requires 8784 h per year of the total operating hours to produce 640,809 tonnes of clinker. To achieve effective and efficient energy management scheme, thermal energy audit analysis was employed on the pyroprocessing unit of the cement plant. Fuel combustion generates the bulk of the thermal energy for the process, amounting to 95.48% (4164.02 kJ/kg cl ) of the total thermal energy input. Thermal efficiency of the unit stands at 41%, below 50-54% achieved in modern plants. The exhaust gases and kiln shell heat energy losses are in significant quantity, amounting to 27.9% and 11.97% of the total heat input respectively. To enhance the energy performance of the unit, heat losses conservation systems are considered. Waste heat recovery steam generator (WHRSG) and Secondary kiln shell were studied. Power and thermal energy savings of 42.88 MWh/year and 5.30 MW can be achieved respectively. Financial benefits for use of the conservation methods are substantial. Environmental benefit of 14.10% reduction in Greenhouse gases (GHG) emissions could be achieved.

Energy audit and conservation opportunities for pyroprocessing unit of a typical dry process cement plant

Energy Technology Data Exchange (ETDEWEB)

Kabir, G.; Abubakar, A.I.; El-Nafaty, U.A. [Chemical Engineering Programme, Abubakar Tafawa Balewa University, P. M. B. 0248, Bauchi (Nigeria)

2010-03-15

Cement production process has been highly energy and cost intensive. The cement plant requires 8784 h per year of the total operating hours to produce 640,809 tonnes of clinker. To achieve effective and efficient energy management scheme, thermal energy audit analysis was employed on the pyroprocessing unit of the cement plant. Fuel combustion generates the bulk of the thermal energy for the process, amounting to 95.48% (4164.02 kJ/kg{sub cl}) of the total thermal energy input. Thermal efficiency of the unit stands at 41%, below 50-54% achieved in modern plants. The exhaust gases and kiln shell heat energy losses are in significant quantity, amounting to 27.9% and 11.97% of the total heat input respectively. To enhance the energy performance of the unit, heat losses conservation systems are considered. Waste heat recovery steam generator (WHRSG) and Secondary kiln shell were studied. Power and thermal energy savings of 42.88 MWh/year and 5.30 MW can be achieved respectively. Financial benefits for use of the conservation methods are substantial. Environmental benefit of 14.10% reduction in Greenhouse gases (GHG) emissions could be achieved. (author)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-12-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations related to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing plant modifications and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and their load factors are also given. At the Loviisa 1 plant unit one of two specially-backed AC busbars was lost during the second quarter of 1993. A ca. 30 minute voltage break caused malfunctions in the plant unit's electrical equipment and rendered inoperable certain components important to safety. The event is rated on the International Nuclear Event Scale (INES) at level 1. In inspections carried out at TVO II during the annual maintenance outage, the number of cracks detected in control rod structural material was higher than usual. When cracks occur, part of boron carbide, the power regulating medium in control rods, may wash into the reactor water and control rod shutdown capability may be impaired. The event is rated on the INES at level 1. Other events in the second quarter of 1993 had no bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

Start-up and commercial operation of the Laguna Verde power plants, unit 1

International Nuclear Information System (INIS)

Torres R, J.F.

1991-01-01

The main features of the unit 1 of the Laguna Verde Power Plant is presented as well as the phases of the start-up process. The process includes various steps and tests up to start the commercial operation. (author)

Immigrant phytophagous insects on woody plants in the United States and Canada: an annotated list.

Science.gov (United States)

William J. Mattson; P. Niemela; I. Millers; Y. Inguanzo

1994-01-01

Nearly 2,000 foreign plants and 2,000 foreign insect species have become naturalized in North America during the past 500 years. This publication documents those immigrant phytophagous insect species which have become established on woody plants or their products in the continental United States and Canada. Of these 368 immigrant insects, 72% came from Europe.

Participatory plant breeding and organic agriculture: A synergistic model for organic variety development in the United States

Directory of Open Access Journals (Sweden)

Adrienne C. Shelton

2016-12-01

Full Text Available Abstract Organic farmers require improved varieties that have been adapted to their unique soils, nutrient inputs, management practices, and pest pressures. One way to develop adapted varieties is to situate breeding programs in the environment of intended use, such as directly on organic farms, and in collaboration with organic farmers. This model is a form of participatory plant breeding, and was originally created in order to meet the needs of under-served, small-scale farmers in developing countries. A robust body of literature supports the quantitative genetic selection theory of participatory plant breeding, and helps to explain its increasing prevalence among organic breeding projects in the United States. The history of the organic farming movement in the United States highlights the cultural relevance of engaging organic farmers in the breeding process, complementing the biological rationale for participatory plant breeding. In addition, limited private investment in organic plant breeding encourages the involvement of plant breeders at public institutions. This paper synthesizes the biological, cultural, and economic justifications for utilizing participatory plant breeding as an appropriate methodology for organic cultivar development.

Better prognostic marker in ICU - APACHE II, SOFA or SAP II!

Science.gov (United States)

Naqvi, Iftikhar Haider; Mahmood, Khalid; Ziaullaha, Syed; Kashif, Syed Mohammad; Sharif, Asim

2016-01-01

This study was designed to determine the comparative efficacy of different scoring system in assessing the prognosis of critically ill patients. This was a retrospective study conducted in medical intensive care unit (MICU) and high dependency unit (HDU) Medical Unit III, Civil Hospital, from April 2012 to August 2012. All patients over age 16 years old who have fulfilled the criteria for MICU admission were included. Predictive mortality of APACHE II, SAP II and SOFA were calculated. Calibration and discrimination were used for validity of each scoring model. A total of 96 patients with equal gender distribution were enrolled. The average APACHE II score in non-survivors (27.97+8.53) was higher than survivors (15.82+8.79) with statistically significant p value (discrimination power than SAP II and SOFA.

Human resource development for the new nuclear power plant unit in Armenia

International Nuclear Information System (INIS)

Gevorgyan, A.; Galstyan, A.; Donovan, M.

2008-01-01

This paper presents a discussion of a study to define the programs for development of the human resource infrastructure needed for a new nuclear power plant unit in the Republic of Armenia. While Armenia has a workforce experienced in operation and regulation of a nuclear power plant (NPP), a significant portion of the current Armenia Nuclear Power Plant (ANPP) workforce is approaching retirement age and will not be available for the new plant. The Government of Armenia is performing a human resource infrastructure study in cooperation with the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), sponsored by the JAEA. The study of Human Resource Development for Armenia uses the INPRO methodology for assessment of human resources. The results of this study will provide the basis for decisions on human resource development programs for nuclear power in Armenia and provide a model for countries with the limited resources that are working to develop nuclear energy in the future. (authors)

The steam generator repair project of the Donald C. Cook Nuclear Plant, Unit 2

International Nuclear Information System (INIS)

White, J.D.

1993-01-01

Donald C. Cook Nuclear Plant Unit 2 is part of a two unit nuclear complex located in southwestern Michigan and owned and operated by the Indiana Michigan Power Company. The Cook Nuclear Plant is a pressurized water reactor (PWR) plant with four Westinghouse Series 51 steam generators housed in an ice condenser containment. This paper describes the program undertaken by Indiana Michigan Power and the American Electric Power Service Corporation (AEPSC) to repair the Unit 2 steam generators. (Both Indiana Michigan Power and AEPSC arc subsidiaries of American Electric Power Company, Incorporated (AEP). AEPSC provides management and technical support services to Indiana Michigan Power and the other AEP operating companies.) Eddy current examinations, in a series of refueling and forced outages between November 1983 and July 1986 resulted in 763 (5.6%) plugged tubes. In order to maintain adequate reactor core cooling, a limit of 10% is placed on the allowable percentage of steam generator tubes that can be removed from service by plugging. Additionally, sections of tubes were removed for metallurgical analysis and confirmed that the degradation was due to intergranular stress corrosion cracking. In developing the decision on how to repair the steam generators, four alternative actions were considered for addressing these problems: retubing in place, sleeving, operating at 80% reactor power to lower temperature and thus reduce the rate of corrosion, replacing steam generator lower assemblies

Integrated plant safety assessment, Systematic Evaluation Program: Dresden Nuclear Power Station, Unit 2 (Docket No. 50-237)

International Nuclear Information System (INIS)

1989-10-01

The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0823), under the scope of the Systematic Evaluation Program (SEP), for the Commonwealth Edison Company (CECo) Dresden Nuclear Power Station, Unit 2 located in Grundy County, Illinois. The NRC initiated the SEP to provide the framework for reviewing the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed by means of the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations subsequent to issuing the final IPSAR for Dresden Unit 2. The review was provided for (1) an assessment of the significance of differences between current technical positions on selected issues and those that existed when Dresden Unit 2 was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. The final IPSAR and this supplement forms part of the bases for considering the conversion of the existing provisional operating license to a full-term operating license. 83 refs., 9 tabs

A study on the optimal replacement periods of digital control computer's components of Wolsung nuclear power plant unit 1

International Nuclear Information System (INIS)

Mok, Jin Il; Seong, Poong Hyun

1993-01-01

Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Even a trip of a single nuclear power plant (NPP) causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this paper we investigated the optimal replacement periods of the control computer's components of Wolsung nuclear power plant Unit 1. We first derived mathematical models of optimal replacement periods to the digital control computer's components of Wolsung NPP Unit 1 and calculated the optimal replacement periods analytically. We compared the periods with the replacement periods currently used at Wolsung NPP Unit 1. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained and those used in the field show a little difference. (Author)

RCRA closure of eight land-based units at the Y-12 plant

International Nuclear Information System (INIS)

Stone, J.E.; Welch, S.H.

1988-01-01

Eight land-based hazardous waste management units at the Oak Ridge Y-12 Plant are being closed under an integrated multi-year program. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. These units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. The closure of these sites will be funded by a new Department of Energy budget category, the Environmental Restoration Budget Category (ERBC), which is intended to provide greater flexibility in the response to closure and remedial activities. A major project, Closure and Post-Closure Activities (CAPCA), has been identified for ERBC funding to close and remediate the land units in accordance with RCRA requirements. Establishing the scope of this program has required the development of risk assessments and the preparation of an integrated schedule

Evolutionary Trails of Plant Group II Pyridoxal Phosphate-Dependent Decarboxylase Genes.

Science.gov (United States)

Kumar, Rahul

2016-01-01

Type II pyridoxal phosphate-dependent decarboxylase (PLP_deC) enzymes play important metabolic roles during nitrogen metabolism. Recent evolutionary profiling of these genes revealed a sharp expansion of histidine decarboxylase genes in the members of Solanaceae family. In spite of the high sequence homology shared by PLP_deC orthologs, these enzymes display remarkable differences in their substrate specificities. Currently, limited information is available on the gene repertoires and substrate specificities of PLP_deCs which renders their precise annotation challenging and offers technical challenges in the immediate identification and biochemical characterization of their full gene complements in plants. Herein, we explored their evolutionary trails in a comprehensive manner by taking advantage of high-throughput data accessibility and computational approaches. We discussed the premise that has enabled an improved reconstruction of their evolutionary lineage and evaluated the factors offering constraints in their rapid functional characterization, till date. We envisage that the synthesized information herein would act as a catalyst for the rapid exploration of their biochemical specificity and physiological roles in more plant species.

76 FR 77022 - In the Matter of Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2...

Science.gov (United States)

2011-12-09

... and 72-3] In the Matter of Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2, H. B. Robinson Steam Electric Plant, Unit 2, Independent Spent Fuel Storage Installation; Order Approving Indirect Transfer of Control of Licenses I. Carolina Power & Light Company (CP&L, the licensee) is...

Analysis of factors influencing the impingement of threadfin shad (Dorosoma pretenense) at power plants in the southeastern United States

International Nuclear Information System (INIS)

Loar, J.M.; Griffith, J.S.; Kumar, K.D.

1977-01-01

Data on intake design and location, plant operating procedures, water quality, numbers of fish impinged, and sampling procedures were analyzed for 27 fossil-fueled and 5 nuclear power plants located on inland waters in the southeastern United States. Small (less than 9 cm) clupeids, especially threadfin shad (Dorosoma pretenense), comprised the majority of the fish impinged at these facilities. The parameter that was most strongly associated with shad impingement was water temperature. Maximum impingement rates occurred during the winter when intake temperatures dropped below 10 0 C. Analyses of differences in impingement rates between plants failed to adequately demonstrate that the magnitude of impingement at a particular plant was the result of any site-specific characteristics associated with intake design or location. High approach velocities at the traveling screens did not necessarily result in high levels of impingement. Results obtained from inter-unit comparisons at several plants indicate that unit and screen differences do exist, but it is unclear from existing data whether or not such inter-unit differences determine the magnitude of impingement losses or merely affect the distribution of impinged fish at a given intake structure. Recommendations for monitoring fish impingement include the identification of impinged fish by species, collection of data on water temperatures and various plant operational parameters, periodic analyses of localized velocity regimes near the intake, and frequent estimates of the relative density of the fish population in the vicinity of the intake

Planning for decommissioning of Ignalina Nuclear Power Plant Unit-1

International Nuclear Information System (INIS)

Poskas, P.; Poskas, R.; Zujus, R.

2002-01-01

In accordance to Ignalina NPP Unit 1 Closure Law, the Government of Lithuania approved the Ignalina NPP Unit 1 Decommissioning Program until 2005. For enforcement of this program, the plan of measures for implementation of the program was prepared and approved by the Minister of Economy. The plan consists of two parts, namely technical- environmental and social-economic. Technical-environmental measures are mostly oriented to the safe management of spent nuclear fuel and operational radioactive waste stored at the plant and preparation of licensing documents for Unit 1 decommissioning. Social-economic measures are oriented to mitigate the negative social and economic impact on Lithuania, inhabitants of the region, and, particularly, on the staff of Ignalina NPP by means of creating favorable conditions for a balanced social and economic development of the region. In this paper analysis of planned radioactive waste management technologies, licensing documents for decommissioning, other technical-environmental and also social-economic measures is presented. Specific conditions in Lithuania important for defining the decommissioning strategy are highlighted. (author)

Global Thermal Power Plants Database: Unit-Based CO2, SO2, NOX and PM2.5 Emissions in 2010

Science.gov (United States)

Tong, D.; Qiang, Z.; Davis, S. J.

2016-12-01

There are more than 30,000 thermal power plants now operating worldwide, reflecting a tremendously diverse infrastructure that includes units burning oil, natural gas, coal and biomass and ranging in capacity from 1GW. Although the electricity generated by this infrastructure is vital to economic activities across the world, it also produces more CO2 and air pollution emissions than any other industry sector. Here we present a new database of global thermal power-generating units and their emissions as of 2010, GPED (Global Power Emissions Database), including the detailed unit information of installed capacity, operation year, geographic location, fuel type and control measures for more than 70000 units. In this study, we have compiled, combined, and harmonized the available underlying data related to thermal power-generating units (e.g. eGRID of USA, CPED of China and published Indian power plants database), and then analyzed the generating capacity, capacity factor, fuel type, age, location, and installed pollution-control technology in order to determine those units with disproportionately high levels of emissions. In total, this work is of great importance for improving spatial distribution of global thermal power plants emissions and exploring their environmental impacts at global scale.

HYLIFE-II inertial fusion energy power plant design

International Nuclear Information System (INIS)

Moir, R.W.

1992-01-01

The HYLIFE-II inertial fusion power plant design study uses a liquid fall, in the form of jets, to protect the first structural wall from neutron damage, x rays, and blast to provide a 30-y lifetime. HYLIFE-I used liquid lithium. HYLIFE-II avoids the fire hazard of lithium by using a molten salt composed of fluorine, lithium, and beryllium (Li 2 BeF 4 ) called Flibe. Access for heavy-ion beams is provided. Calculations for assumed heavy-ion beam performance show a nominal gain of 70 at 5 MJ producing 350 MJ, about 5.2 times less yield than the 1.8 Gj from a driver energy of 4.5 MJ with gain of 400 for HYLIFE-I. The nominal 1 GWe of power can be maintained by increasing the repetition rate by a factor of about 5.2, from 1.5 to 8Hz. A higher repetition rate requires faster re-establishment of the jets after a shot, which can be accomplished in part by decreasing the jet fall height and increasing the jet flow velocity. In addition, although not adequately considered for HYLIFE-I, there is liquid splash that must be forcibly cleared because gravity is too slow, at higher repetition rates than 1 Hz. Splash removal is accomplished in the central region by oscillating jet flows. The cost of electricity is estimated to be 0.09 $/kW·h in constant 1988 dollars, about twice that of future coal and light water reactor nuclear power. The driver beam cost is about one-half the total cost, that is, a zero cost driver would give a calculated cost of electricity of 0.045 $/kWh

HYLIFE-II inertial fusion energy power plant design

International Nuclear Information System (INIS)

Moir, R.W.

1992-01-01

The HYLIFE-II inertial fusion power plant design study uses a liquid fall, in the form of jets, to protect the first structural wall from neutron damage, x rays, and blast to provide a 30-y lifetime. HYLIFE-I used liquid lithium. HYLIFE-II avoids the fire hazard of lithium by using a molten salt composed of fluorine, lithium, and beryllium (Li 2 BeF 4 ) called Flibe. Access for heavy-ion beams is provided. Calculations for assumed heavy-ion beam performance show a nominal gain of 70 at 5 MJ producing 350 MJ, about 5.2 times less yield than the 1.8 GJ from a driver energy of 4.5 MJ with gain of 400 for HYLIFE-I. The nominal 1 GWe of power can be maintained by increasing the repetition rate by a factor of about 5.2, from 1.5 to 8 Hz. A higher repetition rate requires faster re-establishment of the jets after a shot, which can be accomplished in part by decreasing the jet fall height and increasing the jet flow velocity. In addition, although not adequately considered for HYLIFE-I, there is liquid splash that must be forcibly cleared because gravity is too slow, at higher repetition rates than 1 Hz. Splash removal is accomplished in the central region by oscillating jet flows. The cost of electricity is estimated to be 0.09 $/kW·h in constant 1988 dollars, about twice that of future coal and light water reactor nuclear power. The driver beam cost is about one-half the total cost, that is, a zero cost driver would give a calculated cost of electricity of 0.045 $/kWh

Auxiliary feedwater system risk-based inspection guide for the Beaver Valley, Units 1 and 2 nuclear power plants

International Nuclear Information System (INIS)

Lloyd, R.C.; Vehec, T.A.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Rossbach, L.W.; Sena, P.P. III

1993-02-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Beaver Valley Units 1 and 2 were selected as two of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at Beaver Valley Units 1 and 2

A symbiosis-dedicated SYNTAXIN OF PLANTS 13II isoform controls the formation of a stable host-microbe interface in symbiosis.

Science.gov (United States)

Huisman, Rik; Hontelez, Jan; Mysore, Kirankumar S; Wen, Jiangqi; Bisseling, Ton; Limpens, Erik

2016-09-01

Arbuscular mycorrhizal (AM) fungi and rhizobium bacteria are accommodated in specialized membrane compartments that form a host-microbe interface. To better understand how these interfaces are made, we studied the regulation of exocytosis during interface formation. We used a phylogenetic approach to identify target soluble N-ethylmaleimide-sensitive factor-attachment protein receptors (t-SNAREs) that are dedicated to symbiosis and used cell-specific expression analysis together with protein localization to identify t-SNAREs that are present on the host-microbe interface in Medicago truncatula. We investigated the role of these t-SNAREs during the formation of a host-microbe interface. We showed that multiple syntaxins are present on the peri-arbuscular membrane. From these, we identified SYNTAXIN OF PLANTS 13II (SYP13II) as a t-SNARE that is essential for the formation of a stable symbiotic interface in both AM and rhizobium symbiosis. In most dicot plants, the SYP13II transcript is alternatively spliced, resulting in two isoforms, SYP13IIα and SYP13IIβ. These splice-forms differentially mark functional and degrading arbuscule branches. Our results show that vesicle traffic to the symbiotic interface is specialized and required for its maintenance. Alternative splicing of SYP13II allows plants to replace a t-SNARE involved in traffic to the plasma membrane with a t-SNARE that is more stringent in its localization to functional arbuscules. © 2016 The Authors. New Phytologist © 2016 New Phytologist Trust.

Environmental impact assessments of a fifth nuclear power plant unit in Finland

International Nuclear Information System (INIS)

Aurela, Jorma; Koivisto, Katarina

2000-01-01

This paper presents the results of president questionnaires and media monitoring of press cuttings concerned with siting of the new fifth in a row Finnish NPP. Two years ago both Fortum Power and Heat Oy and Teollisuuden Voima Oy (TVO) launched their Environmental impact assessment (EIA) procedures of a new nuclear power unit in Finland. The EIA procedures were launched to investigate the environmental impacts of a fifth nuclear power plant which possibly will be built in Loviisa or at Olkiluoto. In Finland there are four operating NPP units, two in Loviisa (Fortum) and two in Eurajoki, Olkiluoto (TVO). In the EIA procedure citizens and various associations and authorities have an opportunity to express their views on the matters related to the project. The Ministry of Trade and Industry (MTI) as the coordination authority arranges the organisation of the EIA hearings and the collection of statements and opinions. The EIA procedure in Finland takes place in two stages. The first stage i.e. the EIA programme describes the project and presents the plan on how the environmental effects are investigated and assessed. In the second stage the actual assessment of the environmental effects of the project will be submitted. Both Fortum and Teollisuuden Voima Oy (TVO) launched in spring 1998 their EIA procedures. The main alternatives are the Loviisa 3 project includes two plant type alternatives. The size of the plant is between 1000 and 1700 MWe, and the extension project of the Olkiluoto NPP to build a NPP unit of about 1000-1500 MWe at Olkiluoto. The EIA reports were submitted to the MTI in August 1999 and after that they were on display for two months for opinions and statements

Communication and surrounding of Asco and Vandellos II nuclear power plants; La comunicacion y el entorno de las centrales de Asco y Vandellos II

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The Asco and Vandellos-II power plants have always been integrated into the regions where they are located, and they take an active part in the development of surrounding towns through quality employment provided by our facilities, social and cultural support and aid to development promoted by regional councils. Communication to media is a corporate priority defined in our strategic plant, to ensure openness, rigour and punctuality. We also attend to the visitors who want to learn more about our facilities in the visitor center, and we have agreements with agrarian institutions in the area so that students can de practical training in the farms we own for agricultural production. (Author)

Inventory of power plants in the United States as of January 1, 1996

International Nuclear Information System (INIS)

1996-12-01

The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1996. The publication also provides a 10-year outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress; Federal and State agencies; the electric utility industry; and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 as amended

Inventory of power plants in the United States as of January 1, 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1996. The publication also provides a 10-year outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress; Federal and State agencies; the electric utility industry; and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 as amended.

Development of a method to evaluate shared alternate AC power source effects in multi-unit nuclear power plants

International Nuclear Information System (INIS)

Jung, Woo Sik; Yang, Joon Eun

2003-07-01

In order to evaluate accurately a Station BlackOut (SBO) event frequency of a multi-unit nuclear power plant that has a shared Alternate AC (AAC) power source, an approach has been developed which accommodates the complex inter-unit behavior of the shared AAC power source under multi-unit Loss Of Offsite Power (LOOP) conditions. The approach is illustrated for two cases, 2 units and 4 units at a single site, and generalized for a multi-unit site. Furthermore, the SBO frequency of the first unit of the 2-unit site is quantified. The SBO frequency at a target unit of Probabilistic Safety Assessment (PSA) could be underestimated if the inter-unit dependency of the shared AAC power source is not properly modeled. The effect of the inter-unit behavior of the shared AAC power source on the SBO frequency is not negligible depending on the Common Cause Failure (CCF) characteristics among AC power sources. The methodology suggested in the present report is believed to be very useful in evaluating the SBO frequency and the core damage frequency resulting from the SBO event. This approach is also applicable to the probabilistic evaluation of the other shared systems in a multi-unit nuclear power plant

Kozloduy nuclear power plant. Units 1-4. Status of safety assessment activities. Rev. 2

International Nuclear Information System (INIS)

1999-01-01

This paper presents the results of the status of safety assessment activities carried out by the Kozloduy Nuclear Power Plant (KNPP) in order to evaluate the current status of the safety of its reactor units 1-4. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of Russian design developed according to the safety standards in force in USSR in late 60-s. Now a days 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short Tenn Program was implemented between the years 1991 and 1997 thanks of the strong safety commitment of NEK and KNPP staff and the broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level

Resource conversation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

1993-08-01

Volume II contains attachments for Module II and Module III. Attachments for Module II are: part A permit application; examples of acceptable documentation; Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program; inspection schedule and monitoring schedule; inspection log forms; personnel training course outlines; hazardous waste job position training requirements; contingency plan; closure plan; and procedures for establishing background for the underground units. One attachment, facility process information, is included for Module III. Remaining attachments for this module are in Volume III

Oxidation behavior analysis of cladding during severe accidents with combined codes for Qinshan Phase II Nuclear Power Plant

International Nuclear Information System (INIS)

Shi, Xingwei; Cao, Xinrong; Liu, Zhengzhi

2013-01-01

Highlights: • A new verified oxidation model of cladding has been added in Severe Accident Program (SAP). • A coupled analysis method utilizing RELAP5 and SAP codes has been developed and applied to analyze a SA caused by LBLOCA. • Analysis of cladding oxidation under a SA for Qinshan Phase II Nuclear Power Plant (QSP-II NPP) has been performed by SAP. • Estimation of the production of hydrogen has been achieved by coupled codes. - Abstract: Core behavior at a high temperature is extremely complicated during transition from Design Basic Accident (DBA) to the severe accident (SA) in Light Water Reactors (LWRs). The progression of core damage is strongly affected by the behavior of fuel cladding (oxidation, embrittlement and burst). A Severe Accident Program (SAP) is developed to simulate the process of fuel cladding oxidation, rupture and relocation of core debris based on the oxidation models of cladding, candling of melted material and mechanical slumping of core components. Relying on the thermal–hydraulic boundary parameters calculated by RELAP5 code, analysis of a SA caused by the large break loss-of-coolant accident (LBLOCA) without mitigating measures for Qinshan Phase II Nuclear Power Plant (QSP-II NPP) was performed by SAP for finding the key sequences of accidents, estimating the amount of hydrogen generation and oxidation behavior of the cladding

COMURHEX II, a 610 million euro investment to meet tomorrow's nuclear power needs

International Nuclear Information System (INIS)

2007-01-01

The worldwide development of nuclear power will lead to increasing demands for uranium. To meet its customers' growing requirements, AREVA has chosen to invest in COMURHEX II to renew and modernize its industrial conversion tool. An entirely new plant is to be built on the Tricastin site to the north of the existing COMURHEX plant. The plant, together with other large-scale investment projects such as the future Georges Besse II enrichment plant - also located on the Tricastin site - and the modernization of the FBFC fuel fabrication facilities in the south of France, will enable AREVA to strengthen its position as a long-standing and fully integrated player at the Front End of the nuclear fuel cycle. These major investments confirm the group's strong commitment to the global development of nuclear power. Converting uranium ore into uranium hexafluoride (UF 6 ) is a key stage before the enrichment and fabrication of nuclear fuel. AREVA is gearing up for market changes, increasing its uranium production from 15,000 tons per year to 21,000 tons per year to match market needs. Today the conversion units of the different industrial operators are showing their age. They will need replacing in the medium term to increase production capacity and keep abreast of the economic, regulatory and environmental conditions of tomorrow's market. Its euros 610 million investment in the Narbonne and Pierrelatte sites in southern France will make AREVA the first uranium converter to overhaul its industrial tool. Thus indicating the group's intention of remaining world leader in UF 6 conversion. The COMURHEX II project will involve the modernization and upgrading of our installations on the basis of tried-and-tested processes and techniques, while incorporating technological innovations that will improve the production performance, reinforce nuclear safety in the facilities, while further reducing the environmental impact of their activities. The first industrial production on the

Effect of Jigsaw II, Reading-Writing-Presentation, and Computer Animations on the Teaching of "Light" Unit

Science.gov (United States)

Koç, Yasemin; Yildiz, Emre; Çaliklar, Seyma; Simsek, Ümit

2016-01-01

The aim of this study is to determine the effect of Jigsaw II technique, reading-writing-presentation method, and computer animation on students' academic achievements, epistemological beliefs, attitudes towards science lesson, and the retention of knowledge in the "Light" unit covered in the 7th grade. The sample of the study consists…

Atucha II NPP full scope simulator modelling with the thermal hydraulic code TRACRT

International Nuclear Information System (INIS)

Alonso, Pablo Rey; Ruiz, Jose Antonio; Rivero, Norberto

2011-01-01

In February 2010 NA-SA (Nucleoelectrica Argentina S.A.) awarded Tecnatom the Atucha II full scope simulator project. NA-SA is a public company owner of the Argentinean nuclear power plants. Atucha II is due to enter in operation shortly. Atucha II NPP is a PHWR type plant cooled by the water of the Parana River and has the same design as the Atucha I unit, doubling its power capacity. Atucha II will produce 745 MWe utilizing heavy water as coolant and moderator, and natural uranium as fuel. A plant singular feature is the permanent core refueling. TRAC R T is the first real time thermal hydraulic six-equations code used in the training simulation industry for NSSS modeling. It is the result from adapting to real time the best estimate code TRACG. TRAC R T is based on first principle conservation equations for mass, energy and momentum for liquid and steam phases, with two phase flows under non homogeneous and non equilibrium conditions. At present, it has been successfully implemented in twelve full scope replica simulators in different training centers throughout the world. To ease the modeling task, TRAC R T includes a graphical pre-processing tool designed to optimize this process and alleviate the burden of entering alpha numerical data in an input file. (author)

Phase 2 Sampling Plan for Chestnut Ridge Operable Unit 2 (Filled Coal Ash Pond/Upper McCoy Branch) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1993-01-01

CDM Federal Programs Corporation (CDM Federal) was contracted by Energy Systems to prepare a Phase II Sampling Plan to describe the field investigation work necessary to address regulatory agency review comments on the Remedial Investigation of the Filled Coal Ash Pond (FCAP)/Upper McCoy Branch, Chestnut Ridge Operable Unit 2 at the Y-12 Plant, conducted by CH2M Hill in 1990. The scope and approach of the field investigation described in this plan specifically focus on deficiencies noted by the regulators in discussions at the comment resolution meeting of May 8, 1992, in Oak Ridge, Tennessee. This Phase II Sampling Plan includes a field sampling plan, a field and laboratory quality assurance project plan, a health and safety plan, a waste management plan, and appendixes providing an update to the applicable or relevant and appropriate requirements for this site and field and laboratory testing methods and procedures

Station blackout transient at the Browns Ferry Unit 1 Plant: a severe accident sequence analysis (SASA) program study

International Nuclear Information System (INIS)

Schultz, R.R.

1982-01-01

Operating plant transients are of great interest for many reasons, not the least of which is the potential for a mild transient to degenerate to a severe transient yielding core damage. Using the Browns Ferry (BF) Unit-1 plant as a basis of study, the station blackout sequence was investigated by the Severe Accident Sequence Analysis (SASA) Program in support of the Nuclear Regulatory Commission's Unresolved Safety Issue A-44: Station Blackout. A station blackout transient occurs when the plant's AC power from a comemrcial power grid is lost and cannot be restored by the diesel generators. Under normal operating conditions, f a loss of offsite power (LOSP) occurs [i.e., a complete severance of the BF plants from the Tennessee Valley Authority (TVA) power grid], the eight diesel generators at the three BF units would quickly start and power the emergency AC buses. Of the eight diesel generators, only six are needed to safely shut down all three units. Examination of BF-specific data show that LOSP frequency is low at Unit 1. The station blackout frequency is even lower (5.7 x 10 - 4 events per year) and hinges on whether the diesel generators start. The frequency of diesel generator failure is dictated in large measure by the emergency equipment cooling water (EECW) system that cools the diesel generators

Laboratory studies on enhancing the throughput of demineraliser units by proper selection of ion exchange resins

Energy Technology Data Exchange (ETDEWEB)

Rao, S V; Unny, V K.P.; Shetiya, R S [Reactor Services and Maintenance Division, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

In water treatment plants of nuclear reactors, type I strong base anion resins are extensively used in anion units along with strong acid cation resins in cation units for demineralisation of water. There is another kind of strong base anion resin called type II resin which is chemically slightly different from type I resin. Type II resins differ from the type I in that one of the methyl groups in the quaternary ammonium functional group of the latter, is replaced by an ethanol group. This results in lower basicity of the resin and hence, higher regeneration efficiency. However, the resin is not like a weak base resin in its properties since it is capable of removing silica from water, though not with the same efficiency as that of the type I strong base resin. Studies were carried out to compare the performance of presently used type I resins with that of type II resins supplied by local manufacturers to assess the suitability of the latter for use in the DM plants of Trombay reactors. This paper discusses the results of the studies. (author). 2 figs., 6 tabs.

Inventory of power plants in the United States as of January 1, 1997

International Nuclear Information System (INIS)

1997-12-01

The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1997. The publication also provides a 10-yr outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress; Federal and State agencies; the electric utility industry; and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended

Inventory of power plants in the United States as of January 1, 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1997. The publication also provides a 10-yr outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress; Federal and State agencies; the electric utility industry; and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended.

Analysis of the utilization history and the planning and the participation profiles of the shaft plant Asse II. Final report; Analyse der Nutzungsgeschichte und der Planungs- und Beteiligungsformen der Schachtanlage Asse II. Endbericht

Energy Technology Data Exchange (ETDEWEB)

Ipsen, Detlev; Kost, Susanne; Weichler, Holger

2010-03-08

The report on the utilization history of Asse II covers the following issues: Historical facts of the purchase of the shaft plant Asse II, decision sequences and line of arguments, research mine or final repository? Emplacement of radioactive materials (inventory), stability of the mine layout and water ingress, risk assessment - accident analysis, communication and public information, conclusions and recommendations.

Fuel performance experience at TVO nuclear power plant

International Nuclear Information System (INIS)

Patrakka, E.T.

1985-01-01

TVO nuclear power plant consists of two BWR units of ASEA-ATOM design. The fuel performance experience extending through six cycles at TVO I and four cycles at TVO II is reported. The experience obtained so far is mainly based on ASEA-ATOM 8 x 8 fuel and has been satisfactory. Until autumn 1984 one leaking fuel assembly had been identified at TVO I and none at TVO II. Most of the problems encountered have been related to leaf spring screws and channel screws. The experience indicates that satisfactory fuel performance can be achieved when utilizing strict operational rules and proper control of fuel design and manufacture. (author)

Turkey Point Plant, Units 3 and 4. Semiannual operating report No. 6, January--June 1975

International Nuclear Information System (INIS)

1975-01-01

Net electrical power generated by Unit 3 was 2,676,523 MWH(e) with the plant on line 4,148.8 hrs. Unit 4 generated 1,429,108 MWH(e) and was on line 2,232.0 hrs. Information is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, abnormal occurrences, and environmental radiation monitoring. (FS)

Visible Light Absorption of Binuclear TiOCoII Charge-Transfer UnitAssembled in Mesoporous Silica

Energy Technology Data Exchange (ETDEWEB)

Han, Hongxian; Frei, Heinz

2007-01-30

Grafting of CoII(NCCH3)2Cl2 onto mesoporous Ti-MCM-41 silicain acetonitrile solution affords binuclear Ti-O-CoII sites on the poresurface under complete replacement of the precursor ligands byinteractions with anchored Ti centers and the silica surface. The CoIIligand field spectrum signals that the Co centers are anchored on thepore surface in tetrahedral coordination. FT-infrared action spectroscopyusing ammonia gas adsorption reveals Co-O-Si bond modes at 831 and 762cm-1. No Co oxide clusters are observed in the as-synthesized material.The bimetallic moieties feature an absorption extending from the UV intothe visible to about 600 nm which is attributed to the TiIV-O-CoII?3TiIII-O-CoIII metal-to-metal charge-transfer (MMCT) transition. Thechromophore is absent in MCM-41 containing Ti and Co centers isolatedfrom each other; this material was synthesized by grafting CoII onto aTi-MCM-41 sample with the Ti centers protected by a cyclopentadienylligand. The result indicates that the appearance of the charge-transferabsorption requires that the metal centers are linked by an oxo bridge,which is additionally supported by XANES spectroscopy. The MMCTchromophore of Ti-O-CoII units has sufficient oxidation power to serve asvisible light electron pump for driving multi-electron transfer catalystsof demanding uphill reactions such as water oxidation.

The software testing of PPS for shin Ulchin nuclear power plant units 1 and 2

International Nuclear Information System (INIS)

Kang, Dong Pa; Park, Cheol Lak; Cho, Chang Hui; Sohn, Se Do; Baek, Seung Min

2012-01-01

The testing of software (S/W) is the process of analyzing a software item to detect the differences between existing and required conditions to evaluate the features of the software items. This paper introduces the S/W testing of Plant Protection System (PPS), as a safety system which actuate Reactor Trip (RT) and Engineered Safety Features (ESF) for Shin Ulchin Nuclear Power Plant Units 1 and 2 (SUN 1 and 2)

Ageing management program of wires for Atucha II Nuclear Power Plant

International Nuclear Information System (INIS)

Zorrilla, J.; Antonaccio, E.; Luraschi, C.; Simionato, E.; Nieto, H.

2012-01-01

Electrical cables constitute one of the most important components of NPP in terms o maintenance, safety and availability of the plant. Due to their large extension (thousands of kilometers) it is impossible to fully replace them and aging management becomes essential for long term operation of NPP. Since Atucha II is under construction there was a good opportunity to establish and implement a holistic cable aging management program from the beginning according to the state of the art in this field. The scope of this program involves safety related cables, including EQ cables and non EQ cables as well. Due to the diversity of the installed cables is impossible to address an aging management program of every single specimen. However it is possible to establish 'cables families' of similar aging behavior based on insulation and jacket material, manufacture, etc Several aging management strategies were set for the different 'cables families'. These strategies include cables deposit in plant, elaboration of procedures of visual and tactile inspection, NDE techniques, etc Currently the aging management program is being implemented covering topic such as: Cable screening and grouping. Review of EQ documentation and conventional qualification information referring to the installed cables. Establishment of base line of condition monitoring techniques. Calibration and set up of test parameters for NDE techniques. Aging mechanism characterization and determination of. Design construction and installation of cable deposit in plant (author)

Scenarios for multi-unit inertial fusion energy plants producing hydrogen fuel

International Nuclear Information System (INIS)

Logan, B.G.

1993-12-01

This work describes: (a) the motivation for considering fusion in general, and Inertial Fusion Energy (IFE) in particular, to produce hydrogen fuel powering low-emission vehicles; (b) the general requirements for any fusion electric plant to produce hydrogen by water electrolysis at costs competitive with present consumer gasoline fuel costs per passenger mile, for advanced car architectures meeting President Clinton's 80 mpg advanced car goal, and (c) a comparative economic analysis for the potential cost of electricity (CoE) and corresponding cost of hydrogen (CoH) from a variety of multi-unit IFE plants with one to eight target chambers sharing a common driver and target fab facility. Cases with either heavy-ion or diode-pumped, solid-state laser drivers are considered, with ''conventional'' indirect drive target gains versus ''advanced, e.g. Fast Ignitor'' direct drive gain assumptions, and with conventional steam balance-of-plant (BoP) versus advanced MHD plus steam combined cycle BoP, to contrast the potential economics under ''conventional'' and ''advanced'' IFE assumptions, respectively

Inventory of power plants in the United States, 1991

International Nuclear Information System (INIS)

1992-01-01

Operable capacity at US electric power plants totaled 693,016 megawatts, as of year-end 1991. Coal-fired capacity accounted for 43 percent (299,849 megawatts) of the total US generating capacity, the share it has essentially maintained for the past decade. Gas-fired capacity accounted for 18 percent (125,683 megawatts); nuclear, 14 percent (99,589 megawatts); water, 13 percent (92,031 megawatts); petroleum, 10 percent (72,357 megawatts); other, one percent (3,507 megawatts). The 693,016 megawatts of operable capacity includes 3,627 megawatts of new capacity that came on line during 1991 (Table 2). This new capacity is 42 percent less than capacity in new units reported for 1990. Gas-fired capacity accounted for the greatest share of this new capacity. It represents 38 percent of the new capacity that started operation in 1991. The surge in new gas-fired capacity is the beginning of a trend that is expected to exist over the next 10 years. That is, gas-fired capacity will dominate new capacity additions. Gas-fired capacity additions during the next 10 years will primarily be in simple cycle gas turbines and gas turbines operating as combined cycle units. These planned gas turbine and combined cycle units, whose capacity totals over 21,000 megawatts, are expected to serve peak and intermediate loads of electric utilities

Intermediate heat exchanger and steam generator designs for the HYLIFE-II fusion power plant using molten salts

International Nuclear Information System (INIS)

Lee, Y.T.; Hoffman, M.A.

1992-01-01

The HYLIFE-II fusion power plant employs the molten salt, Flibe, for the liquid jets which form the self-healing 'first wall' of the reactor. The molten salt, sodium fluoroborate then transports the heat from the IHX's to the steam generators. The design and optimization of the IHX's and the steam generators for use with molten salts has been done as part of the HYLIFE-II conceptual design study. The results of this study are described, and reference designs of these large heat exchangers are selected to minimize the cost of electricity while satisfying other important constraints

Decommissioning of units 1 - 4 at Kozloduy nuclear power plant in Bulgaria

International Nuclear Information System (INIS)

Dishkova, Denitsa

2014-01-01

Nuclear safety and security are absolute priorities for the European Union countries and this applies not only to nuclear power plants in operation but also to decommissioning. In terms of my technical background and my working experience in the field of licensing and environmental impact assessment during the decommissioning of Units 1 to 4 at Kozloduy Nuclear Power Plant (KNPP) in Bulgaria, I decided to present the strategy for decommissioning of Units 1 to 4 at KNPP which was selected and followed to achieve safe and effective decommissioning process. The selected strategy in each case must meet the legislative framework, to ensure safe management of spent fuel and radioactive waste, to provide adequate funding and to lead to positive socio-economic impact. The activities during the decommissioning generate large volume of waste. In order to minimize their costs and environmental impact it should be given a serious consideration to the choice, the development and the implementation of the most adequate process for treatment and the most appropriate measurement techniques. The licensing process of the decommissioning activities is extremely important and need to cope with all safety concerns and ensure optimal waste management. (authors)

78 FR 69367 - Golden Valley Electric Association: Healy Power Plant Unit #2 Restart

Science.gov (United States)

2013-11-19

... of Decision. SUMMARY: The Rural Utilities Service (RUS) has issued a Record of Decision (ROD) for the... financing from RUS to facilitate the restart of Unit 2 and for improvements to the Healy Plant, which... DOE and AIDEA. The decision documented in RUS's ROD is that RUS agrees to consider, subject to...

A fast prediction of plant behaviour in the steam generator tube rupture accident at Mihama unit 2 using a similar case

International Nuclear Information System (INIS)

Gofuku, Akio; Tanaka, Yutaka; Numoto, Atsushi; Yoshikawa, Hidekazu.

1996-01-01

It is important to predict fast and accurately future trend of behaviour of a nuclear power plant in an emergency situation. The case-based reasoning is a strong tool for this purpose because it solves a problem by effectively using past similar cases. This study investigates the applicability of the case-based reasoning as a fast prediction technique of plant behaviour. This paper discusses a prediction of initial plant behaviour in the steam generator tube rupture accident happened at the Mihama nuclear power plant unit 2 by using the behaviour data of an accident of the same type happened at Prairie Island nuclear power plant unit 1. The prediction results coincide well with the reported plant behaviour although there are several important differences in the detailed plant specifications and operator actions between the two SGTR accidents. (author)

Field measurement of the piping system vibration of Ko-Ri unit 4 during the load-following operation

International Nuclear Information System (INIS)

Chung, Tae-Young; Hong, Sung-Yull; Kim, Bum-Nyun.

1989-01-01

During the load-following operation of nuclear power plants, flow rate, temperature, and pressure in the piping system can be varied by changing the electric power output level, and these variations can cause different vibration phenomena in the piping system. The piping system vibration is important because it is directly related to the dynamic stress of the piping system and can affect the life of the piping system through structural fatigue. An assessment of vibration levels for the classes II and III piping systems of the Ko-Ri Unit 4950-MW nuclear power plant was performed according to the given pattern of the load-following operation to study its feasibility from the viewpoint of piping system vibration. The classes II and III piping system vibration of the Ko-Ri Unit 4 may not cause any potential problem under the given pattern of the load-following operation; however, it is recommended that long-term operation in the 85 to 95% power range be avoided as much as possible

Beznau II nuclear power plant: Expertise on NOK's request for the removal of the time limitation for the operation licence; KKW Beznau II: Gutachten zum Gesuch der NOK um Aufhebung der Befristung der Betriebsbewilligung

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-03-15

The Federal Agency for the Safety of Nuclear Installations (HSK) is the Swiss authority responsible for nuclear safety and protection against radioactivity in nuclear power plants. It has to examine the request of the North-East Swiss Power Corporation (NOK) concerning the removal of the operational time limitation for the Beznau-II reactor (KKB-II). In the present report HSK reviews the enterprise management and the safety of KKB-II on the basis of the results of the Periodic Safety Review. The Beznau nuclear power plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner. At the same time the plant has been improved and this guarantees that the mechanisms of ageing degradation are systematically identified and that measures can be taken that are possibly necessary. Under such conditions, the safety of KKB-II can be guarantied at all times. As a result of the management of quality, environmental and working safety conditions, the correct application and the continuous improvement of all processes important to safety are ensured. With these measures KKB has shown that safety is given priority over and against all other working goals. The examination by HSK of the Periodic Safety Review has shown that, in the past, KKB has applied modernisation measures independent of the licensing situation of the two reactor blocks. These modernisation measures largely contribute to the fact that the HSK examination did not reveal any significant safety deficiencies. Other improvement measures allow risk reduction or can bee seen as an adaptation to experience gained and to the state of the technological art. In conclusion, HSK states that no safety-relevant facts have been found which could prevent the removal of the time limitation on the operational licence for KKB-II. From the point of view of HSK, KKB-II fulfils the conditions for the safe continuation of operation

Final report on Phase II remedial action at the former Middlesex Sampling Plant and associated properties. Volume 2

International Nuclear Information System (INIS)

1985-04-01

Volume 2 presents the radiological measurement data taken after remedial action on properties surrounding the former Middlesex Sampling Plant during Phase II of the DOE Middlesex Remedial Action Program. Also included are analyses of the confirmatory radiological survey data for each parcel with respect to the remedial action criteria established by DOE for the Phase II cleanup and a discussion of the final status of each property. Engineering details of this project and a description of the associated health physics and environmental monitoring activities are presented in Volume 1

RCRA land unit closures at the Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Welch, S.H.; Kelly, B.A.; Delozier, M.F.P.; Manrod, W.E.

1987-01-01

Eight land-based hazardous waste management units at the Y-12 Plant are being closed under an integrated multi-year program. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. These units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. The closure of these sites will be funded by a new Department of Energy budget category, the Environmental Restoration Budget Category (ERBC), which is intended to provide greater flexibility in the response to closure and remedial activities. A major project, Closure and Post-Closure Activities (CAPCA), has been identified for ERBC funding to close and remediate the land units in accordance with RCRA requirements. Establishing the scope of this program has required the development of a detailed set of assumptions and a confirmation program for each assumption. Other significant activities in the CAPCA program include the development of risk assessments and the preparation of an integrated schedule

Combustion systems and power plants incorporating parallel carbon dioxide capture and sweep-based membrane separation units to remove carbon dioxide from combustion gases

Science.gov (United States)

Wijmans, Johannes G [Menlo Park, CA; Merkel, Timothy C [Menlo Park, CA; Baker, Richard W [Palo Alto, CA

2011-10-11

Disclosed herein are combustion systems and power plants that incorporate sweep-based membrane separation units to remove carbon dioxide from combustion gases. In its most basic embodiment, the invention is a combustion system that includes three discrete units: a combustion unit, a carbon dioxide capture unit, and a sweep-based membrane separation unit. In a preferred embodiment, the invention is a power plant including a combustion unit, a power generation system, a carbon dioxide capture unit, and a sweep-based membrane separation unit. In both of these embodiments, the carbon dioxide capture unit and the sweep-based membrane separation unit are configured to be operated in parallel, by which we mean that each unit is adapted to receive exhaust gases from the combustion unit without such gases first passing through the other unit.

Pre-commissioning activities of exchange units of Heavy Water Plant, Manuguru (Paper No. 1.2)

International Nuclear Information System (INIS)

Kamath, H.S.; Sikaria, R.P.

1992-01-01

Heavy Water Plant, Manuguru (HWPM) comprises of two exchange units where enrichment of deuterium from natural concentration to 15% concentration is achieved using dual temperature H 2 S-H 2 O exchange process in a three stage cascade. In each exchange unit an inventory of around 200 MT of H 2 S gas is required under normal operating pressure and a feed water flow rate of 450 MT/Hr is required to be maintained. In view of the large flow rates of H 2 S circulating gas, water, cooling water, steam etc., the lines sizes in exchange unit are quite large. Further, H 2 S gas being highly toxic and corrosive, extreme care is required in order to ensure integrity and leak tightness. While due care is taken in material selection, design, quality surveillance etc., during fabrication, certain additional measures are required to be taken during precommissioning of the systems handling H 2 S under pressure. This paper deals with the activities from completion of plant erection including hydrotesting of piping by the piping contractor to the stage of trial production run. (author)

Controlling engineering project changes for multi-unit, multi-site standardized nuclear power plants

International Nuclear Information System (INIS)

Randall, E.; Boddeker, G.; McGugin, H.; Strother, E.; Waggoner, G.

1978-01-01

Multibillioin dollar multiple nuclear power plant projects have numerous potential sources of engineering changes. The majority of these are internally generated changes, client generated changes, and changes from construction, procurement, other engineering organizations, and regulatory organizations. For multiunit, multisite projects, the use of a standardized design is cost effective. Engineering changes can then be controlled for a single standardized design, and the unit or site unique changes can be treated as deviations. Once an effective change procedure is established for change control of the standardized design, the same procedures can be used for control of unit or site unique changes

The history of the construction und operation of the KNK II German Fast Breeder Power Plant

International Nuclear Information System (INIS)

Marth, W.

1993-08-01

This report describes the German KNK fast breeder project from its beginnings in 1957 until permanent shutdown in 1991. The initial design provided for a sodium-cooled, but thermal reactor. Already during the commissioning of KNK I on the premises of the Karlsruhe Nuclear Research Center modification into a fast nuclear power plant was decided. Considerable difficulties in licensing had to be overcome. KNK II reached high burnup values in the fuel elements and closing of the fuel cycle was achieved. A number of technical problems concerning individual components are described in detail. After the politically motivated discontinuation of the SNR 300 fast breeder project at Kalkar, KNK II was shut down for good in August 1991. (orig.) [de

RCGVS design improvement and depressurization capability tests for Ulchin nuclear power plant units 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Sung, Kang Sik; Seong, Ho Je; Jeong, Won Sang; Seo, Jong Tae; Lee, Sang Keun [Korea Power Engineering Company, Inc., Seoul (Korea, Republic of); Lim, Keun Hyo; Choi, Kwon Sik; Oh, Chul Sung [Korea Electric Power Cooperation, Taejon (Korea, Republic of)

1999-12-31

The Reactor Coolant Gas Vent System(RCGVS) design for Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3 and 4) has been improved from the Yonggwang Nuclear Power Plant Units 3 and 4 (YGN 3 and 4) based on the evaluation results for depressurization capability tests performed at YGN 3 and 4. There has been a series of plant safety analyses for Natural Circulation Cooldown(NCC) event and thermo-dynamic analyses with RELAP5 code for the steam blowdown phenomena in order to optimize the orifice size of UCN 3 and 4 RCGVS. Based on these analyses results, the RCGVS orifics size for UCN 3 and 4 has been reduced to 9/32 inch from the 11/32 inch for YGN 3 and 4. The depressurization capability tests, which were performed at UCN 3 in order to verify the FSAR NCC analysis results, show that the RCGVS depressurization rates are being within the acceptable ranges. Therefore, it is concluded that the orificed flow path of UCN 3 and 4 RCGVS is adequately designed, and can provide the safety-grade depressurization capability required for a safe plant operation. 6 refs., 5 figs., 1 tab. (Author)

RCGVS design improvement and depressurization capability tests for Ulchin nuclear power plant units 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Sung, Kang Sik; Seong, Ho Je; Jeong, Won Sang; Seo, Jong Tae; Lee, Sang Keun [Korea Power Engineering Company, Inc., Seoul (Korea, Republic of); Lim, Keun Hyo; Choi, Kwon Sik; Oh, Chul Sung [Korea Electric Power Cooperation, Taejon (Korea, Republic of)

1998-12-31

The Reactor Coolant Gas Vent System(RCGVS) design for Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3 and 4) has been improved from the Yonggwang Nuclear Power Plant Units 3 and 4 (YGN 3 and 4) based on the evaluation results for depressurization capability tests performed at YGN 3 and 4. There has been a series of plant safety analyses for Natural Circulation Cooldown(NCC) event and thermo-dynamic analyses with RELAP5 code for the steam blowdown phenomena in order to optimize the orifice size of UCN 3 and 4 RCGVS. Based on these analyses results, the RCGVS orifics size for UCN 3 and 4 has been reduced to 9/32 inch from the 11/32 inch for YGN 3 and 4. The depressurization capability tests, which were performed at UCN 3 in order to verify the FSAR NCC analysis results, show that the RCGVS depressurization rates are being within the acceptable ranges. Therefore, it is concluded that the orificed flow path of UCN 3 and 4 RCGVS is adequately designed, and can provide the safety-grade depressurization capability required for a safe plant operation. 6 refs., 5 figs., 1 tab. (Author)

78 FR 65007 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

Science.gov (United States)

2013-10-30

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion...

Computation code TEP 1 for automated evaluation of technical and economic parameters of operation of WWER-440 nuclear power plant units

International Nuclear Information System (INIS)

Zadrazil, J.; Cvan, M.; Strimelsky, V.

1987-01-01

The TEP 1 program is used for automated evaluation of the technical and economic parameters of nuclear power plant units with WWER-440 reactors. This is an application program developed by the Research Institute for Nuclear Power Plants in Jaslovske Bohunice for the KOMPLEX-URAN 2M information system, delivered by the USSR to the V-2 nuclear power plants in Jaslovske Bohunice and in Dukovany. The TEP 1 program is written in FORTRAN IV and its operation has two parts. First the evaluation of technical and economic parameters of operation for a calculation interval of 10 mins and second, the control of the calculation procedure, follow-up on input data, determination of technical and economic parameters for a lengthy time interval, and data printout and storage. The TEP 1 program was tested at the first unit of the V-2 power plant and no serious faults appeared in the process of the evaluation of technical and economic parameters. A modification of the TEP 1 programme for the Dukovany nuclear power plant is now being tested on the first unit of the plant. (Z.M.)

[Diabetic foot risk in patients with type II diabetes mellitus in a family medicine unit].

Science.gov (United States)

Márquez-Godínez, S A; Zonana-Nacach, A; Anzaldo-Campos, M C; Muñoz-Martínez, J A

2014-01-01

To determine the risk of diabetic foot in patients with type II diabetes mellitus (DM) seen in a Family Medicine Unit. The study included type II DM patients with a disease duration ≥ 5 years seen in a Family Medicine Unit, Tijuana, Mexico, during September-December 2011. Neuropathy was assessed with the Diabetic Neuropathy Symptom questionnaire, and pressure sensation using a 10-g Semmes-Weinstein monofilament. A patient had a high risk of diabetic foot if there was sensitivity loss, foot deformities, and non-palpable pedal pulses. We studied 205 patients with an average (± SD) age and DM duration of 59 ± 10 years and 10.7 ± 6.7 years, respectively. Ninety one patients (44%) had a high risk of developing diabetic foot, and it was associated with; an education of less than 6 years (OR 2.3; 95%CI: 1-1-4.1), DM disease duration ≥ 10 years (OR 5.1; 95%CI: 2.8-9.4), female gender (OR 2.0; 95%CI: 1.1-3.6), monthly familiar income diabetic neuropathy, since they have a high risk of diabetic foot. Copyright © 2013 Sociedad Española de Médicos de Atención Primaria (SEMERGEN). Publicado por Elsevier España. All rights reserved.

The HYLIFE-II inertial fusion energy power plant concept and implications for IFE

International Nuclear Information System (INIS)

Moir, R.W.

1994-01-01

HYLIFE-II is based on nonflammable, renewable-liquid-wall fusion target chambers formed with Li 2 BeF 4 molten-salt jets, a heavy-ion driver, and single-sided illumination of indirect-drive targets. Building fusion chambers from existing materials with life-of-plant structural walls behind the liquid walls, while still meeting non-nuclear grade construction and low-level waste requirements, has profound implications for IFE development. Fluid-flow work and computational fluid dynamics predict chamber clearing adequate for 6-Hz pulse rates. Predicted electricity cost is reduced about 30% to 4.4 cents/kWh at 1 GWe. Development can be foreshortened and cost reduced by obviating expensive neutron sources to develop first-wall materials. The driver and chamber can be upgraded in stages, avoiding separate and sequential facilities. The most important features of a practical inertial fusion power plant are sufficient ignition and gain in targets; a low-cost, efficient, rep-ratable driver; and low-cost targets

The ring-stiffened shell of the ISAR II nuclear power plant natural-draught cooling tower

International Nuclear Information System (INIS)

Form, J.

1986-01-01

The natural-draught cooling tower of the ISAR II nuclear power plant is one of the largest in the world. The bid specifications provided for an unstiffened cooling tower shell. For the execution, however, it was decided to adopt a shell with three additional stiffening rings. The present contribution deals with the static and dynamic calculations of the execution and, in particular, with the working technique employed for the construction of the rings. (author)

Accident consequences analysis of the HYLIFE-II inertial fusion energy power plant design

Energy Technology Data Exchange (ETDEWEB)

Reyes, S. E-mail: reyessuarezl@llnl.gov; Latkowski, J.F.; Gomez del Rio, J.; Sanz, J

2001-05-21

Previous studies of the safety and environmental aspects of the HYLIFE-II inertial fusion energy power plant design have used simplistic assumptions in order to estimate radioactivity releases under accident conditions. Conservatisms associated with these traditional analyses can mask the actual behavior of the plant and have revealed the need for more accurate modeling and analysis of accident conditions and radioactivity mobilization mechanisms. In the present work, computer codes traditionally used for magnetic fusion safety analyses (CHEMCON, MELCOR) have been applied for simulating accident conditions in a simple model of the HYLIFE-II IFE design. Here we consider a severe loss of coolant accident (LOCA) in conjunction with simultaneous failures of the beam tubes (providing a pathway for radioactivity release from the vacuum vessel towards the confinement) and of the two barriers surrounding the chamber (inner shielding and confinement building itself). Even though confinement failure would be a very unlikely event it would be needed in order to produce significant off-site doses. CHEMCON code allows calculation of long-term temperature transients in fusion reactor first wall, blanket, and shield structures resulting from decay heating. MELCOR is used to simulate a wide range of physical phenomena including thermal-hydraulics, heat transfer, aerosol physics and fusion product transport and release. The results of these calculations show that the estimated off-site dose is less than 5 mSv (0.5 rem), which is well below the value of 10 mSv (1 rem) given by the DOE Fusion Safety Standards for protection of the public from exposure to radiation during off-normal conditions.

Accident consequences analysis of the HYLIFE-II inertial fusion energy power plant design

Science.gov (United States)

Reyes, S.; Latkowski, J. F.; Gomez del Rio, J.; Sanz, J.

2001-05-01

Previous studies of the safety and environmental aspects of the HYLIFE-II inertial fusion energy power plant design have used simplistic assumptions in order to estimate radioactivity releases under accident conditions. Conservatisms associated with these traditional analyses can mask the actual behavior of the plant and have revealed the need for more accurate modeling and analysis of accident conditions and radioactivity mobilization mechanisms. In the present work, computer codes traditionally used for magnetic fusion safety analyses (CHEMCON, MELCOR) have been applied for simulating accident conditions in a simple model of the HYLIFE-II IFE design. Here we consider a severe loss of coolant accident (LOCA) in conjunction with simultaneous failures of the beam tubes (providing a pathway for radioactivity release from the vacuum vessel towards the confinement) and of the two barriers surrounding the chamber (inner shielding and confinement building itself). Even though confinement failure would be a very unlikely event it would be needed in order to produce significant off-site doses. CHEMCON code allows calculation of long-term temperature transients in fusion reactor first wall, blanket, and shield structures resulting from decay heating. MELCOR is used to simulate a wide range of physical phenomena including thermal-hydraulics, heat transfer, aerosol physics and fusion product transport and release. The results of these calculations show that the estimated off-site dose is less than 5 mSv (0.5 rem), which is well below the value of 10 mSv (1 rem) given by the DOE Fusion Safety Standards for protection of the public from exposure to radiation during off-normal conditions.

78 FR 53483 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

Science.gov (United States)

2013-08-29

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00025; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...

78 FR 53484 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4

Science.gov (United States)

2013-08-29

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...

Risk maps for targeting exotic plant pest detection programs in the United States

Science.gov (United States)

R.D. Magarey; D.M. Borchert; J.S. Engle; M Garcia-Colunga; Frank H. Koch; et al

2011-01-01

In the United States, pest risk maps are used by the Cooperative Agricultural Pest Survey for spatial and temporal targeting of exotic plant pest detection programs. Methods are described to create standardized host distribution, climate and pathway risk maps for the top nationally ranked exotic pest targets. Two examples are provided to illustrate the risk mapping...

40 CFR Table 4 to Subpart Bbbb of... - Model Rule-Class II Emission Limits for Existing Small Municipal Waste Combustion Unit a

Science.gov (United States)

2010-07-01

... Existing Small Municipal Waste Combustion Unit a 4 Table 4 to Subpart BBBB of Part 60 Protection of... NEW STATIONARY SOURCES Emission Guidelines and Compliance Times for Small Municipal Waste Combustion... Part 60—Model Rule—Class II Emission Limits for Existing Small Municipal Waste Combustion Unit a For...

Inventory of power plants in the United States. [By state within standard Federal Regions, using county codes

Energy Technology Data Exchange (ETDEWEB)

None

1977-12-01

The purpose of this inventory of power plants is to provide a ready reference for planners whose focus is on the state, standard Federal region, and/or national level. Thus the inventory is compiled alphabetically by state within standard Federal regions. The units are listed alphabetically within electric utility systems which in turn are listed alphabetically within states. The locations are identified to county level according to the Federal Information Processing Standards Publication Counties and County Equivalents of the States of the United States. Data compiled include existing and projected electrical generation units, jointly owned units, and projected construction units.

78 FR 47011 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Science.gov (United States)

2013-08-02

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0195] Software Unit Testing for Digital Computer Software... revised regulatory guide (RG), revision 1 of RG 1.171, ``Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants.'' This RG endorses American National Standards...

77 FR 50722 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Science.gov (United States)

2012-08-22

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0195] Software Unit Testing for Digital Computer Software...) is issuing for public comment draft regulatory guide (DG), DG-1208, ``Software Unit Testing for Digital Computer Software used in Safety Systems of Nuclear Power Plants.'' The DG-1208 is proposed...

78 FR 38411 - Vogtle Electric Generating Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria

Science.gov (United States)

2013-06-26

... Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the inspections, tests...

Aseptic Plant Culture System (APCS), Phase II

Data.gov (United States)

National Aeronautics and Space Administration — Aseptic plant culture plays a significant role in biotechnology and plant physiology research, and in vegetative propagation of many plant species. The development...

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-12-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO 1 and II were in operation for almost the whole second quarter of 1991. The load factor average was 87.4 %. In consequence of a fire, which broke out in the switchgear building, connections to both external grids were lost and TVO II relied on power supplied by four back-up diesels for 7.5 hrs. The event is classified as Level 2 on the International Nuclear Event Scale. The process of examining the non-leaking fuel bundles removed from the Loviisa nuclear reactors has continued. The examinations have revealed, so far, that the uppermost spacing lattices of the bundles exhibit deformations similar to those detected in the leaking fuel bundles removed from the reactors. This event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale) on the Scale. The Finnish Centre for Radiation and Nuclear Safety has assessed the safety of the Loviisa and Olkiluoto nuclear power plants based on the new regulations issued on 14.2.1991 by the Council of State. The safety regulations are much more stringent than those in force when the Loviisa and Olkiluoto nuclear power plants were built. The assessment indicated that the TVO nuclear power plant meets these safety regulations. The Loviisa nuclear power plant meets the requirements with the exception of certain requirements related to the ensuring of safety functions and provision for accidents. At the Loviisa nuclear power plant there are several projects under consideration to enhance safety

External and internal accidents in PWR power plants. Comparison of current regulations in Belgium, United States, France, Federal Republic of Germany and United Kingdom

International Nuclear Information System (INIS)

Maere, G. de; Roch, M.; Cavaco, A.; Preat, M.

1986-01-01

In this report a comparison is made of the rules and practices applied in various countries (Belgium, France, Federal Republic of Germany, United Kingdom and United States of America) in designing PWR plants to resist natural hazards (first part of the report) and hazards associated with human activities (second part). The third part of the report deals with the practices in different countries concerning the protection against accidents of internal origin [fr

WWER-1000 unit reliability problems from the point of view of the main supplier of technological equipment

International Nuclear Information System (INIS)

Bursa, V.; Holousova, M.; Turnik, S.

1990-01-01

At Skoda Works in Plzen, data from the period of construction of nuclear power plants are processed on an ICL DRS 300 computer. The database systems DBASE II and DATAFLEX are available for creating reliability information systems. The information system that is being developed for WWER-1000 units is tested at the WWER-440 units of the Dukovany and Mochovce nuclear power plants. Activities in the field of evaluation of structure reliability of WWER-1000 nuclear power plants are aimed at two major goals, viz., developing a methodology for testing the reliability of the whole unit and its subsystems, and performing reliability analysis and calculations of reliability indices of the secondary circuit of a WWER-1000 nuclear power plant. The reason for the latter concern is the fact that in 1984-1986, secondary circuits contributed 46% to failures of Czechoslovak WWER-440 nuclear power plants. According to existing analyses, the time fluctuations of reliability indices obey no rule that could be employed for inferring indices expected in steady-state operating conditions from indices established in the starting stage of operation. (Z.M.). 10 refs

Effects of plant density on recombinant hemagglutinin yields in an Agrobacterium-mediated transient gene expression system using Nicotiana benthamiana plants.

Science.gov (United States)

Fujiuchi, Naomichi; Matsuda, Ryo; Matoba, Nobuyuki; Fujiwara, Kazuhiro

2017-08-01

Agrobacterium-mediated transient expression systems enable plants to rapidly produce a wide range of recombinant proteins. To achieve economically feasible upstream production and downstream processing, it is beneficial to obtain high levels of two yield-related quantities of upstream production: recombinant protein content per fresh mass of harvested biomass (g gFM -1 ) and recombinant protein productivity per unit area-time (g m -2 /month). Here, we report that the density of Nicotiana benthamiana plants during upstream production had significant impacts on the yield-related quantities of recombinant hemagglutinin (HA). The two quantities were smaller at a high plant density of 400 plants m -2 than at a low plant density of 100 plants m -2 . The smaller quantities at the high plant density were attributed to: (i) a lower HA content in young leaves, which usually have high HA accumulation potentials; (ii) a lower biomass allocation to the young leaves; and (iii) a high area-time requirement for plants. Thus, plant density is a key factor for improving upstream production in Agrobacterium-mediated transient expression systems. Biotechnol. Bioeng. 2017;114: 1762-1770. © 2017 Wiley Periodicals, Inc. © 2017 Wiley Periodicals, Inc.

Edwin I. Hatch Nuclear Plant, Unit 1. Semiannual operating report, September 12--December 31, 1974

International Nuclear Information System (INIS)

1974-01-01

Hatch-1 achieved initial criticality on September 12, 1974, and initial synchronization on November 11, 1974. The unit is a BWR of 813 MW(e) and has generated 50,775.6 MWH since September 12 with the generator on line 865.62 hours. Net plant efficiency was 20.88 percent with plant availability of 28.32 percent. Information is presented concerning operations, changes, tests, safety related maintenance, primary coolant chemistry, occupational personnel radiation doses, and radioactive effluent releases. (U.S.)

Nuclear power plant life time improvement and management program in Korea

International Nuclear Information System (INIS)

Sung Yull Hong; Ill Seok Jeong; Taek Ho Song

1995-01-01

Korea Electric Power Research Institute (KEPRI) of Korea Electric Power Corporation (KEPCO) has performed a lifetime management of nuclear power plant program (LMNPP), ''Nuclear Power Plant Lifetime Management (PLIM) (I)'', since November 1993, which is a feasibility study of the Kori Unit 1 lifetime management including aging evaluation of the thirteen major components. The results of the PLIM(I) will provide information which is necessary for decision making of the Kori Unit 1 lifetime improvement. A plan of the work scope and schedule for the next phase, PLIM(II), will also be provided by this project. This paper introduced KEPRI's basic strategy of LMNPP, PLIM organization, current status, some interim results of the PLIM(I), and other related programs in Korea. So far, we have done field data survey, systems/structures screening, components prioritization, lifetime evaluation methodology study, and fracture mechanics tests of the Kori Unit 1 reactor pressure vessel surveillance coupons. Currently life assessment of the major components and PLIM economic evaluation of Kori Unit 1 are under way. (author)

Technical evaluation of RETS-required reports for Crystal River Nuclear Generating Plant, Unit 3, for 1983

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.

1985-01-01

A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Florida Power Corporation's Crystal River Nuclear Plant, Unit 3, during 1983. The three periodic reports reviewed were (1) the Effluent and Waste Disposal Semiannual Report, January 1-June 30, 1983, (2) the Effluent and Waste Disposal Semiannual Report, July 1-December 31, 1983, and (3) the Annual Environmental Operating Report, Radiological, 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

Auxiliary units for refining of high nitrogen content oils: Premium II refinery case

Energy Technology Data Exchange (ETDEWEB)

Nicolato, Paolo Contim; Pinotti, Rafael [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil)

2012-07-01

PETROBRAS is constantly investing on its refining park in order to increase the production of clean and stable fuels and to be capable to process heavier oils with high contaminants content. Sulfur and nitrogen are the main heteroatoms present in petroleum. They are responsible for some undesirable fuels properties like corrosivity and instability, and also emit pollutants when burnt. Hydrotreating and hydrocracking processes are designed to remove these contaminants and adjust other fuel properties, generating, as byproduct, sour gases and sour water streams rich in H{sub 2}S and NH{sub 3}, which are usually sent to Sour Water Treatment Units and Sulfur Recovery Units. The regeneration of the amine used for the light streams treatment, as fuel gas and LPG, also generates sour gas streams that must be also sent to Sulfur Recovery Units. As the ammonia content in the sour streams increases, some design parameters must be adjusted to avoid increasing the Refinery emissions. Sulfur Recovery Units must provide proper NH3 destruction. Sour Water Treatment must have a proper segregation between H{sub 2}S and ammonia streams, whenever desirable. Amine Regeneration Systems must have an efficient procedure to avoid the ammonia concentration in the amine solution. This paper presents some solutions usually applied to the Petroleum Industry and analyses some aspects related to Premium II Refinery Project and how its design will help the Brazilian refining park to meet future environmental regulation and market demands. (author)

Temperature variation on the Mediterranean Sea by the exploitation of the Vandellos II Nuclear Power Plant

International Nuclear Information System (INIS)

Villarreal Romero, M.; Ribes Hernandez, G.; Esparza Martin, J. L.

2010-01-01

The aim of this study is to verify the compliance with the Resolution of 7th February MAH/285/2007 Departament de Medi Ambient I Habitatge de la Generalitat de Catalunya establishing discharges limits to the Mediterranean Sea and, in particular, the section that references the thermal rise. The study area include about 1.5 km coastline, which is located in the vicinity of the Vandellos II Nuclear Power Plant.

Optimization of the daily operation of the plants of Medio Sao Francisco; Otimizacao da operacao diaria das usinas do Medio Sao Francisco

Energy Technology Data Exchange (ETDEWEB)

Fernandes, Jessica Pillon Torralba; Colnago, Glauber Renato; Correia, Paulo de Barros; Ohishi, Takaaki [Universidade Estadual de Campinas (UNICAMP), SP (Brazil). Fac. de Engenharia Mecanica. Dept. de Energia], emails: pillon@fem.unicamp.br, colnago@fem.unicamp.br, pcorreia@fem.unicamp.br, taka@densis.fee.unicamp.br

2010-07-01

This paper presents an optimization model for daily operation of Sao Francisco hydroelectric power plants. The study considers eight power plants - Sobradinho (USB), Luiz Gonzaga (ULG), Apolonio Sales (UAS), Paulo Afonso I, II, III, (UPA), Paulo Afonso IV (USQ) e Xingo (UXG)- belongs to Sao Francisco Hydroelectric Company (CHESF). Its objective is to maximize the power plant efficiency and to minimize the number of startup and shutdowns of generating units (GU), simultaneously. Considering those GU are equal, is determined the number of units to be dispatched and their charge. The optimal dispatch, linear and non-linear programming techniques and genetic algorithms (GA) support this article. (author)

Atucha II NPP full scope simulator modelling with the thermal hydraulic code TRAC{sub R}T

Energy Technology Data Exchange (ETDEWEB)

Alonso, Pablo Rey; Ruiz, Jose Antonio; Rivero, Norberto, E-mail: prey@tecnatom.e, E-mail: jaruiz@tecnatom.e, E-mail: nrivero@tecnatom.e [Tecnatom S.A., Madrid (Spain)

2011-07-01

In February 2010 NA-SA (Nucleoelectrica Argentina S.A.) awarded Tecnatom the Atucha II full scope simulator project. NA-SA is a public company owner of the Argentinean nuclear power plants. Atucha II is due to enter in operation shortly. Atucha II NPP is a PHWR type plant cooled by the water of the Parana River and has the same design as the Atucha I unit, doubling its power capacity. Atucha II will produce 745 MWe utilizing heavy water as coolant and moderator, and natural uranium as fuel. A plant singular feature is the permanent core refueling. TRAC{sub R}T is the first real time thermal hydraulic six-equations code used in the training simulation industry for NSSS modeling. It is the result from adapting to real time the best estimate code TRACG. TRAC{sub R}T is based on first principle conservation equations for mass, energy and momentum for liquid and steam phases, with two phase flows under non homogeneous and non equilibrium conditions. At present, it has been successfully implemented in twelve full scope replica simulators in different training centers throughout the world. To ease the modeling task, TRAC{sub R}T includes a graphical pre-processing tool designed to optimize this process and alleviate the burden of entering alpha numerical data in an input file. (author)

Comparative Susceptibility of Plants Native to the Appalachian Range of the United States to Inoculation With Phytophthora ramorum

Science.gov (United States)

R.G. Linderman; Patricia B. de Sá; E.A. Davis

2008-01-01

Phytophthora ramorum, cause of sudden oak death of trees or ramorum blight of other plant species, has many hosts. Some geographic regions, such as the Appalachian range of the eastern United States, are considered high risk of becoming infested with the pathogen because known susceptible plants occur there and climatic characteristics appear...

How can we improve biomethane production per unit of feedstock in biogas plants?

International Nuclear Information System (INIS)

Asam, Zaki-ul-Zaman; Poulsen, Tjalfe Gorm; Nizami, Abdul-Sattar; Rafique, Rashad; Kiely, Ger; Murphy, Jerry D.

2011-01-01

Biogas production is one of the number of tools that may be used to alleviate the problems of global warming, energy security and waste management. Biogas plants can be difficult to sustain from a financial perspective. The facilities must be financially optimized through use of substrates with high biogas potential, low water content and low retention requirement. This research carried out in laboratory scale batch digesters assessed the biogas potential of energy crops (maize and grass silage) and solid manure fractions from manure separation units. The ultimate methane productivity in terms of volatile solids (VS) was determined as 330, 161, 230, 236, 361 L/kg VS from raw pig slurry, filter pressed manure fiber (FPMF), chemically precipitated manure fiber (CPMF), maize silage and grass silage respectively. Methane productivity based on mass (L/kg substrate) was significantly higher in FPMF (55 L/kg substrate), maize silage (68 L/kg substrate) and grass silage (45-124 L/kg substrate (depending on dry solids of feedstock)) as in comparison to raw pig slurry (10 L/kg substrate). The use of these materials as co-substrates with raw pig slurry will increase significantly the biomethane yield per unit feedstock in the biogas plant.

Horizontal transfer of potential mobile units in phytoplasmas.

Science.gov (United States)

Ku, Chuan; Lo, Wen-Sui; Kuo, Chih-Horng

2013-09-01

Phytoplasmas are uncultivated phytopathogenic bacteria that cause diseases in a wide range of economically important plants. Through secretion of effector proteins, they are able to manipulate their plant hosts to facilitate their multiplication and dispersal by insect vectors. The genome sequences of several phytoplasmas have been characterized to date and a group of putative composite transposons called potential mobile units (PMUs) are found in these highly reduced genomes. Recently, our team reported the genome sequence and comparative analysis of a peanut witches' broom (PnWB) phytoplasma, the first representative of the phytoplasma 16SrII group. Comparisons between the species phylogeny and the phylogenies of the PMU genes revealed that the PnWB PMU is likely to have been transferred from the 16SrI group. This indicates that PMUs are not only the DNA unit for transposition within a genome, but also for horizontal transfer among divergent phytoplasma lineages. Given the association of PMUs with effector genes, the mobility of PMUs across genomes has important implications for phytoplasma ecology and evolution.

Design study on the efficiency of the thermal scheme of power unit of thermal power plants in hot climates

Science.gov (United States)

Sedlov, A.; Dorokhov, Y.; Rybakov, B.; Nenashev, A.

2017-11-01

At the stage of pre-proposals unit of the thermal power plants for regions with a hot climate requires a design study on the efficiency of possible options for the structure of the thermal circuit and a set of key parameters. In this paper, the thermal circuit of the condensing unit powerfully 350 MW. The main feature of the external conditions of thermal power plants in hot climates is the elevated temperature of cooling water of the turbine condensers. For example, in the Persian Gulf region as the cooling water is sea water. In the hot season of the year weighted average sea water temperature of 30.9 °C and during the cold season to 22.8 °C. From the turbine part of the steam is supplied to the distillation-desalination plant. In the hot season of the year heat scheme with pressure fresh pair of 23.54 MPa, temperature 570/560 °C and feed pump with electric drive (EDP) is characterized by a efficiency net of 0.25% higher than thermal schem with feed turbine pump (TDP). However, the supplied power unit with PED is less by 11.6 MW. Calculations of thermal schemes in all seasons of the year allowed us to determine the difference in the profit margin of units of the TDP and EDP. During the year the unit with the TDP provides the ability to obtain the profit margin by 1.55 million dollars more than the unit EDP. When using on the market subsidized price of electricity (Iran) marginal profit of a unit with TDP more at 7.25 million dollars.

Generation IV nuclear energy systems: road map and concepts. 2. Generation II Measurement Systems for Generation IV Nuclear Power Plants

International Nuclear Information System (INIS)

Miller, Don W.

2001-01-01

need for substantial research. As we consider I and C systems in Generation IV reactors, we have the opportunity to take a much less 'timid' design philosophy than was taken in the design of I and C systems in the ALWRs. We need to make use of advanced technology to design an I and C system for the Generation IV multi-unit plant designs currently being considered. Such a design should accomplish the following: 1. provides for multi-unit control; 2. contributes to a plant design objective of a very low core damage frequency; 3. maximizes plant thermal efficiency (>50%); 4. maximizes plant capacity factor (>90%); 5. optimizes operability; 6. maximizes maintainability; 7. provides for on-line monitoring, calibration, and diagnostics; 8. provides optimum response to disturbances; 9. provides excellent load-following capability. When we consider the current situation in operating Generation I and II nuclear power plants and even Generation III ALWR design, we conclude that Generation IV reactors should employ at least Generation II measurement systems. Let us first consider data transmission, which is a form of communication, and ask the question: Do new communication-transferring methods by electrons flow in copper wires? The obvious answer is no. Virtually all new communication systems are using some electromagnetic method, such as light, microwaves, HF or VHF radio signals, and virtually no copper wires. When we envision Generation IV nuclear power plants, we should minimize the use of copper wires for data transmission. We should transmit data primarily by fiber optics and various wireless methods, some of which can penetrate thick barriers. Now let us consider sensors. If we use light for data transmission, then we should also use optical-based sensors. We should also take advantage of microprocessors, which provide opportunities to embed 'intelligence' in the sensor that can be used to increase accuracy, stability, and tolerance to external stressors (i.e., radiation

Increasing plant density in eastern United States broccoli production systems to maximize marketable head yields

Science.gov (United States)

Increased demand for fresh market broccoli (Brassica oleracea L. var. italica) has led to increased production along the eastern seaboard of the United States. Maximizing broccoli yields is a primary concern for quickly expanding eastern commercial markets. Thus, a plant density study was carried ...

Report of the international fire safety mission to Temelin, unit 1 nuclear power plant Czech Republic 4 to 14 February 1996

International Nuclear Information System (INIS)

1996-01-01

This report presents the results of an IAEA Fire Safety Mission conducted within the scope of Technical Co-operation Project CZR/9/005 to assess the licensing process, design, analysis and operational management of the Temelin Nuclear Power Plant with regards to fire safety of the plant. The Temelin Nuclear Power Plant currently has two units under construction. Each unit is equipped with a pressurized water reactor of the WWER design with a net electrical output of about MWe. The plant has already made significant upgrading in fire protection from the original design. The Team's evaluation is based on the IAEA Safety Series No. 50-SG-D2 (Rev.1), Fire Protection in Nuclear Power Plants, and other fire protection guidelines currently produced by the IAEA. The evaluation, conclusions and recommendations presented in this report reflect the views of the Fire Safety Mission experts. The recommendations are provided for consideration by the responsible authorities in the Czech Republic towards enhancing fire safety at the Temelin plant

The new local control systems for operating gaseous diffusion plant units at Pierrelatte

International Nuclear Information System (INIS)

Delacroix, C.

1990-01-01

The development of a local control network for operating gaseous diffusion plant units is presented. The objective of the control system up date was to replace all the information network hardware. The new generation HP1000 calculators and a network architecture were chosen. The validation tests performed in laboratory and in situ, and the management policies towards the personnel during the technical changes are summarized [fr

Draft environmental statement: Related to operation of the Edwin I. Hatch Nuclear Plant Unit No. 2, Georgia Power Company: Docket No. 50-366

International Nuclear Information System (INIS)

1977-04-01

The proposed action is the issuance of an operation license to the Georgia Power Company for the startup and operation of the Edwin I. Hatch Nuclear Plant, Unit No. 2 (Docket No. 50-366), located on the Altamaha River in Appling County, approximately 11 miles north from Baxley, Georgia. The information in this Statement represents the second, assessment of the environmental impact associated with the Edwin I. Hatch Nuclear Plant, Unit No. 2, pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receipt of an application, in 1970, to construct this plant, the staff carried out a review of impact that would occur during the construction and operation of this plant. That evaluation was issued as a Final Environmental Statement in October 1972. As the result of that environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and a public hearing in Baxley, Georgia and Washington, D.C., the AEC (now NRC) issued a permit in December 1972, for the construction of Unit No. 2 of the Edwin I. Hatch Nuclear Plant. As of February 1977, the construction of Unit No. 2 was 70% complete. With a proposed fuel-loading date of April 1978 for Unit No. 2, the applicant has petitioned for license to operate Unit No. 2 and has submitted (July 1975) the required safety and environmental reports to substantiate this petition. 97 refs., 18 figs., 37 tabs

Safety and operating experience at EBR-II: lessons for the future

International Nuclear Information System (INIS)

Sackett, J.I.; Golden, G.H.

1981-01-01

EBR-II is a small LMFBR power plant that has performed safely and reliably for 16 years. Much has been learned from operating it to facilitate the design, licensing, and operation of large commercial LMFBR power plants in the US. EBR-II has been found relatively easy to keep in conformity with evolving safety requirements, largely because of inherent safety features of the plant. Such features reduce dependence on active safety systems to protect against accidents. EBR-II has experienced a number of plant-transient incidents, some planned, others inadvertent; none has resulted in any significant plant damage. The operating experience with EBR-II has led to the formulation of an Operational Reliability Test Program (ORTP), aimed at showing inherently safe performance of fuel and plant systems

Resource Conservation and Recovery Act (RCRA) Part B Permit Application for Production Associated Units at the Oak Ridge Y-12 Plant

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

This is the RCRA required permit application for Radioactive and Hazardous Waste Management at the Oak Ridge Y-12 Plant for the following units: Building 9206 Container Storage Unit; Building 9212 Container Storage Unit; Building 9720-12 Container Storage Unit; Cyanide Treatment Unit. All four of these units are associated with the recovery of enriched uranium and other metals from wastes generated during the processing of nuclear materials.

Resource Conservation and Recovery Act (RCRA) Part B Permit Application for Production Associated Units at the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

1994-09-01

This is the RCRA required permit application for Radioactive and Hazardous Waste Management at the Oak Ridge Y-12 Plant for the following units: Building 9206 Container Storage Unit; Building 9212 Container Storage Unit; Building 9720-12 Container Storage Unit; Cyanide Treatment Unit. All four of these units are associated with the recovery of enriched uranium and other metals from wastes generated during the processing of nuclear materials

Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis

International Nuclear Information System (INIS)

Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R.

1993-01-01

The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the I nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant , CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

Biomass Production System (BPS) Plant Growth Unit

Science.gov (United States)

Morrow, R. C.; Crabb, T. M.

The Biomass Production System (BPS) was developed under the Small Business Innovative Research (SBIR) program to meet science, biotechnology and commercial plant growth needs in the Space Station era. The BPS is equivalent in size to a double middeck locker, but uses it's own custom enclosure with a slide out structure to which internal components mount. The BPS contains four internal growth chambers, each with a growing volume of more than 4 liters. Each of the growth chambers has active nutrient delivery, and independent control of temperature, humidity, lighting, and CO2 set-points. Temperature control is achieved using a thermoelectric heat exchanger system. Humidity control is achieved using a heat exchanger with a porous interface which can both humidify and dehumidify. The control software utilizes fuzzy logic for nonlinear, coupled temperature and humidity control. The fluorescent lighting system can be dimmed to provide a range of light levels. CO2 levels are controlled by injecting pure CO2 to the system based on input from an infrared gas analyzer. The unit currently does not scrub CO2, but has been designed to accept scrubber cartridges. In addition to providing environmental control, a number of features are included to facilitate science. The BPS chambers are sealed to allow CO2 and water vapor exchange measurements. The plant chambers can be removed to allow manipulation or sampling of specimens, and each chamber has gas/fluid sample ports. A video camera is provided for each chamber, and frame-grabs and complete environmental data for all science and hardware system sensors are stored on an internal hard drive. Data files can also be transferred to 3.5-inch disks using the front panel disk drive

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-08-01

During the first quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 32.5% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 99.0%. An international nuclear event scale has been introduced for the classification of nuclear power plant events according to their nuclear and radiation safety significance. The scale first undergoes about a year long trial period in several countries. on the scale, events are divided into levels from 1 to 7 of which events at Level 7 are the most serious. Furthermore, Level 0 (Below Scale) is used for events with no safety significance. All events which occurred at the Finnish nuclear power plants this quarter are classified as Level 0. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. At the Loviisa plant, a back-up emergency feedwater system independent of the plant's other systems has been introduced which offers a new, alternative means of removing residual heat from the reactor. Owing to this system, the risk of a severe accident has been further reduced. At the TVO plants, systems have been introduced by which accident sequences which lead to containment failure could be eliminated and the consequences of a potential severe accident could be mitigated. In this report, also the release of short-lived radioactive materials along the transfer route of an irradiated sample is described which occured at the FiR 1 research reactor. The amounts of radioactive materials individuals received in their bodies in connection with this event were very low

Superfund record of decision (EPA Region 3), Westinghouse Elevator Company Plant, Operable Unit 2, Cumberland Township, Adams County, Gettysburg, PA, March 31, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

This Record of Decision (ROD) presents the selected remedial action for Operable Unit 2 (Soils) at the Westinghouse Elevator Company Plant Site in Adams County, Pennsylvania. The selected remedy for the soils at the Westinghouse Elevator Plant is No Additional Action for this Operable Unit. The other alternatives evaluated would produce little or no environmental benefit at substantial cost.

STARFIRE-II studies. Summary

International Nuclear Information System (INIS)

Baker, C.C.; Brooks, J.N.; Ehst, D.A.; Smith, D.L.; Sze, D.K.

1985-01-01

The US Department of Energy's Office of Fusion Energy has initiated several studies during FY-1985 called Tokamak Power System Studies (TPSS). The TPSS is being carried out by several laboratories, universities and industry with the general objective of developing innovative physics and technology concepts to improve the commercial attractiveness of tokamak power reactors. The effort of Argonne National Laboratory, entitled STARFIRE-II, is an effort to update and improve STARFIRE, which was the last comprehensive conceptual design study in the US of a commercial tokamak power plant. The STARFIRE-II effort has developed a number of goals in order to improve fusion commercial power plants based in part on several recent studies. The primary goals for STARFIRE-II are listed

EVALUASI KINERJA UNIT BISNIS ASPHALT MIXING PLANT PT PRAYOGA PERTAMBANGAN DAN ENERGI

OpenAIRE

Raden Isma Anggraini; Aida Vitayala Hubeis; Radjab Tampubolon

2016-01-01

Currently, the mining sector is still one of the main sectors driving the economy of Indonesia and is in demand by both indigenous and foreign investors. Asphalt mixing plant business unit (AMP BU) is currently the main priority scale of PT Prayoga. The AMP UB excellent performance of PT Prayoga enable itself to be able to contribute to the company's revenue and accelerate development of infrastructure in Bogor. The objectives of the research were to identify key performance indicator (KPI) t...

Resource Conservation and Recovery Act (RCRA) Part B permit application for Production Associated Units at the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

1995-05-01

Attention is focused on permit applications for the following units: Building 9206 Container Storage Unit; Building 9212 Container Storage Unit; Building 9720-12 Container Storage Unit; and Cyanide Treatment Unit. This report addresses the following areas: facility description; waste characteristics; process information; ground water monitoring; procedures to prevent hazards; contingency plan; personnel training; closure plan, post closure plant, and financial requirements; record keeping; other federal laws; organic air emissions; solid waste management units; and certification

Resource Conservation and Recovery Act (RCRA) Part B permit application for Production Associated Units at the Oak Ridge Y-12 Plant

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

Attention is focused on permit applications for the following units: Building 9206 Container Storage Unit; Building 9212 Container Storage Unit; Building 9720-12 Container Storage Unit; and Cyanide Treatment Unit. This report addresses the following areas: facility description; waste characteristics; process information; ground water monitoring; procedures to prevent hazards; contingency plan; personnel training; closure plan, post closure plant, and financial requirements; record keeping; other federal laws; organic air emissions; solid waste management units; and certification.

N-donor co-ligands driven two new Co(II)- coordination polymers with bi- and trinuclear units: Crystal structures, and magnetic properties

Energy Technology Data Exchange (ETDEWEB)

Zhou, Zhi-Hang [College of Materials and Chemical Engineering, Hubei Provincial Collaborative Innovation Center for New Energy Microgrid, Key Laboratory of Inorganic Non-metallic Crystalline and Energy Conversion Materials, China Three Gorges University, Yichang 443002 (China); Han, Min-Le [College of Chemistry and Chemical Engineering, Henan Key Laboratory of Function-Oriented Porous Materials, Luoyang Normal University, Luoyang 471022 (China); Wu, Ya-Pan; Dong, Wen-Wen [College of Materials and Chemical Engineering, Hubei Provincial Collaborative Innovation Center for New Energy Microgrid, Key Laboratory of Inorganic Non-metallic Crystalline and Energy Conversion Materials, China Three Gorges University, Yichang 443002 (China); Li, Dong-Sheng, E-mail: lidongsheng1@126.com [College of Materials and Chemical Engineering, Hubei Provincial Collaborative Innovation Center for New Energy Microgrid, Key Laboratory of Inorganic Non-metallic Crystalline and Energy Conversion Materials, China Three Gorges University, Yichang 443002 (China); Lu, Jack Y., E-mail: lu@uhcl.edu [Department of Chemistry, University of Houstons-Clear Lake, Houston, TX 77058 (United States)

2016-10-15

Two new Co(II) coordination polymers(CPs), namely [Co{sub 2}(bpe){sub 2}(Hbppc)]{sub n} (1) and [Co{sub 3}(μ{sub 3}-OH)(bppc)(bpm)(H{sub 2}O)]·3H{sub 2}O (2) (H{sub 5}bppc=biphenyl-2,4,6,3′,5′-pentacarboxylic acid, bpe=1,2-bis(4-pyridyl)ethene, bpm=bis(4-pyridyl)amine), have been obtained and characterized by elemental analysis, single-crystal X-ray diffraction, powder X-ray diffraction (PXRD), IR spectra and thermogravimetric analysis (TGA). 1 shows a binodal (4,6)-connected fsc net with a (4{sup 4}·6{sup 10}·8)(4{sup 4}·6{sup 2}) topology, while 2 shows a binodal (5,7)-connected 3D network based on trinuclear [Co{sub 3}(μ{sub 3}-OH)]{sup 5+} units with unusual (3.4{sup 6}.5{sup 2}.6)(3{sup 2}.4{sup 6}.5{sup 7}.6{sup 5}.7) topology. Variable-temperature magnetic susceptibility measurements reveals that complex 1 shows ferromagnetic interactions between the adjacent Co(II) ions, whereas 2 is a antiferromagnetic system. - Graphical abstract: Two new Co(II) coordination polymers with bi- and trinuclear units have been obtained. 1 shows a binodal (4,6)-connected fsc net with a (4{sup 4}·6{sup 10}·8)(4{sup 4}·6{sup 2}) topology and antiferromagnetic interactions between the adjacent Co(II) ions, while 2 is a binodal (5,7)-connected 3D network with unusual (3.4{sup 6}.5{sup 2}.6)(3{sup 2}.4{sup 6}.5{sup 7}.6{sup 5}.7) topology and a ferromagnetic system. - Highlights: • Two Co(II) coordination polymers with different multimetallic clusters as building units. • A (4,6)-connected fsc net and a (5,7)-connected 3D network. • A antiferromagnetic coupling for 1 and A ferromagnetic coupling for 2.

78 FR 79709 - Duke Energy Florida, Inc., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown...

Science.gov (United States)

2013-12-31

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-302; NRC-2013-0283] Duke Energy Florida, Inc., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear Regulatory Commission (NRC). ACTION: Notice of receipt; availability; public meeting; and request...

Policing starter unit selection of the enterocin type II polyketide synthase by the type II thioesterase EncL.

Science.gov (United States)

Kalaitzis, John A; Cheng, Qian; Meluzzi, Dario; Xiang, Longkuan; Izumikawa, Miho; Dorrestein, Pieter C; Moore, Bradley S

2011-11-15

Enterocin is an atypical type II polyketide synthase (PKS) product from the marine actinomycete 'Streptomyces maritimus'. The enterocin biosynthesis gene cluster (enc) codes for proteins involved in the assembly and attachment of the rare benzoate primer that initiates polyketide assembly with the addition of seven malonate molecules and culminates in a Favorskii-like rearrangement of the linear poly-β-ketone to give its distinctive non-aromatic, caged core structure. Fundamental to enterocin biosynthesis, which utilizes a single acyl carrier protein (ACP), EncC, for both priming with benzoate and elongating with malonate, involves maintaining the correct balance of acyl-EncC substrates for efficient polyketide assembly. Here, we report the characterization of EncL as a type II thioesterase that functions to edit starter unit (mis)priming of EncC. We performed a series of in vivo mutational studies, heterologous expression experiments, in vitro reconstitution studies, and Fourier-transform mass spectrometry-monitored competitive enzyme assays that together support the proposed selective hydrolase activity of EncL toward misprimed acetyl-ACP over benzoyl-ACP to facilitate benzoyl priming of the enterocin PKS complex. While this system resembles the R1128 PKS that also utilizes an editing thioesterase (ZhuC) to purge acetate molecules from its initiation module ACP in favor of alkylacyl groups, the enterocin system is distinct in its usage of a single ACP for both priming and elongating reactions with different substrates. Copyright © 2011 Elsevier Ltd. All rights reserved.

Start-up test of Fukushima Daini Nuclear Power Station Unit No.3

International Nuclear Information System (INIS)

Inomata, Toshio; Umezu, Akira; Kajikawa, Makoto; Koibuchi, Hiroshi; Netsu, Nobuhiko.

1986-01-01

In Unit 3 of the Fukushima Nuclear Power Station II (daini), a BWR power plant of output 1,100 MW, commercial operation was started in June 1985. Its start-up test was finished successfully in about nine months. That is, new equipments introduced were demonstration tested. Though the items of testing are increased, the start-up test took short time, resulting in construction period only 54.7 months of the Unit 3, the shortest in the world. During the test, there was no scramming other than the planned. Described are the following: an outline of the Unit 3, the items of its improvement and standardization, including the new equipments, preparations for the start-up test, the start-up test and its evaluation. (Mori, K.)

The research on corrosion condition and anticorrosion methods of SEP system pipelines in Qinshan Nuclear Power Plant Phase II

International Nuclear Information System (INIS)

Zhang Wei; Cao Feng; Wang Jianjun

2010-01-01

SEP system in Qinshan nuclear power plant phase II provides drinking water and firefight water for nuclear island, conventional island, inner and outer of BOP structures. Many corrosion perforations in the SEP pipeline were found during operation. This article analysis the corrosion reasons and presents some reasonable treatment and surveillance methods. (authors)

Safety evaluation report related to the operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-328, Tennessee Valley Authority. Supplement No. 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1981-01-01

On September 17, 1980, the Nuclear Regulatory Commission (NRC) issued the facility operating license DPR-77 to the Tennessee Valley Authority for the Sequoyah Nuclear Plant, Unit 1, located in Hamilton County, Tennessee. The license authorized operation of Unit 1 at 100 percent power; however, a license condition regarding the adequacy of the hydrogen control system was included that required resolution by January 31, 1981. The purpose of Supplement No. 4 to the SER is to further update our Safety Evaluation Reports on the hydrogen control measures (Section 22.2, II.B.7), and to comply with the license condition which is as follows: 'By January 31, 1981, TVA shall by testing and analysis show to the satisfaction of the NRC staff that an interim hydrogen control system will provide with reasonable assurance protection against breach of containment in the event that a substantial quantity of hydrogen is generated.' TVA submitted on December 11, 1980, the first quarterly report on the research program for hydrogen control. Also, TVA revised volume 2 of the Sequoyah Core Degradation Program Report to incorporate additional information on the overall program. Section II.B.7 of Supplement No. 4 responds to the license condition. Each section is supplementary to and not in lieu of discussion in the Safety Evaluation Report and Supplements Nos. 1, 2, and 3, except where specifically noted. Supplements No. 2 and 3 to the Safety Evaluation Report provided a basis for concluding that the full-power licensing of Sequoyah Unit 1 need not await completion of ongoing work on hydrogen control measures. This supplement concludes that operation of the IDIS for an interim period of one year is appropriate.

Specification of an Expert system for the control of extraction units in reprocessing plants

International Nuclear Information System (INIS)

Jorda, A.; Charon, E.; Coppens, P.; Romet, J.L.

1986-01-01

Industrial operation of extraction units in reprocessing plants is very complex because the great number of chemical and hydraulic parameters to take into account. This complexity associated to the impossibility to see inside the active enclosures make difficult the operation processes, diagnosis and corrections. Management of parameters by an expert system will increase productivity and safety of solvent extraction in pulsed columns [fr

75 FR 8753 - Carolina Power & Light Company, Brunswick Steam Electric Plant, Units 1 and 2; Environmental...

Science.gov (United States)

2010-02-25

... Dusenbury of the North Carolina Department of Environment and Natural Resources regarding the environmental... & Light Company, Brunswick Steam Electric Plant, Units 1 and 2; Environmental Assessment and Finding of No... identification of licensing and regulatory actions requiring environmental assessments,'' the NRC prepared an...

Plant automation

International Nuclear Information System (INIS)

Christensen, L.J.; Sackett, J.I.; Dayal, Y.; Wagner, W.K.

1989-01-01

This paper describes work at EBR-II in the development and demonstration of new control equipment and methods and associated schemes for plant prognosis, diagnosis, and automation. The development work has attracted the interest of other national laboratories, universities, and commercial companies. New initiatives include use of new control strategies, expert systems, advanced diagnostics, and operator displays. The unique opportunity offered by EBR-II is as a test bed where a total integrated approach to automatic reactor control can be directly tested under real power plant conditions

Final Environmental Statement related to the operation of Perry Nuclear Power Plant, Units 1 and 2 Docket Nos. 50-440 and 50-441, Cleveland Electric Illuminating Company

International Nuclear Information System (INIS)

1982-08-01

The information in this Final Environmental Statement is the second assessment of the environmental impact associated with the construction and operation of the Perry Nuclear Power Plant, Units 1 and 2, located on Lake Erie in Lake County, about 11 km (7 mi) northeast of Painesville, Ohio. The first assessment was the Final Environmental Statement related to the construction of the plant issued in April 1974, prior to issuance of the construction permits (CPRR-148 and CPPR-149). Plant construction for Unit 1 is currently about 83% complete, and Unit 2 about 43% complete. Fuel loading for Units 1 and 2 currently estimated by the licensee (Cleveland Electric Illuminating Company) for November 1983, with Unit 2 fuel load scheduled for May 1987. The present assessment is the result of the NRC staff review of the activities associated with the proposed operation of the plant

Development of ultra supercritical (USC) power plant

Energy Technology Data Exchange (ETDEWEB)

Chang, Sung Ho; Kim, Bum Soo [KEPCO Research Institute, Daejeon (Korea, Republic of); Min, Taek Ki [Chung Nat' l Univ., Cheongwon (Korea, Republic of)

2012-02-15

For environmental reasons and because of our limited energy resources, high efficiency power generation technology will be necessary in the future. Ultra supercritical (USC) power generation technology is the key to managing the greenhouse gas problems and energy resource problems discussed in the Kyoto Protocol to the United Nations Framework Convention on Climate Change. Other countries and manufacturers are trying to build commercial power plants. In this paper, an efficient method of achieving near zero emission operation of a high efficiency fossil power plant using USC power generation is discussed. Development of USC power generation in Korea has been supported by the Korean government in two phases: Phase I was USC key technology development from 2002 to 2008, and Phase II is USC development and technology optimization from 2010 to 2017.

Estimating Climate Trends: Application to United States Plant Hardiness Zones

Directory of Open Access Journals (Sweden)

Nir Y. Krakauer

2012-01-01

Full Text Available The United States Department of Agriculture classifies plant hardiness zones based on mean annual minimum temperatures over some past period (currently 1976–2005. Since temperatures are changing, these values may benefit from updating. I outline a multistep methodology involving imputation of missing station values, geostatistical interpolation, and time series smoothing to update a climate variable’s expected value compared to a climatology period and apply it to estimating annual minimum temperature change over the coterminous United States. I show using hindcast experiments that trend estimation gives more accurate predictions of minimum temperatures 1-2 years in advance compared to the previous 30 years’ mean alone. I find that annual minimum temperature increased roughly 2.5 times faster than mean temperature (~2.0 K versus ~0.8 K since 1970, and is already an average of 1.2  0.5 K (regionally up to ~2 K above the 1976–2005 mean, so that much of the country belongs to warmer hardiness zones compared to the current map. The methods developed may also be applied to estimate changes in other climate variables and geographic regions.

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-12-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well TVO I and II were in operation for almost the whole second quarter of 1992. Longer breaks in production were caused by the annual maintenance of the TVO plant units. The load factor was 87.4 %. At TVO I it was detected during the annual maintenance outage when removing nuclear fuel assemblies from the reactor that one assembly had been loaded into the reactor in an incorrect manner during the previous year's annual maintenance: the assembly was slightly higher than the other assemblies. The water cooling the nuclear fuel partly by-passed the fuel assembly and the coolant flow proper passing through the assembly was below design. The fuel assembly's cooling had been sufficient during the whole operating cycle but could have essentially deteriorated during certain transients with the danger of consequent damage to some fuel rods. On the International Nuclear Event Scale the event is classified as level 1. Other events in this quarter which are classified on the International Nuclear Event Scale were level 0/below scale on the scale

Human Reliability analysis for digitized nuclear power plants: Case study on the LingAo II nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Zou, Yan Hua; Zhang, Li [Institute of Human Factors Engineering AND Safety Management, Hunan Institute of Technology, Hengyang (China); Dai, Cao; Li, Peng Cheng; Qing, Tao [Human Factors Institute, University of South China, Hengyang (China)

2017-03-15

The main control room (MCR) in advanced nuclear power plants (NPPs) has changed from analog to digital control system (DCS). Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

Human Reliability Analysis for Digitized Nuclear Power Plants: Case Study on the LingAo II Nuclear Power Plant

Directory of Open Access Journals (Sweden)

Yanhua Zou

2017-03-01

Full Text Available The main control room (MCR in advanced nuclear power plants (NPPs has changed from analog to digital control system (DCS. Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

Final environmental statement related to operation of Indian Point Nuclear Generating Plant, Unit No. 3: (Docket No. 50-286): Volume 1

International Nuclear Information System (INIS)

1975-02-01

The proposed action is the issuance of a license to consolidated Edison Company of New York, Inc., for the operation of the Indian Point Nuclear Generating Plant, Unit No. 3, located in the State of New York, Westchester County, Village of Buchanan, 24 miles north of the New York City boundary line. Although the present action is the issuance of an operating license for Unit No. 3, this Statement considers the environmental impacts from simultaneous operation of all three Units. A Final Environmental Statement has been issued for Unit No. 2. Furthermore, in view of the proximity to the Indian Point site of existing and presently proposed power plants on the Hudson River, the cumulative environmental benefits and impacts of the plants within a 30-mile reach of the river have been assessed. The proposed action is interreleated to other actions taken by other Federal agencies such as the Environmental Protection Agency, in regard to granting or denying application for discharge permits under the National Pollutant Discharge Elimination System (NPDES) instituted through the Federal Water Pollution Control Act Amendments of 1972, and the Federal Power Commission, in licensing of other facilities on the Hudson River. 128 figs., 210 tabs

Risk-based assessment of the allowable outage times for the unit 1 leningrad nuclear power plant ECCS components

International Nuclear Information System (INIS)

Koukhar, Sergey; Vinnikov, Bronislav

2009-01-01

Present paper describes a method for risk - informed assessment of the Allowable Outage Times (AOTs). The AOT is the time, when components of a safety system allowed to be out of service during power operation or during shutdown operation off a plant. If the components are not restored during the time, the plant in operation must be shut down or the plant in a given shutdown mode has to go to safer shutdown mode. Application of the method is also provided for the equipment of the Unit 1 Leningrad NPP ECCS components. For solution of the problem it is necessary to carry out two series of computations using a Living PSA model, level 1. In the first series of the computations the core damage frequency (CDFb) for the base configuration of the plant is determined (there is no equipment out of service). Here the symbol 'b' means the base configuration of a plant. In the second series of the computations the core damage frequency (CDFi) for the configuration of the plant with the component (which is out of service) is calculated. That is here CDFi is determined for the failure probability of the component equal to 1.0 (component 'i' is unavailable). Then it is necessary to determine so called Risk Increase Factor (RIF) using the following ratio: RIFi = CDFi / CDFb. At last the AOT is calculated with the help of the ratio: AOTi = Tppr / RIFi, where Tppr is a period of time between two Planned Preventive Repairs (PPRs). 1. Using the risk based approach the AOTs were calculated for a set of the components of the Unit 1 Leningrad NPP ECCS components. 2. The main conclusion from the analysis is that the current deterministic AOTs for the ECCS components are conservative and should be extended. 3. The risk based extension of the AOTs for the ECCS components can prevent the Unit 1 Leningrad NPP to enter into the operating modes with increased risk. (author)

Synthesis, NMR characterization, X-ray crystal structure of Co(II) Ni(II) and Cu(II) complexes of a pyridine containing self-assembling

International Nuclear Information System (INIS)

Ranjbar, M.; Taghavipour, M.; Moghimi, A.; Aghabozorg, H.

2002-01-01

In the recent years, the self-assembling systems have been attracted chemists. The intermolecular bond in such systems mainly consists of ion pairing and hydrogen bonding [1,2]. The reaction between self-assembling system liquid LH 2 (py dc=2,6-pyridinedicarboxylic acid and py da=2,6- pyridine diamin) with cobalt (II) nitrate, nickel (II) chloride, and copper (II) acetate in water leads to the formation of self- assemble coordination complexes, [py da.H] 2 [M(py dc) 2 ]. H 2 O, M=Co(II),Ni(II), and Cu(II). The characterization was performed using elemental analysis, ESI mass spectroscopy, 1 H and 13 C NMR and X-ray crystallography. The crystal systems are monoclinic with space group P2 1 /n and four molecules per unit cell. These complexes shows 13 C NMR resonances of cationic counter ion [(py dc,H)] + in DMSO- d 6 but no signal corresponding to the two coordinated ligands [py dc] 2- The metal atoms are six-coordinated with a distorted octahedral geometry. The two [py de] 2- units are almost perpendicular to each other

EBR-II [Experimental Breeder Reactor-II] system surveillance using pattern recognition software

International Nuclear Information System (INIS)

Mott, J.E.; Radtke, W.H.; King, R.W.

1986-02-01

The problem of most accurately determining the Experimental Breeder Reactor-II (EBR-II) reactor outlet temperature from currently available plant signals is investigated. Historically, the reactor outlet pipe was originally instrumented with 8 temperature sensors but, during 22 years of operation, all these instruments have failed except for one remaining thermocouple, and its output had recently become suspect. Using pattern recognition methods to compare values of 129 plant signals for similarities over a 7 month period spanning reconfiguration of the core and recalibration of many plant signals, it was determined that the remaining reactor outlet pipe thermocouple is still useful as an indicator of true mixed mean reactor outlet temperature. Application of this methodology to investigate one specific signal has automatically validated the vast majority of the 129 signals used for pattern recognition and also highlighted a few inconsistent signals for further investigation

EBR-II: summary of operating experience

International Nuclear Information System (INIS)

Perry, W.H.; Leman, J.D.; Lentz, G.L.; Longua, K.J.; Olson, W.H.; Shields, J.A.; Wolz, G.C.

1978-01-01

Experimental Breeder Reactor II (EBR-II) is an unmoderated, sodium-cooled reactor with a design power of 62.5 MWt. The primary cooling system is a submerged-pool type. The early operation of the reactor successfully demonstrated the feasibility of a sodium-cooled fast breeder reactor operating as an integrated reactor, power plant, and fuel-processing facility. In 1967, the role of EBR-II was reoriented from a demonstration plant to an irradiation facility. Many changes have been made and are continuing to be made to increase the usefulness of EBR-II for irradiation and safety tests. A review of EBR-II's operating history reveals a plant that has demonstrated high availability, stable and safe operating characteristics, and excellent performance of sodium components. Levels of radiation exposure to the operating and maintenance workers have been low; and fission-gas releases to the atmosphere have been minimal. Driver-fuel performance has been excellent. The repairability of radioactive sodium components has been successfully demonstrated a number of times. Recent highlights include installation and successful operation of (1) the hydrogen-meter leak detectors for the steam generators, (2) the cover-gas-cleanup system and (3) the cesium trap in the primary sodium. Irradiations now being conducted in EBR-II include the run-beyond-cladding breach fuel tests for mixed-oxide and carbide elements. Studies are in progress to determine EBR-II's capability for conducting important ''operational safety'' tests. These tests would extend the need and usefulness of EBR-II into the 1980's

TRUPACT-II 157 Examination Report

International Nuclear Information System (INIS)

Barry H. O'Brien; Jeffrey M. Lacy; Kip E. Archibald

2003-01-01

This report presents the results of examination and recovery activities performed on the TRUPACT-II 157 shipping container. The container was part of a contact-handled transuranic waste shipment being transported on a truck to the Waste Isolation Pilot Plant in New Mexico when an accident occurred. Although the transport vehicle sustained only minor damage, airborne transuranic contamination was detected in air samples extracted from inside TRUPACT-II 157 at the Waste Isolation Pilot Plant. Consequently, the shipping container was rejected, resealed, and returned to the Idaho National Engineering and Environmental Laboratory where the payload was disassembled, examined, and recovered for subsequent reshipment to the Waste Isolation Pilot Plant. This report documents the results of those activities

TRUPACT-II 157 Examination Report

Energy Technology Data Exchange (ETDEWEB)

Barry H. O& #39; Brien; Jeffrey M. Lacy; Kip E. Archibald

2003-12-01

This report presents the results of examination and recovery activities performed on the TRUPACT-II 157 shipping container. The container was part of a contact-handled transuranic waste shipment being transported on a truck to the Waste Isolation Pilot Plant in New Mexico when an accident occurred. Although the transport vehicle sustained only minor damage, airborne transuranic contamination was detected in air samples extracted from inside TRUPACT-II 157 at the Waste Isolation Pilot Plant. Consequently, the shipping container was rejected, resealed, and returned to the Idaho National Engineering and Environmental Laboratory where the payload was disassembled, examined, and recovered for subsequent reshipment to the Waste Isolation Pilot Plant. This report documents the results of those activities.

A new concept for filtration units for trapping radioactive aerosols and iodine in the ventilation systems of nuclear power plants with WWER reactors

International Nuclear Information System (INIS)

Foerster, V.; Slanina, S.

1985-01-01

The paper describes a concept for new filtration units in the ventilation systems of nuclear power plants with WWER reactors. The new units are characterized by more stringent requirements on the efficiency of air purification (removal of radioactive contaminants) and various requirements for the quality of air purification in the ventilation systems. Work performed at the Scientific Research Institute for Air Technology has resulted in filtration units of a universal modular type, the structural design of which permits a high degree of variation in their component parts. A brief description is given of the filtration units, their basic technical characteristics and examples of their use in nuclear power plant ventilation systems. (author)

Construction technique for a chemical plant (II)

International Nuclear Information System (INIS)

1978-08-01

This book deals with design and construction for a chemical plant which includes design and building of steel structure for a chemical plant with types, basic regulation, plan, shop fabrication for steel structure and field construction. It explains design and construction of making building for a chemical construction with measurement, types of building and basic rule of the building, design of the building, constructing plumbing for a chemical plant with plan, management of material, checking for construction, construction of electrical installation on plan, know-how to construction and maintenance.

Characteristics and verification of a car-borne survey system for dose rates in air: KURAMA-II

International Nuclear Information System (INIS)

Tsuda, S.; Yoshida, T.; Tsutsumi, M.; Saito, K.

2015-01-01

The car-borne survey system KURAMA-II, developed by the Kyoto University Research Reactor Institute, has been used for air dose rate mapping after the Fukushima Dai-ichi Nuclear Power Plant accident. KURAMA-II consists of a CsI(Tl) scintillation detector, a GPS device, and a control device for data processing. The dose rates monitored by KURAMA-II are based on the G(E) function (spectrum-dose conversion operator), which can precisely calculate dose rates from measured pulse-height distribution even if the energy spectrum changes significantly. The characteristics of KURAMA-II have been investigated with particular consideration to the reliability of the calculated G(E) function, dose rate dependence, statistical fluctuation, angular dependence, and energy dependence. The results indicate that 100 units of KURAMA-II systems have acceptable quality for mass monitoring of dose rates in the environment. - Highlights: • KURAMA-II is a car-borne survey system developed by Kyoto University. • A spectrum-dose conversion operator for KURAMA-II was calculated and examined. • We examined the radiation characteristics of KURAMA-II such as energy dependence. • KURAMA-II has acceptable quality for environmental mass dose rate monitoring

Plant Growth and Development: An Outline for a Unit Structured Around the Life Cycle of Rapid-Cycling Brassica Rapa.

Science.gov (United States)

Becker, Wayne M.

This outline is intended for use in a unit of 10-12 lectures on plant growth and development at the introductory undergraduate level as part of a course on organismal biology. The series of lecture outlines is structured around the life cycle of rapid-cycling Brassica rapa (RCBr). The unit begins with three introductory lectures on general plant…

Startup of Pumping Units in Process Water Supplies with Cooling Towers at Thermal and Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Berlin, V. V., E-mail: vberlin@rinet.ru; Murav’ev, O. A., E-mail: muraviov1954@mail.ru; Golubev, A. V., E-mail: electronik@inbox.ru [National Research University “Moscow State University of Civil Engineering,” (Russian Federation)

2017-03-15

Aspects of the startup of pumping units in the cooling and process water supply systems for thermal and nuclear power plants with cooling towers, the startup stages, and the limits imposed on the extreme parameters during transients are discussed.

Performance Evaluation of Two Different Industrial Foam Filters with LiMCA II Data

Science.gov (United States)

Syvertsen, Martin; Bao, Sarina

2015-04-01

Plant-scale filtration experiments with molten aluminum have been carried out with two different types of 10 × 10 × 2 in, 30 ppi ceramic foam filters. The filters were produced in the same production line where the only difference was the composition of the ceramic slurry used for the filter production. The inclusion contents in the aluminum melt before and after the filters were measured with two constantly running liquid metal cleanliness analyzer (LiMCA) II units. Three methods for analyzing the recorded data are presented. A significant difference in the filtration performance as function of time was found when settling of inclusions in the melt was taken into account. Statistical treatment of the time dependent LiMCA II data was performed.

Coal conversion process by the United Power Plants of Westphalia

Energy Technology Data Exchange (ETDEWEB)

1974-08-01

The coal conversion process used by the United Power Plants of Westphalia and its possible applications are described. In this process, the crushed and predried coal is degassed and partly gasified in a gas generator, during which time the sulfur present in the coal is converted into hydrogen sulfide, which together with the carbon dioxide is subsequently washed out and possibly utilized or marketed. The residual coke together with the ashes and tar is then sent to the melting chamber of the steam generator where the ashes are removed. After desulfurization, the purified gas is fed into an external circuit and/or to a gas turbine for electricity generation. The raw gas from the gas generator can be directly used as fuel in a conventional power plant. The calorific value of the purified gas varies from 3200 to 3500 kcal/cu m. The purified gas can be used as reducing agent, heating gas, as raw material for various chemical processes, or be conveyed via pipelines to remote areas for electricity generation. The conversion process has the advantages of increased economy of electricity generation with desulfurization, of additional gas generation, and, in long-term prospects, of the use of the waste heat from high-temperature nuclear reactors for this process.

Assessment of RELAP5/MOD2 against a main feedwater turbopump trip transient in the Vandellos II Nuclear Power Plant

International Nuclear Information System (INIS)

Llopis, C.; Casals, A.; Perez, J.; Mendizabal, R.

1993-12-01

The Consejo de Seguridad Nuclear (CSN) and the Asociacion Nuclear Vandellos (ANV) have developed a model of Vandellos II Nuclear Power Plant. The ANV collaboration consisted in the supply of design and actual data, the cooperation in the simulation of the control systems and other model components, as well as in the results analysis. The obtained model has been assessed against the following transients occurred in plant: A trip from the 100% power level (CSN); a load rejection from 100% to 50% (CSN); a load rejection from 75% to 65% (ANV); and, a feedwater turbopump trip (ANV). This copy is a report of the feedwater turbopump trip transient simulation. This transient actually occurred in the plant on June 19, 1989

Quininium tetrachloridozinc(II

Directory of Open Access Journals (Sweden)

Li-Zhuang Chen

2009-10-01

Full Text Available The asymmetric unit of the title compound {systematic name: 2-[hydroxy(6-methoxyquinolin-1-ium-4-ylmethyl]-8-vinylquinuclidin-1-ium tetrachloridozinc(II}, (C20H26N2O2[ZnCl4], consists of a double protonated quininium cation and a tetrachloridozinc(II anion. The ZnII ion is in a slightly distorted tetrahedral coordination environment. The crystal structure is stabilized by intermolecular N—H...Cl and O—H...Cl hydrogen bonds.

Mobility problems at the KNK II shut-down systems, cause investigations and valuation in comparison with the experience at other plants

International Nuclear Information System (INIS)

Hess, B.

1992-12-01

During the operation of the second core of the fast test reactor KNK II the shutdown systems showed repeatedly problems with their mobility, which also caused to be reported events. The present report gives a summary description of the events in chronological order. The investigations to remove the mobility problems and the resulting design modifications are described together with the comments of the licensing authorities on the way to the restart of the plant. The results of the post-irradiation investigations in the hot cells and of sodium-chemical investigations are also described. In addition to the comparison of the events at the KNK plant itself and a review of the experiences at comparable plants it will be shown that all known cases of mobility problems did only influence the availability of the plant but that the safe shut-down of the plant was never at risk [de

78 FR 76317 - Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/Fish Screen Facility Protection...

Science.gov (United States)

2013-12-17

...-FF08RSRC00] Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/ Fish Screen Facility Protection... and Wildlife (CDFW), announce that the record of decision (ROD) for the Llano Seco Riparian Sanctuary...: www.fws.gov/refuge/sacramento river/ and http://www.riverpartners.org/where-we-work/sanctuary...

United States experience in environmental cost-benefit analysis for nuclear power plants with implications for developing countries

International Nuclear Information System (INIS)

Spangler, M.B.

1980-08-01

Environmental cost-benefit analysis in the United States involves a comparison of diverse societal impacts of the proposed developments and its alternatives. Regarding nuclear power plant licensing actions, such analyses include the need for base-load electrical generating capacity versus the no-action alternative; alternative sources of energy; alternative sites for the proposed nuclear plants; and alternative technologies for mitigating environmental impacts. Many U.S. experiences and environmental assessment practices and comparative resource requirements presented in this report will not provide a wholly reliable reflection of the precise situation of each country. Nevertheless, the procedural and substantive issues encountered by the United States in nuclear power plant licensing may exhibit a number of important, if rough, parallelisms for other countries. Procedural issues dealt with include: the scoping of alternatives and impact issues; the problem of balancing incommensurable impacts; and treating uncertainty in measuring or forecasting certain kinds of environmental impacts. Although substantive environmental impact issues will vary appreciably among nations, it is to be expected that many of the substantive impact issues such as impacts on biota, community-related effects, and aesthetic impacts will also have some measure of universal interest to other countries

Discriminatory power of rbcL barcode locus for authentication of some of United Arab Emirates (UAE) native plants.

Science.gov (United States)

Maloukh, Lina; Kumarappan, Alagappan; Jarrar, Mohammad; Salehi, Jawad; El-Wakil, Houssam; Rajya Lakshmi, T V

2017-06-01

DNA barcoding of United Arab Emirates (UAE) native plants is of high practical and scientific value as the plants adapt to very harsh environmental conditions that challenge their identification. Fifty-one plant species belonged to 22 families, 2 monocots, and 20 eudicots; a maximum number of species being legumes and grasses were collected. To authenticate the morphological identification of the wild plant taxa, rbcL and matK regions were used in the study. The primer universality and discriminatory power of rbcL is 100%, while it is 35% for matK locus for these plant species. The sequences were submitted to GenBank; accession numbers were obtained for all the rbcL sequences and for 6 of matK sequences. We suggest rbcL as a promising barcode locus for the tested group of 51 plants. In the present study, an inexpensive, simple method of identification of rare desert plant taxa through rbcL barcode is being reported.

Phase II Hydrologic Data for the Groundwater Flow and Contaminant Transport Model of Corrective Action Unit 98: Frenchman Flat, Nye County, Nevada, Rev. No.: 0

Energy Technology Data Exchange (ETDEWEB)

John McCord

2004-12-01

This report documents pertinent hydrologic data and data analyses as part of the Phase II Corrective Action Investigation (CAI) for Frenchman Flat (FF) Corrective Action Unit (CAU): CAU 98. The purpose of this data compilation and related analyses is to provide the primary reference to support the development of the Phase II FF CAU groundwater flow model.

EBR-II: twenty years of operating experience

International Nuclear Information System (INIS)

Lentz, G.L.; Buschman, H.W.; Smith, R.N.

1985-01-01

Experimental Breeder Reactor No. 2 (EBR-II) is an unmoderated, sodium-cooled reactor with a design power of 62.5 MWt. For the last 20 years EBR-II has operated safely, has demonstrated stable operating characteristics, has shown excellent performance of its sodium components, and has had an excellent plant factor. These years of operating experience provide a valuable resource to the nuclear community for the development and design of future liquid metal fast reactors. This report provides a brief description of the EBR-II plant and its early operating experience, describes some recent problems of interest to the nuclear community, and also mentions some of the significant operating achievements of EBR-II. Finally, a few words and speculations on EBR-II's future are offered. 4 figs., 1 tab

ATWS analysis for Browns Ferry Nuclear Plant Unit 1

International Nuclear Information System (INIS)

Dallman, R.J.; Jouse, W.C.

1985-01-01

Analyses of postulated Anticipated Transients Without Scram (ATWS) were performed at the Idaho National Engineering Laboratory (INEL). The Browns Ferry Nuclear Plant Unit 1 (BFNP1) was selected as the subject of this work because of the cooperation of the Tennessee Valley Authority (TVA). The work is part of the Severe Accident Sequence Analysis (SASA) Program of the US Nuclear Regulatory Commission (NRC). A Main Steamline Isolation Valve (MSIV) closure served as the transient initiator for these analyses, which proceeded a complete failure to scram. Results from the analyses indicate that operator mitigative actions are required to prevent overpressurization of the primary containment. Uncertainties remain concerning the effectiveness of key mitigative actions. The effectiveness of level control as a power reduction procedure is limited. Power level resulting from level control only reduce the Pressure Suppression Pool (PSP) heatup rate from 6 to 4 0 F/min

Strategy of plant concept development in Hitachi

International Nuclear Information System (INIS)

Kumiaki, Moriya

2007-01-01

Hitachi contributes to the society in various fields of nuclear power such as the Light Water Reactor field, the Fast Breeder Reactor, the fuel cycle, and the medical treatment. Since the beginning of a first commercial operation of a BWR in Japan, Hitachi has constructed 20 units of BWR. Hitachi continues its efforts in achieving high reliability and large-scale output, and in 1996, it completed Advanced Boiling Water Reactor (ABWR) in cooperation with various BWR utilities, General Electric Company, and Toshiba Corporation. Hitachi has enhanced the ABWR technology further based on the above enough experience. The latest technologies were reflected in Hamaoka unit 5 and Shika unit 2 as the latest ABWR plants. The further upgrade technologies would been reflected in Shimane-3, Ohma-1 and Higashidori-1 as ABWR plants under planning. Hitachi obtains the chance to construct the nuclear power plant continuously. For the next generation, Hitachi is working on developing nuclear power plants that take diversified needs and global characteristics into account. As one of the approaches, the output series formation of BWR is extended as the following. ABWR-II and ESBWR (Economic and Simplified BWR) as a large-scale centralized power supply emphasizing cost efficiency, Medium size ABWR and natural circulation type BWR as medium and small-scale distributed power supply that features flexibility to various market needs, such as minimized capital risks, timely return on a capital investment, etc. As another approach, Hitachi tries to extend the Light Water Reactor technology. RBWR (Resource-Renewable BWR ) that achieves a high conversion ratio over 1.0 based on the BWR technology will make the fuel cycle flexible. Hitachi will continue the challenge for the next ABWR and the future with the enough experience of BWR construction. (author)

Development and installation of a new on-line plant safety monitoring system for the Paks VVER-440 units

International Nuclear Information System (INIS)

Vegh, J.; Major, C.; Buerger, L.; Lipcsei, S.; Horvath, C.; Kapocs, G.; Eiler, J.; Hornaes, A.; Hulsund, J.E.

2000-01-01

The paper describes the architecture, modules, algorithms and human-machine interface of a new operator support system (OSS), which is integrated into the new, reconstructed Paks NPP plant computers. The main task of the new OSS is to perform continuous plant safety monitoring and assessment, it has the following basic functions: on-line evaluation and presentation of critical safety function (CSF) status trees, continuous evaluation and presentation of the actual safety status of the plant, displaying and browsing the new symptom-oriented EOPs, automatic displaying of those process signals which are quoted in the EOPs. The first version of the new operator support system was connected to the Paks NPP full scope simulator in October 1999. This configuration was later successfully applied for the simulator testing of the new symptom-oriented EOP set for the Paks NPP in November 1999. The installation process was continued in 2000: the new system started its operation on Unit 2 (June) and on Unit 1 (August), together with the reconstructed, new PCS. (author)

Design Analysis of Power Extracting Unit of an Onshore OWC Based Wave Energy Power Plant using Numerical Simulation

Directory of Open Access Journals (Sweden)

Zahid Suleman

2011-07-01

Full Text Available This research paper describes design and analysis of power extracting unit of an onshore OWC (Oscillating Water Column based wave energy power plant of capacity about 100 kilowatts. The OWC is modeled as solid piston of a reciprocating pump. The power extracting unit is designed analytically by using the theory of reciprocating pumps and principles of fluid mechanics. Pro-E and ANSYS workbench softwares are used to verify the analytical design. The analytical results of the flow velocity in the turbine duct are compared with the simulation results. The results are found to be in good agreement with each other. The results achieved by this research would finally assist in the overall design of the power plant which is the ultimate goal of this research work.

Potential advantages and disadvantages of sequentially building small nuclear units instead of a large nuclear plant

International Nuclear Information System (INIS)

Feretic, D.; Cavlina, N.; Grgic, D.

2008-01-01

Renewal of nuclear power programs in countries with modest electricity consumptions and weak electrical grid interconnections has raised the question of optimal nuclear power plants sizes for such countries. The same question would be also valid for isolated or weakly connected regions within a large country. Building large size nuclear power plant could be prevented by technical or financial limits. Research programs have been initiated in the International Atomic Energy Agency and in the USA (within the framework of the Global Nuclear Energy Partnership (GNEP) program) with the aim to inspect under which circumstances small and medium reactors could be the preferred option compared to large nuclear plants. The economy of scale is a clear advantage of large plants. This paper compares, by using probabilistic methods, the net cash flow of large and medium size plants, taking as example a large nuclear plant (around 1200 MW) and four sequentially built smaller plants (300 MW). Potential advantages and disadvantageous of both options have been considered. Main advantages of the sequential construction of several identical small units could be the reduced investor risk and reduced investment costs due to the learning effect. This analysis is a part of studies for the Croatian power generating system development. (orig.)

Nuclear power in the United States

International Nuclear Information System (INIS)

Johnston, J.B.

1985-01-01

All over the world except in the United States, nuclear energy is a low cost, secure, environmentally acceptable form of energy. In the United States, civilian nuclear power is dead. 112 nuclear power plants have been abandoned or cancelled in the last decade, and there has been no new order for nuclear plants since 1978. It will be fortunate to have 125 operating nuclear plants in the United States in the year 2000. There are almost 90 completed nuclear power plants and about 45 under construction in the United States, but several of those under construction will eventually be abandoned. About 20 % of the electricity in the United States will be generated by nuclear plants in 2000 as compared with 13 % supplied in the last year. Under the present regulatory and institutional arrangement, American electric utilities would not consider to order a new nuclear power plant. Post-TMI nuclear plants became very expensive, and there is also ideological opposition to nuclear power. Coal-firing plants are also in the similar situation. The uncertainty about electric power demand, the cost of money, the inflation of construction cost and regulation caused the situation. (Kako, I.)

A Novel Approach for the Removal of Lead(II Ion from Wastewater Using Mucilaginous Leaves of Diceriocaryum eriocarpum Plant

Directory of Open Access Journals (Sweden)

Joshua N. Edokpayi

2015-10-01

Full Text Available Lead(II ion is a very toxic element known to cause detrimental effects to human health even at very low concentrations. An adsorbent prepared using mucilaginous leaves from Diceriocaryum eriocarpum plant (DEP was used for the adsorption of lead(II ion from aqueous solution. Batch experiments were performed on simulated aqueous solutions under optimized conditions of adsorbent dosage, contact time, pH and initial lead(II ion concentration at 298 K. The Langmuir isotherm model more suitably described the adsorption process than the Freundlich model with linearized coefficients of 0.9661 and 0.9547, respectively. Pseudo-second order kinetic equation best described the kinetics of the reaction. Fourier transform infra-red analysis confirmed the presence of amino (–NH, carbonyl (–C=O and hydroxyl (–OH functional groups. Application of the prepared adsorbent to wastewater samples of 10 mg/L and 12 mg/L of lead(II ion concentration taken from a waste stabilization pond showed removal efficiencies of 95.8% and 96.4%, respectively. Futhermore, 0.1 M HCl was a better desorbing agent than 0.1 M NaOH and de-ionized water. The experimental data obtained demonstrated that mucilaginous leaves from DEP can be used as a suitable adsorbent for lead(II ion removal from wastewater.

Study Improving Performance of Centrifugal Compressor In Paiton Coal Fired Power Plant Unit 1 And 2

Science.gov (United States)

Kusuma, Yuriadi; Permana, Dadang S.

2018-03-01

The compressed air system becomes part of a very important utility system in a Plant, including the Steam Power Plant. In PLN’S coal fired power plant, Paiton units 1 and 2, there are four Centrifugal air compressor types, which produce compressed air as much as 5.652 cfm and with electric power capacity of 1200 kW. Electricity consumption to operate centrifugal compressor is 7.104.117 kWh per year. This study aims to measure the performance of Centrifugal Compressors operating in Paiton’s coal fired power plant units 1 and 2. Performance Compressor is expressed by Specific Power Consumption (SPC) in kW/100 cfm. For this purpose, we measure the compressed air flow rate generated by each compressor and the power consumed by each compressor. The result is as follows Air Compressor SAC 2B : 15.1 kW/100 cfm, Air Compressor SAC 1B : 15.31 kW/100 cfm,Air Compressor SAC 1A : 16.3 kW/100 cfm and air Compressor SAC 2C : 18.19 kW/100 cfm. From the measurement result, air compressor SAC 2B has the best performance that is 15.1 kW / 100 cfm. In this study we analyze efforts to improve the performance of other compressors to at least match the performance of the SAC 2B air compressor. By increasing the Specific Power Consumption from others Compressor, it will get energy saving up to 284,165 kWh per year.

System modeling and simulation at EBR-II

International Nuclear Information System (INIS)

Dean, E.M.; Lehto, W.K.; Larson, H.A.

1986-01-01

The codes being developed and verified using EBR-II data are the NATDEMO, DSNP and CSYRED. NATDEMO is a variation of the Westinghouse DEMO code coupled to the NATCON code previously used to simulate perturbations of reactor flow and inlet temperature and loss-of-flow transients leading to natural convection in EBR-II. CSYRED uses the Continuous System Modeling Program (CSMP) to simulate the EBR-II core, including power, temperature, control-rod movement reactivity effects and flow and is used primarily to model reactivity induced power transients. The Dynamic Simulator for Nuclear Power Plants (DSNP) allows a whole plant, thermal-hydraulic simulation using specific component and system models called from libraries. It has been used to simulate flow coastdown transients, reactivity insertion events and balance-of-plant perturbations

Baseline risk assessment for groundwater operable units at the Chemical Plant Area and the Ordnance Works Area, Weldon Spring, Missouri

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-14

The U.S. Department of Energy (DOE) and the U.S. Department of the Army (DA) are evaluating conditions in groundwater and springs at the DOE chemical plant area and the DA ordnance works area near Weldon Spring, Missouri. The two areas are located in St. Charles County, about 48 km (30 mi) west of St. Louis. The 88-ha (217-acre) chemical plant area is chemically and radioactively contaminated as a result of uranium-processing activities conducted by the U.S. Atomic Energy Commission in the 1950s and 1960s and explosives-production activities conducted by the U.S. Army (Army) in the 1940s. The 6,974-ha (17,232-acre) ordnance works area is primarily chemically contaminated as a result of trinitrotoluene (TNT) and dinitrotoluene (DNT) manufacturing activities during World War II. This baseline risk assessment (BRA) is being conducted as part of the remedial investigation/feasibility study (RUFS) required under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980, as amended. The purpose of the BRA is to evaluate potential human health and ecological impacts from contamination associated with the groundwater operable units (GWOUs) of the chemical plant area and ordnance works area. An RI/FS work plan issued jointly in 1995 by the DOE and DA (DOE 1995) analyzed existing conditions at the GWOUs. The work plan included a conceptual hydrogeological model based on data available when the report was prepared; this model indicated that the aquifer of concern is common to both areas. Hence, to optimize further data collection and interpretation efforts, the DOE and DA have decided to conduct a joint RI/BRA. Characterization data obtained from the chemical plant area wells indicate that uranium is present at levels slightly higher than background, with a few concentrations exceeding the proposed U.S. Environmental Protection Agency (EPA) maximum contaminant level (MCL) of 20 {micro}g/L (EPA 1996c). Concentrations of other radionuclides (e

A comparative thermodynamic, economic and risk analysis concerning implementation of oxy-combustion power plants integrated with cryogenic and hybrid air separation units

International Nuclear Information System (INIS)

Skorek-Osikowska, Anna; Bartela, Łukasz; Kotowicz, Janusz

2015-01-01

Highlights: • Mathematical model of an integrated oxy-combustion power plant. • Comparison of a hybrid membrane–cryogenic oxygen generation plant with a cryogenic plant. • Thermodynamic analysis of the modeled cases of the plant. • Comparative economic analysis of the power plant with cryogenic and hybrid ASU. • Comparative risk analysis using a Monte Carlo method and sensitivity analysis. - Abstract: This paper presents a comparison of two types of oxy-combustion power plant that differ from each other in terms of the method of oxygen separation. For the purpose of the analysis, detailed thermodynamic models of oxy-fuel power plants with gross power of approximately 460 MW were built. In the first variant (Case 1), the plant is integrated with a cryogenic air separation unit (ASU). In the second variant (Case 2), the plant is integrated with a hybrid membrane–cryogenic installation. The models were built and optimized using the GateCycle, Aspen Plus and Aspen Custom Modeller software packages and with the use of our own computational codes. The results of the thermodynamic evaluation of the systems, which primarily uses indicators such as the auxiliary power and efficiencies of the whole system and of the individual components that constitute the unit, are presented. Better plant performance is observed for Case 2, which has a net efficiency of electricity generation that is 1.1 percentage points greater than that of Case 1. For the selected structure of the system, an economic analysis of the solutions was made. This analysis accounts for different scenarios of the functioning of the Emission Trading Scheme and includes detailed estimates of the investment costs in both cases. As an indicator of profitability, the break-even price of electricity was used primarily. The results of the analysis for the assumptions made are presented in this paper. A system with a hybrid air separation unit has slightly better economic performance. The break-even price

Unit operations used to treat process and/or waste streams at nuclear power plants

International Nuclear Information System (INIS)

Godbee, H.W.; Kibbey, A.H.

1980-01-01

Estimates are given of the annual amounts of each generic type of LLW [i.e., Government and commerical (fuel cycle and non-fuel cycle)] that is generated at LWR plants. Many different chemical engineering unit operations used to treat process and/or waste streams at LWR plants include adsorption, evaporation, calcination, centrifugation, compaction, crystallization, drying, filtration, incineration, reverse osmosis, and solidification of waste residues. The treatment of these various streams and the secondary wet solid wastes thus generated is described. The various treatment options for concentrates or solid wet wastes, and for dry wastes are discussed. Among the dry waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting and shredding. Organic materials [liquids (e.g., oils or solvents) and/or solids], could be incinerated in most cases. The filter sludges, spent resins, and concentrated liquids (e.g., evaporator concentrates) are usually solidified in cement, or urea-formaldehyde or unsaturated polyester resins prior to burial. Incinerator ashes can also be incorporated in these binding agents. Asphalt has not yet been used. This paper presents a brief survey of operational experience at LWRs with various unit operations, including a short discussion of problems and some observations on recent trends

Systematic evaluation program review of NRC Safety Topic VI-10.A associated with the electrical, instrumentation and control portions of the testing of reactor trip system and engineered safety features, including response time for the Dresden station, Unit II nuclear power plant

International Nuclear Information System (INIS)

St Leger-Barter, G.

1980-11-01

This report documents the technical evaluation and review of NRC Safety Topic VI-10.A, associated with the electrical, instrumentation, and control portions of the testing of reactor trip systems and engineered safety features including response time for the Dresden II nuclear power plant, using current licensing criteria

No universal scale-dependent impacts of invasive species on native plant species richness.

Science.gov (United States)

Stohlgren, Thomas J; Rejmánek, Marcel

2014-01-01

A growing number of studies seeking generalizations about the impact of plant invasions compare heavily invaded sites to uninvaded sites. But does this approach warrant any generalizations? Using two large datasets from forests, grasslands and desert ecosystems across the conterminous United States, we show that (i) a continuum of invasion impacts exists in many biomes and (ii) many possible species-area relationships may emerge reflecting a wide range of patterns of co-occurrence of native and alien plant species. Our results contradict a smaller recent study by Powell et al. 2013 (Science 339, 316-318. (doi:10.1126/science.1226817)), who compared heavily invaded and uninvaded sites in three biomes and concluded that plant communities invaded by non-native plant species generally have lower local richness (intercepts of log species richness-log area regression lines) but steeper species accumulation with increasing area (slopes of the regression lines) than do uninvaded communities. We conclude that the impacts of plant invasions on plant species richness are not universal.

The Argentine nuclear policy: evaluation and proposals of the National Atomic Energy Commission. Privatization of the nuclear power plants and the situation of Atucha II. Addendum 1

International Nuclear Information System (INIS)

2001-01-01

An analysis is made of the possible privatization of the nuclear power plants in Argentina. The urgent definition of a nuclear policy for the short, medium and long term is strongly recommended to the Government together with the conclusion of the construction of the Atucha II nuclear power plant

Phase II Contaminant Transport Parameters for the Groundwater Flow and Contaminant Transport Model of Corrective Action Unit 98: Frenchman Flat, Nye County, Nevada, Rev. No.: 0

Energy Technology Data Exchange (ETDEWEB)

DeNovio, Nicole M.; Bryant, Nathan; King, Chrissi B.; Bhark, Eric; Drellack, Sigmund L.; Pickens, John F.; Farnham, Irene; Brooks, Keely M.; Reimus, Paul; Aly, Alaa

2005-04-01

This report documents pertinent transport data and data analyses as part of the Phase II Corrective Action Investigation (CAI) for Frenchman Flat (FF) Corrective Action Unit (CAU) 98. The purpose of this data compilation and related analyses is to provide the primary reference to support parameterization of the Phase II FF CAU transport model.

Enhancement of organizational resilience in light of the Fukushima Dai-ichi Nuclear Power Plant accident (4). Consideration of nurturing attitude to achieve the safety-II

International Nuclear Information System (INIS)

Oba, Kyoko; Yoshizawa, Atsufumi; Kitamura, Masaharu

2015-01-01

The Fukushima nuclear plant accident has been examined aiming at clarifying the factors influencing responding which is one of the four cornerstones of resilience engineering. Among the causal factors of responding, such as attitude, skill, health and environment, particular attention has been paid on the role of attitude. In addition, the case of Tokai Dai-ni nuclear plant, which was the success case despite tsunami attack, and the case of Fukushima Dai-ichi nuclear plant have been examined focusing on preparatory actions taken prior to the tsunami attack. Through the comparative examinations, attitudes of several kinds have been identified as key factors contributing to enhance organizational resilience. Moreover, the importance of safety-II concept proposed in conjunction with the methodology of resilience engineering has been clearly exemplified. As a whole, it can be concluded that the methodology of resilience engineering and the concept of safety-II are quite effective when utilized with the structured model. (author)

76 FR 66333 - Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental...

Science.gov (United States)

2011-10-26

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2011-0247] Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental Assessment and Finding of No Significant... Facility Operating License No. DPR-23, issued to Carolina Power & Light Company (the licensee), for...

Radiation protection for repairs of reactor's internals at the 2nd Unit of the Nuclear Power Plant Temelin

International Nuclear Information System (INIS)

Zapletal, P.; Konop, R.; Koc, J.; Kvasnicka, O.; Hort, M.

2011-01-01

This presentation describes the process and extent of repairs of the 2 nd unit of the Nuclear power plant Temelin during the shutdown of the reactor. All works were optimized in terms of radiation protection of workers.

Germanium Does Not Substitute for Boron in Cross-Linking of Rhamnogalacturonan II in Pumpkin Cell Walls1

Science.gov (United States)

Ishii, Tadashi; Matsunaga, Toshiro; Iwai, Hiroaki; Satoh, Shinobu; Taoshita, Junji

2002-01-01

Boron (B)-deficient pumpkin (Cucurbita moschata Duchesne) plants exhibit reduced growth, and their tissues are brittle. The leaf cell walls of these plants contain less than one-half the amount of borate cross-linked rhamnogalacturonan II (RG-II) dimer than normal plants. Supplying germanium (Ge), which has been reported to substitute for B, to B-deficient plants does not restore growth or reduce tissue brittleness. Nevertheless, the leaf cell walls of the Ge-treated plants accumulated considerable amounts of Ge. Dimeric RG-II (dRG-II) accounted for between 20% and 35% of the total RG-II in the cell walls of the second to fourth leaves from Ge-treated plants, but only 2% to 7% of the RG-II was cross-linked by germanate (dRG-II-Ge). The ability of RG-II to form a dimer is not reduced by Ge treatment because approximately 95% of the monomeric RG-II generated from the walls of Ge-treated plants is converted to dRG-II-Ge in vitro in the presence of germanium oxide and lead acetate. However, dRG-II-Ge is unstable and is converted to monomeric RG-II when the Ge is removed. Therefore, the content of dRG-II-Ge and dRG-II-B described above may not reflect the actual ratio of these in muro. 10B-Enriched boric acid and Ge are incorporated into the cell wall within 10 min after their foliar application to B-deficient plants. Foliar application of 10B but not Ge results in an increase in the proportion of dRG-II in the leaf cell wall. Taken together, our results suggest that Ge does not restore the growth of B-deficient plants. PMID:12481079

A CRM domain protein functions dually in group I and group II intron splicing in land plant chloroplasts.

Science.gov (United States)

Asakura, Yukari; Barkan, Alice

2007-12-01

The CRM domain is a recently recognized RNA binding domain found in three group II intron splicing factors in chloroplasts, in a bacterial protein that associates with ribosome precursors, and in a family of uncharacterized proteins in plants. To elucidate the functional repertoire of proteins with CRM domains, we studied CFM2 (for CRM Family Member 2), which harbors four CRM domains. RNA coimmunoprecipitation assays showed that CFM2 in maize (Zea mays) chloroplasts is associated with the group I intron in pre-trnL-UAA and group II introns in the ndhA and ycf3 pre-mRNAs. T-DNA insertions in the Arabidopsis thaliana ortholog condition a defective-seed phenotype (strong allele) or chlorophyll-deficient seedlings with impaired splicing of the trnL group I intron and the ndhA, ycf3-int1, and clpP-int2 group II introns (weak alleles). CFM2 and two previously described CRM proteins are bound simultaneously to the ndhA and ycf3-int1 introns and act in a nonredundant fashion to promote their splicing. With these findings, CRM domain proteins are implicated in the activities of three classes of catalytic RNA: group I introns, group II introns, and 23S rRNA.

PIP-II Cryogenic System and the evolution of Superfluid Helium Cryogenic Plant Specifications

Energy Technology Data Exchange (ETDEWEB)

Chakravarty, Anindya [Fermilab; Rane, Tejas [Fermilab; Klebaner, Arkadiy [Fermilab

2017-07-06

The PIP-II cryogenic system consists of a Superfluid Helium Cryogenic Plant (SHCP) and a Cryogenic Distribution System (CDS) connecting the SHCP to the Superconducting (SC) Linac consisting of 25 cryomodules. The dynamic heat load of the SC cavities for continuous wave (CW) as well as pulsed mode of operation has been listed out. The static heat loads of the cavities along with the CDS have also been discussed. Simulation study has been carried out to compute the supercritical helium (SHe) flow requirements for each cryomodule. Comparison between the flow requirements of the cryomodules for the CW and pulsed modes of operation have also been made. From the total computed heat load and pressure drop values in the CDS, the basic specifications for the SHCP, required for cooling the SC Linac, have evolved.

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-08-01

In the Quarterly Reports on the operation of the Finnish nuclear power plants such events and observations are described relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The report also includes a summary of the radiation safety of the plants' workers and the environment, as well as tabulated data on the production and load factors of the plants. The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in commercial operation during the whole first quarter of 1991. The load factor average was 99.1 %. Failures have been detected in the uppermost spacing lattices of nuclear fuel bundles removed from the Loviisa nuclear reactors. Further investigations into the significance of the failures have been initiated. In this quarter, renewed cooling systems for the instrumentation area were introduced at Loviisa 1. The modifications made in the systems serve to ensure reliable cooling of the area even during the hottest summer months when the possibility exists that the temperature of the automation equipment could rise too high causing malfunctions which could endanger plant safety. Occupational radiation doses and external releases of radioactivity were below prescribed limits in this quarter. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

76 FR 388 - Southern Nuclear Operating Company; Vogtle Electric Generating Plant, Unit Nos. 1 and 2; Notice...

Science.gov (United States)

2011-01-04

... Operating Company; Vogtle Electric Generating Plant, Unit Nos. 1 and 2; Notice of Consideration of Issuance... Web site http://www.regulations.gov . Because your comments will not be edited to remove any... will not edit their comments to remove any identifying or contact information, and therefore, they...

78 FR 4467 - UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3...

Science.gov (United States)

2013-01-22

... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3, Exemption 1.0 Background UniStar Nuclear Energy (UNE), on behalf of Calvert Cliffs Nuclear Project, LLC and UniStar Nuclear Operating Services...

76 FR 81994 - UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit...

Science.gov (United States)

2011-12-29

... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit 3; Exemption 1.0 Background: UniStar Nuclear Energy (UNE) submitted to the U.S. Nuclear Regulatory Commission (NRC or the Commission ) a...

Poly[triaqua(μ-butane-1,2,3,4-tetracarboxylatodicadmium(II

Directory of Open Access Journals (Sweden)

Yong-Sheng Yan

2009-12-01

Full Text Available The asymmetric unit of the title CdII coordination polymer, [Cd2(C8H6O8(H2O3]n, contains two crystallographically independent CdII cations, one-half each of two independent anionic butane-1,2,3,4-tetracarboxylate units (L and three water molecules. Both anionic units lie on inversion centers. One of the CdII ions is six-coordinated by four carboxylate O atoms from four L anions and two water O atoms in a distorted octahedral coordination environment. The other CdII ion is eight-coordinated by seven carboxylate O atoms from four L anions and one water O atom. The anionic units bridge neighboring CdII centers, forming a three-dimensional framework. O—H...O hydrogen-bonding interactions between the water molecules and carboxylate O atoms further stabilize the structure.

High accuracy attitude reference stabilization and pointing using the Teledyne SDG-5 gyro and the DRIRU II inertial reference unit

Science.gov (United States)

Green, K. N.; van Alstine, R. L.

This paper presents the current performance levels of the SDG-5 gyro, a high performance two-axis dynamically tuned gyro, and the DRIRU II redundant inertial reference unit relating to stabilization and pointing applications. Also presented is a discussion of a product improvement program aimed at further noise reductions to meet the demanding requirements of future space defense applications.

Final environmental statement. Final addendum to Part II: Manufacture of floating nuclear power plants by Offshore Power Systems. DOCKET-STN--50-437

International Nuclear Information System (INIS)

1978-06-01

This Addendum to Part II of the Final Environmental Statement related to manufacture of floating nuclear power plants by Offshore Power Systems (OPS), NUREG-0056, issued September 1976, was prepared by the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation. The staff's basic evaluation is presented in NUREG-0056. The current Addendum provides further consideration of a number of topics discussed in NUREG-0056, particularly additional consideration of shore zone siting at estuarine and ocean regions. This Summary and Conclusions recapitulates and is cumulative for Part II of the FES and the current Addendum. Augmentations to the Summary and Conclusions presented in Part II of the FES and arising from the evaluations contained in this Addendum are italicized

Interagency partnering for weed prevention--progress on development of a National Early Detection and Rapid Response System for Invasive Plants in the United States

Science.gov (United States)

Westbrooks, R.; Westbrooks, R.

2011-01-01

Over the past 50 years, experience has shown that interagency groups provide an effective forum for addressing various invasive species issues and challenges on multiple land units. However, more importantly, they can also provide a coordinated framework for early detection, reporting, identification and vouchering, rapid assessment, and rapid response to new and emerging invasive plants in the United States. Interagency collaboration maximizes the use of available expertise, resources, and authority for promoting early detection and rapid response (EDRR) as the preferred management option for addressing new and emerging invasive plants. Currently, an interagency effort is underway to develop a National EDRR System for Invasive Plants in the United States. The proposed system will include structural and informational elements. Structural elements of the system include a network of interagency partner groups to facilitate early detection and rapid response to new invasive plants, including the Federal Interagency Committee for the Management of Noxious and Exotic Weeds (FICMNEW), State Invasive Species Councils, State Early Detection and Rapid Response Coordinating Committees, State Volunteer Detection and Reporting Networks, Invasive Plant Task Forces, and Cooperative Weed Management Areas. Informational elements and products being developed include Regional Invasive Plant Atlases, and EDRR Guidelines for EDRR Volunteer Network Training, Rapid Assessment and Rapid Response, and Criteria for Selection of EDRR Species. System science and technical support elements which are provided by cooperating state and federal scientists, include EDRR guidelines, training curriculum for EDRR volunteers and agency field personnel, plant identification and vouchering, rapid assessments, as well as predictive modeling and ecological range studies for invasive plant species.

Evaluation of external hazards to nuclear power plants in the United States

International Nuclear Information System (INIS)

Kimura, C.Y.; Budnitz, R.J.

1987-12-01

The Lawrence Livermore National Laboratory (LLNL) has performed a study of the risk of core damage to nuclear power plants in the United States due to externally initiated events. The broad objective has been to gain an understanding of whether or not each external initiator is among the major potential accident initiators that may pose a threat of severe reactor core damage or of large radioactive release to the environment from the reactor. Four external hazards were investigated in this report. These external hazards are internal fires, high winds/tornadoes, external floods, and transportation accidents. Analysis was based on two figures-of-merit, one based on core damage frequency and the other based on the frequency of large radioactive releases. Using these two figures-of-merit as evaluation criteria, it has been feasible to ascertain whether the risk from externally initiated accidents is, or is not, an important contributor to overall risk for the US nuclear power plants studied. This has been accomplished for each initiator separately. 208 refs., 17 figs., 45 tabs

Preparation for decommissioning of the Kozloduy Nuclear Power Plant units 1 and 2

International Nuclear Information System (INIS)

Delcheva, T.; Ribarski, V.; Demireva, E.

2006-01-01

The first decommissioning strategy of units 1 and 2 of Kozloduy NPP (KNPP) stipulated 3 phases: a 5 year phase including the post operation activities and preparation of the safe enclosure (SE); a 35 years SE period, followed by deferred dismantling. 'Updated Decommissioning Strategy for Units 1-4 of Kozloduy NPP' was issued in June 2006. The Updated Strategy is based on the so called 'Continuous Dismantling' Concept. The updated Strategy starts preparatory work earlier and then moves into dismantling work without a significant gap. The aim is to achieve a more optimal distribution of the dismantling activities along the time, saving jobs and the existing knowledge of the plant personnel during the decommissioning, and ensuring smooth and more effective use of financial and human resources and of the available infrastructure for waste treatment. This paper gives general information about the updated strategy and activities required for its implementation. (author)

The effects of electric power industry restructuring on the safety of nuclear power plants in the United States

Science.gov (United States)

Butler, Thomas S.

Throughout the United States the electric utility industry is restructuring in response to federal legislation mandating deregulation. The electric utility industry has embarked upon an extraordinary experiment by restructuring in response to deregulation that has been advocated on the premise of improving economic efficiency by encouraging competition in as many sectors of the industry as possible. However, unlike the telephone, trucking, and airline industries, the potential effects of electric deregulation reach far beyond simple energy economics. This dissertation presents the potential safety risks involved with the deregulation of the electric power industry in the United States and abroad. The pressures of a competitive environment on utilities with nuclear power plants in their portfolio to lower operation and maintenance costs could squeeze them to resort to some risky cost-cutting measures. These include deferring maintenance, reducing training, downsizing staff, excessive reductions in refueling down time, and increasing the use of on-line maintenance. The results of this study indicate statistically significant differences at the .01 level between the safety of pressurized water reactor nuclear power plants and boiling water reactor nuclear power plants. Boiling water reactors exhibited significantly more problems than did pressurized water reactors.

Optimization of Boiler Control to Improve the Load-following Capability of Power-plant Units

OpenAIRE

Mortensen, J. H.; Mølbak, T.; Andersen, Palle; Pedersen, Tom Søndergaard

1998-01-01

The capability to perform fast load changes has been an important issue in the power market, and will become increasingly more so due to the incresing commercialisation of the European power market. An optimizing control system for improving the load-following capability of power-plant units has therefore been developed. The system is implemented as a complement, producing control signals to be added to those of the existing boiler control system, a concept which has various practical advanta...

Sulfur gained from flue gas, a demonstration unit of the Wellman-Lord process annexed to a black coal power plant

Energy Technology Data Exchange (ETDEWEB)

Schulte, H

1977-12-16

Details of reducing air pollution by desulfurization of flue gases are presented. The demonstration unit is annexed to a 115 MW block at the Gary power plant in Indiana, USA. A second unit is being installed at the larger coal power plant in San Juan, New Mexico. The Wellman-Lord technology achieves a higher than 90% desulfurization of industrial waste gases. The technology is based on washing the gases with sodium sulfide. The resulting concentrated sulfur dioxide gas is used for pure sulfur and sulfuric acid production. Sodium sulfate is another commercial by-product obtained from the sodium sulfide regeneration cycle. Chemical details and the technological flow sheet are discussed. Electricity production costs in the power plants due to desulfurization of waste gases will increase by an estimated 15%. Advantages, in addition to reducing air pollution and marketing sulfur products, are also seen in the absence of sulfur containing wastes for disposal. (In German)

Integrated management for aging of Atucha Nuclear Power Plant

International Nuclear Information System (INIS)

Ranalli, J.M.; Marchena, M.H.; Sabransky, M.; Fonseca, M.; Santich, J.; Pedernera, P.

2012-01-01

Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina.. With the start-up of Atucha II and aiming to integrate the Ageing Management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) created an Ageing Management Department to cope with all ageing issues of both Atucha I and II. In this project both organization has formed a joint working group. The role of CNEA is providing technical support to the plant in the development of procedures a methodological framework for the Ageing Management Program of Atucha NPP. The main documents that have being issued so far are: . An Ageing Management Manual, including standard definition of Materials, Ageing Related Degradation Mechanisms, Operation Environments customized for Atucha NPP. . Walk down procedures and checklists aimed to systematize data collection during outages. . Procedures for performing Ageing Management Reviews and Maintenance Reviews for passive and active components. . Condition Assessments of several safety related systems. . Condition assessment of electrical components. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented (author)

Development of a high integrity container for storage, transportation, and disposal of radioactive wastes from Three Mile Island unit II

International Nuclear Information System (INIS)

Holzworth, R.E.; Chapman, R.L.; Burton, H.M.; Bixby, W.W.

1981-01-01

The EPICOR II ion exchange system used to decontaminate approximately 1900 m 3 of contaminated water in the Auxiliary and Fuel Handling Building (AFHB) generated 50 highly loaded and 22 lesser loaded organic resin liners. The 22 lesser loaded resins were shipped to a commercial disposal site, but the highly loaded liners have been stored on the island since their generation. One highly loaded liner, or prefilter, was shipped to Battelle Columbus Laboratories (BCL) in May, 1981 as part of the United States Department of Energy (DOE) Three Mile Island Information and Examination Program. The prefilter is being characterized to determine the behavior of the waste form with respect to time and the internal environment and to provide an information base for use in management and regulatory decisions relative to the storage, processing, and disposal of these wastes. Due to the unique characteristics of these wastes, the US DOE is sponsoring programs, such as the BCL Sorbent Experiments Program, to evaluate their characteristics and to provide a High Integrity Container (HIC) Development Program which would improve waste suitability for disposal at a land burial facility. This paper addresses regulatory considerations, establishment of design criteria, proposed design concepts, system demonstration, and status of the HIC Development Program for storage, transportation, and disposal of high specific activity, low level radioactive wastes from Three Mile Island Unit II as typified by EPICOR II ion exchange media and liners

Use of high ash fuel in diesel power plants II; Korkean tuhkapitoisuuden omaavan polttoaineen kaeyttoe dieselvoimaloissa II

Energy Technology Data Exchange (ETDEWEB)

Vestergren, R; Normen, E; Hellen, G [Wartsila Diesel International Ltd Oy, Vaasa (Finland); and others

1997-10-01

Heavy fuel oils containing a large amount of ash are used in some geographically restricted areas. The ash components can cause problems with deposit formation and hot corrosion, leading to burned exhaust gas valves in some diesel engines. The LIEKKI 2 programs Use of high ash fuel in diesel power plants, Part I and II, have been initiated to clarify the mechanisms of deposit formation, and start and propagation of hot corrosion. The aim is to get enough knowledge to enable the development of the Waertsilae diesel engines to be able to handle heavy fuels with a very high ash content. The chemistry during combustion has been studied. The chemical and physical properties of the particles in the exhaust gas, of the deposits, and of exhaust valves have been investigated. Exhaust gas particle measurements have been performed when running on high ash fuel, both with and without deposit modifying fuel additive. Theories for the mechanisms mentioned above have been developed. On the practical side two long time field tests are going on, one with an ash/deposit modifying fuel additive (vanadium chemistry alteration), one with fuel water washing (sodium removal). Seven different reports have been written. (orig.)

Sendai High Court rejects residents' appeal to nullify gov't permit for Fukushima II-1

International Nuclear Information System (INIS)

Anon.

1990-01-01

The Sendai High Court on March 20 rejected an appeal made by 33 residents in Naraha-cho, Fukushima Prefecture, to nullify the government permit for Tokyo Electric Power Co.'s plan to establish Fukushima II Nuclear Power Plant Unit 1 (1,100 MW, BWR) near their homes, upholding the Fukushima District Court's 1984 ruling that the government's examination is adequate to ensure safety of the Unit. The plaintiffs are considering taking the case to the Supreme Court. This is the first ruling on the safety of a nuclear power plant in Japan, after the Chernobyl accident in 1986. Unit 1 is currently in operation. Presiding Judge Yoshio Ishikawa approved almost entirely the government's arguments except that on the competence of the plaintiff. The judgement said that the 33 residents living within the radius of fifty and several kilometers from the reactor facilities have plaintiff competency, because if the safety of the reactor facilities could not be assured, the facilities could possibly present a grave danger to the lives and health of the residents. The ruling said that issuing the reactor installation permit was committed to the government's special technical discretion. (N.K.)

Model-based investigation of the electricity market. Unit commitment and power plant investments

International Nuclear Information System (INIS)

Sun, Ninghong

2013-01-01

The German Federal Government published its energy concept in September 2010 with a description of the road into the era of renewable energies. Therefore, the future renewable energy installed in Germany is expected to consist mostly of wind and solar, which are subject to intermittency of supply and significant fluctuations. The growing portion of energy generation by fluctuating sources is turning to a big challenge for the power plant unit commitment and the investment decisions as well. In this thesis, a fundamental electricity market model with combined modeling of these two aspects is developed. This model is subsequently applied to the German electricity market to investigate what kind of power plant investments are indispensable, considering the steadily increasing portion of energy generation from fluctuating sources, to ensure a reliable energy supply in a cost-effective way in the future. In addition, current energy policy in Germany regarding the use of renewable energy and nuclear energy is analyzed.

Baseline risk assessment for the groundwater operable units at the Chemical Plant Area and the Ordnance Works Area, Weldon Spring, Missouri

International Nuclear Information System (INIS)

1999-01-01

The U.S. Department of Energy (DOE) and the U.S. Department of the Army (DA) are evaluating conditions in groundwater and springs at the DOE chemical plant area and the DA ordnance works area near Weldon Spring, Missouri. The two areas are located in St. Charles County, about 48 km (30 mi) west of St. Louis. The 88-ha (217-acre) chemical plant area is chemically and radioactively contaminated as a result of uranium-processing activities conducted by the U.S. Atomic Energy Commission in the 1950s and 1960s and explosives-production activities conducted by the U.S. Army (Army) in the 1940s. The 6,974-ha (17,232-acre) ordnance works area is primarily chemically contaminated as a result of trinitrotoluene (TNT) and dinitrotoluene (DNT) manufacturing activities during World War II. This baseline risk assessment (BRA) is being conducted as part of the remedial investigation/feasibility study (RUFS) required under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980, as amended. The purpose of the BRA is to evaluate potential human health and ecological impacts from contamination associated with the groundwater operable units (GWOUs) of the chemical plant area and ordnance works area. An RI/FS work plan issued jointly in 1995 by the DOE and DA (DOE 1995) analyzed existing conditions at the GWOUs. The work plan included a conceptual hydrogeological model based on data available when the report was prepared; this model indicated that the aquifer of concern is common to both areas. Hence, to optimize further data collection and interpretation efforts, the DOE and DA have decided to conduct a joint RI/BRA. Characterization data obtained from the chemical plant area wells indicate that uranium is present at levels slightly higher than background, with a few concentrations exceeding the proposed U.S. Environmental Protection Agency (EPA) maximum contaminant level (MCL) of 20 microg/L (EPA 1996c). Concentrations of other radionuclides (e

Modernization programme for nuclear power plant units with VVER-1000 in Ukraine

International Nuclear Information System (INIS)

Shenderovich, V.

1997-01-01

All Ukrainian nuclear power plants with WWER type reactors are briefly described from the safety point of view. Information is given on the design and construction of the units. The main goals of upgrading are: elimination of incompliances with current safety standards, improvement of the reliability of safety significant systems, equipment and elements, and implementation of IAEA recommendations. A list of actions making up the large upgrading programme is given; it includes 181 measures to be taken. At present the measures are being designed in order to find appropriate engineering solutions, to develop technical specifications for new equipment, and to ensure precise cost estimation. (M.D.)

Implementation of a digital feedwater control system at Dresden Nuclear Power Plant, Units 2 and 3: Final report

International Nuclear Information System (INIS)

Zapotocky, A.; Popovic, J.R.; Fournier, R.D.

1988-12-01

This report describes the Digital Feedwater Control System Implementation at the Dresden 2 or 3 Units of the BWR Nuclear Power Plant owned by the Commonwealth Edison Company. The digital system has been operational in Unit 3 since August 1986, and in Unit 2 since April 1987. The Bailey Control's Network 90 based digital control system replaced the obsolete GE/MAC 5000 analog control system in the reactor feedwater control loop as a ''like-for-like'' replacement. Operational experience from the Digital Feedwater Control installations has been good and the system demonstrated better performance than the old analog systems. 14 refs., 15 figs., 17 tabs

A regulatory view of the seismic re-evaluation of existing nuclear power plants in the United Kingdom

International Nuclear Information System (INIS)

Inkester, J.E.; Bradford, P.M.

1995-01-01

The paper describes the background to the seismic re-evaluation of existing nuclear power plants in the United Kingdom. Nuclear installations in this country were not designed specifically to resist earthquakes until the nineteen-seventies, although older plants were robustly constructed. The seismic capability of these older installations is now being evaluated as part of the periodic safety reviews which nuclear licensees are required to carry out. The regulatory requirements which set the framework for these studies are explained and the approaches being adopted by the licensees for their assessment of the seismic capability of existing plants are outlined. The process of hazard appraisal is reported together with a general overview of UK seismicity. The paper then discusses the methodologies used to evaluate the response of plant to the hazard. Various other types of nuclear installation besides power plants are subject to licensing in the UK and the application of seismic evaluation to some of these is briefly described. Finally the paper provides some comments on future initiatives and possible areas of development. (author)

Regulatory application of seismic experience data for nuclear power plants in the United States

Energy Technology Data Exchange (ETDEWEB)

Chen, Pei-Ying [Nuclear Regulatory Commission, Washington, DC (United States)

1997-03-01

On the basis of its review and evaluation (Reference 3) of the SQUG GIP (Reference 2) and on the basis of the differences between current seismic qualification requirements and the criteria and procedures provided in the GIP, the NRC staff does not consider the USI A-46 methodology given in the GIP to be a `seismic qualification` procedure. Rather, the staff considers the GIP methodology to be a seismic adequacy verification procedure, which was developed on the basis of generic equipment earthquake experience data, supplemented by generic equipment test data. The implementation of the GIP approach for USI A-46 plants provides safety enhancement, in certain aspects, beyond the original licensing bases. Therefore, the GIP methodology is an acceptable evaluation method, for USI A-46 plants only, to verify the seismic adequacy of the safe-shutdown equipment installed in the NPPs in the United States. With the new development in the experience-based approach for seismic qualification of equipment currently underway in the U.S. nuclear industry, there is a potential for future regulatory application of an experience-based approach as a seismic qualification method for certain selected equipment installed in NPPs in the United States. However, industry`s use of the experience-based approach will be dependent on the submittal and staff approval of this approach. (J.P.N.)

The civil design of the Angra Nuclear power plant, units 2 and 3

International Nuclear Information System (INIS)

Zuegel, L.C.; Diaz, B.E.; Cunha, M.T.

1988-01-01

The civil design of the Angra Nuclear Power Plant, Units 2 and 3 represents an important step in the technological development of Brazil, correlated to high technology enterprises. This design was developed in Brazil, by Brazilian technicians, in a comprehensive way. In all individual and global phases of the design, a full participation of the Brazilian state and private companies has been observed. In order to proceed with the design in this way, a group of Nuclen engineers has stayed for a while in Germany, in KWU's office, for a proper training. The Brazilian design companies, on the other hand, have received a special consulting support given by engineers of German construction companies, especialized in nuclear power plant construction. For the nuclear civil design, as well as for the dynamic analyses and structural design of reinforced concrete and steel structures, the design job assumes an important position in the Brazilian technical experience. The structural design of the reinforced concrete structures of the nuclear power plant, for instance, is the largest one ever performed in Brazil in terms of difficulty, complexity and amount of man-hours expediture. A summary of the civil design steps will be described in this paper. (author) [pt

Withdrawal and consumption of water by thermoelectric power plants in the United States, 2010

Science.gov (United States)

Diehl, Timothy H.; Harris, Melissa A.

2014-01-01

Estimates of water use at thermoelectric plants were developed by the U.S. Geological Survey based on linked heat and water budgets, and complement reported thermoelectric water withdrawals and consumption. The heat- and water-budget models produced withdrawal and consumption estimates, including thermodynamically plausible ranges of minimum and maximum withdrawal and consumption, for 1,290 water-using plants in the United States for 2010. Total estimated withdrawal for 2010 was about 129 billion gallons per day (Bgal/d), and total estimated consumption was about 3.5 Bgal/d. In contrast, total withdrawal reported by the U.S. Department of Energy, Energy Information Administration (EIA), was about 24 percent higher than the modeled estimates, and total EIA-reported consumption was about 8 percent lower. Most thermoelectric generation in 2010 was not associated with thermodynamically plausible EIA-reported values of both withdrawal and consumption.

Women and Body Image in Wartime: Advertisements for Foundation Garments during World War II in the United States

OpenAIRE

板橋, 晶子

2013-01-01

This paper examines the images of women war workers in advertisements for foundation garments during World War II in the United States. In wartime America, functional underwear such as brassieres and girdles were sold as a “vital necessity” for women at work, especially those engaged in defense work. \\Advertisements for foundation garments frequently depicted women war workers who were doing man-sized jobs and lauded those women for their contribution to the war effort, and women war workers’...

76 FR 30206 - Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Unit 1 and 2; Notice...

Science.gov (United States)

2011-05-24

... Operating Company, Inc., Vogtle Electric Generating Plant, Unit 1 and 2; Notice of Consideration of Issuance..., http://www.regulations.gov . Because your comments will not be edited to remove any identifying or... received from other persons for submission to the NRC inform those persons that the NRC will not edit their...

Validation of WIMS-AECL/(MULTICELL)/RFSP system by the results of phase-B test at Wolsung-II unit

Energy Technology Data Exchange (ETDEWEB)

Hong, In Seob; Min, Byung Joo; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-03-01

The object of this study is the validation of WIMS-AECL lattice code which has been proposed for the substitution of POWDERPUFS-V(PPV) code. For the validation of this code, WIMS-AECL/(MULTICELL)/RFSP (lattice calculation/(incremental cross section calculation)/core calculation) code system has been used for the Post-Simulation of Phase-B physics Test at Wolsung-II unit. This code system had been used for the Wolsong-I and Point Lepraeu reactors, but after a few modifications of WIMS-AECL input values for Wolsong-II, the results of WIMS-AECL/RFSP code calculations are much improved to those of the old ones. Most of the results show good estimation except moderator temperature coefficient test. And the verification of this result must be done, which is one of the further work. 6 figs., 15 tabs. (Author)

Thermoeconomic cost analysis of CO_2 compression and purification unit in oxy-combustion power plants

International Nuclear Information System (INIS)

Jin, Bo; Zhao, Haibo; Zheng, Chuguang

2015-01-01

Highlights: • Thermoeconomic cost analysis for CO_2 compression and purification unit is conducted. • Exergy cost and thermoeconomic cost occur in flash separation and mixing processes. • Unit exergy costs for flash separator and multi-stream heat exchanger are identical. • Multi-stage CO_2 compressor contributes to the minimum unit exergy cost. • Thermoeconomic performance for optimized CPU is enhanced. - Abstract: High CO_2 purity products can be obtained from oxy-combustion power plants through CO_2 compression and purification unit (CPU) based on phase separation method. To identify cost formation process and potential energy savings for CPU, detailed thermoeconomic cost analysis based on structure theory of thermoeconomics is applied to an optimized CPU (with double flash separators). It is found that the largest unit exergy cost occurs in the first separation process while the multi-stage CO_2 compressor contributes to the minimum unit exergy cost. In two flash separation processes, unit exergy costs for the flash separator and multi-stream heat exchanger are identical but their unit thermoeconomic costs are different once monetary cost for each device is considered. For cost inefficiency occurring in CPU, it mainly derives from large exergy costs and thermoeconomic costs in the flash separation and mixing processes. When compared with an unoptimized CPU, thermoeconomic performance for the optimized CPU is enhanced and the maximum reduction of 5.18% for thermoeconomic cost is attained. To achieve cost effective operation, measures should be taken to improve operations of the flash separation and mixing processes.

Emergency planning requirements and short-term countermeasures for commercial nuclear power plants in the United States

International Nuclear Information System (INIS)

Kantor, F.; Hogan, R.; Mohseni, A.

1995-01-01

Since the accident at the Three Mile Island Unit, the United States Nuclear Regulatory's Commission (NRC's) emergency planning regulations are now considered and an important part of the regulatory framework for protecting the public health and safety. Many aspects of the countermeasures are presented: Emergency Planning Zones (EPZ), off-Site emergency planning and preparedness, responsibilities of nuclear power plants operators and states and local government. Finally, protective action recommendations are given as well as the federal response to an emergency. The authors noted that the use of potassium iodide is not considered as an effective countermeasure for the public protection in the US. (TEC). 1 fig

Severe Accident Sequence Analysis Program: Anticipated transient without scram simulations for Browns Ferry Nuclear Plant Unit 1

International Nuclear Information System (INIS)

Dallman, R.J.; Gottula, R.C.; Holcomb, E.E.; Jouse, W.C.; Wagoner, S.R.; Wheatley, P.D.

1987-05-01

An analysis of five anticipated transients without scram (ATWS) was conducted at the Idaho National Engineering Laboratory (INEL). The five detailed deterministic simulations of postulated ATWS sequences were initiated from a main steamline isolation valve (MSIV) closure. The subject of the analysis was the Browns Ferry Nuclear Plant Unit 1, a boiling water reactor (BWR) of the BWR/4 product line with a Mark I containment. The simulations yielded insights to the possible consequences resulting from a MSIV closure ATWS. An evaluation of the effects of plant safety systems and operator actions on accident progression and mitigation is presented

RCRA closures at Rocky Flats Plant: A programmatic perspective and case study

International Nuclear Information System (INIS)

Ogg, Randy T.; Peterman, Bruce D.

1992-01-01

The Interagency Agreement (IAG) integrates a unique mechanism for remediating hazardous waste sites at the Rocky Flats Plant (RFP), which include utilizing RCRA and CERCLA technical/regulatory processes. Pursuant to the IAG signed by the Department of Energy (DOE), Environmental Protection Agency (EPA), and the Colorado Department of Health (CDH) on January 22, 1991, sixteen operable units (OUs) were defined for characterization and remediation at RFP. Of the sixteen OUs, six are classified as Resource Conservation and Recovery Act (RCRA) closure units. The six RCRA interim status closure units are: Solar Evaporation Ponds-OU 4, Present LandfUl-OU 7, Original Process Waste Lines-OU 9, Other Outside Closures-OU 10, West Spray Field-OU II, and Inside Building Closures-OU 15. The IAG will function as a technical/regulatory mechanism for managing/complying with all aspects of the RCRA interim status closure units at RFP. (author)

Radiation hazards control activities in BARC and other DAE units in Bombay and Indore: annual report 1994

International Nuclear Information System (INIS)

Bhagwat, A.M.; Pimputkar, D.P.; Mogal, M.P.; Mehta, S.K.

1995-01-01

The radiation hazards control activities of units of Radiation Safety Systems Division stationed at different plants and facilities of Bhabha Atomic Research Centre and other units of Department of Atomic Energy in Bombay are briefly summarised. The activities are reported plantwise and include the following: (i) nature of radioactive operations, (ii) radiological status of the plant, (iii) personnel exposure data including collective and average exposures, (iv) effluent discharges, (v) waste disposal data, and (vi) safety related unusual occurrences and special problems, if any. Important operations for which extensive radiation safety surveillance was provided during the year 1994 are included. During the year 4319 persons were provided with radiation safety coverage at 25 different facilities. The collective dose and the average individual dose for the year 1994 are 6.08 man-Sv and 1.41 mSv respectively. Trends in personnel radiation exposure for a longer period i.e. from 1981 onwards are shown graphically. The figure also shows a steady trend in collective as well as average doses. The major contribution to dose comes from the following facilities: Plutonium Plant, Thorium Plant, Cirus, Radiological Laboratories and Dhruva in the decreasing order. (author). refs., tabs., 1 fig

Radiation hazards control activities in BARC and other DAE units in Bombay and Indore: annual report 1994

Energy Technology Data Exchange (ETDEWEB)

Bhagwat, A M; Pimputkar, D P; Mogal, M P; Mehta, S K [comps.; Bhabha Atomic Research Centre, Bombay (India). Radiation Safety Systems Division

1996-12-31

The radiation hazards control activities of units of Radiation Safety Systems Division stationed at different plants and facilities of Bhabha Atomic Research Centre and other units of Department of Atomic Energy in Bombay are briefly summarised. The activities are reported plantwise and include the following: (i) nature of radioactive operations, (ii) radiological status of the plant, (iii) personnel exposure data including collective and average exposures, (iv) effluent discharges, (v) waste disposal data, and (vi) safety related unusual occurrences and special problems, if any. Important operations for which extensive radiation safety surveillance was provided during the year 1994 are included. During the year 4319 persons were provided with radiation safety coverage at 25 different facilities. The collective dose and the average individual dose for the year 1994 are 6.08 man-Sv and 1.41 mSv respectively. Trends in personnel radiation exposure for a longer period i.e. from 1981 onwards are shown graphically. The figure also shows a steady trend in collective as well as average doses. The major contribution to dose comes from the following facilities: Plutonium Plant, Thorium Plant, Cirus, Radiological Laboratories and Dhruva in the decreasing order. (author). refs., tabs., 1 fig.

Implementation of the II. Stage decommissioning of A1 NPP

International Nuclear Information System (INIS)

Ficher, T.

2015-01-01

Presentation is focused on the implementation of the II. stage decommissioning of A1 NPP. Introductory part focuses on brief characteristics of the power plant with a history of operation, basic technical parameters and actions that were made after operation. The next section describes the basic schedule for decommissioning, structure of management and implementation of the II. stage decommissioning of the A1 NPP and objectives of the individual stages. The last and largest part of the presentation is devoted to detailed description of the II. stage decommissioning of the A1 NPP, its individual tasks and verbal and visual description of the activities that were performed. Presented is decommissioning of the technology and construction of external objects NPP A1 including storage tanks for liquid RAW, next are presented activities carried out in the Main Production Unit - decommissioning of non-operating technologies in various places/rooms, management of waste arising from these activities, treatment of case of A1 long-term spent fuel storage and long-term spent fuel storage. The subsequent section is devoted to the management and handling of contaminated soil, concrete and construction waste, including management of VLLW. (authors)

PACE. A Program for Acquiring Competence in Entrepreneurship. Part II: Becoming an Entrepreneur. Unit G: Resources for Managerial Assistance. Research and Development Series No. 194 B-7.

Science.gov (United States)

Ohio State Univ., Columbus. National Center for Research in Vocational Education.

This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but it can be adapted for special groups or vocational teacher education. The emphasis of the seven instructional units in Part II is establishing business. Unit G focuses on obtaining managerial…

75 FR 44292 - Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2; Notice of...

Science.gov (United States)

2010-07-28

... and DPR-60] Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2... assessment, and behavioral observation) of the unescorted access authorization program when making the... under consideration to determine whether it met the criteria established in NRC Management Directive (MD...

Disturbance and climate change in United States/Mexico borderland plant communities: a state-of-the-knowledge review

Science.gov (United States)

Guy R. McPherson; Jake F. Weltzin

2000-01-01

This review evaluates the effects and importance of disturbance and climate change on plant community dynamics in the United States/Mexico borderlands region. Our primary focus is on knowledge of physiognomic-level change in grasslands and woodlands of southeastern Arizona and southwestern New Mexico. Changes in vegetation physiognomy have broad implications for...

75 FR 16201 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption

Science.gov (United States)

2010-03-31

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-266 and 50-301; NRC-2010-0123] FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption 1.0 Background FPL Energy Point Beach.... Borchardt (NRC) to M. S. Fertel (Nuclear Energy Institute) dated June 4, 2009. The licensee's request for an...

Analysis of thermodynamics of two-fuel power unit integrated with a carbon dioxide separation plant

Directory of Open Access Journals (Sweden)

Kotowicz Janusz

2014-12-01

Full Text Available The article presents the results of thermodynamic analysis of the supercritical coal-fired power plant with gross electrical output of 900 MW and a pulverized coal boiler. This unit is integrated with the absorption-based CO2 separation installation. The heat required for carrying out the desorption process, is supplied by the system with the gas turbine. Analyses were performed for two variants of the system. In the first case, in addition to the gas turbine there is an evaporator powered by exhaust gases from the gas turbine expander. The second expanded variant assumes the application of gas turbine combined cycle with heat recovery steam generator and backpressure steam turbine. The way of determining the efficiency of electricity generation and other defined indicators to assess the energy performance of the test block was showed. The size of the gas turbine system was chosen because of the need for heat for the desorption unit, taking the value of the heat demand 4 MJ/kg CO2. The analysis results obtained for the both variants of the installation with integrated CO2 separation plant were compared with the results of the analysis of the block where the separation is not conducted.

Recommended criteria for the evaluation of on-site nuclear power plant emergency plans, volume II: criteria

International Nuclear Information System (INIS)

1997-01-01

A critical review of existing Canadian and international nuclear power plant (NPP) emergency plans, evaluation criteria, and approaches has been conducted to provide AECB staff with information which can be used to assess the adequacy of NPP on-site emergency response plans. The results of this work are published in two volumes. Volume I, Basis Document, provides the reasons why certain requirements are in place. It also gives comprehensive references to various standards.Volume II, Criteria, contains the criteria which relate to on-site actions and their integration with control room activities and the roles of off-site responsible organizations. The recommended criteria provide information on what is required, and not on how to accomplish the requirements. The licensees are given the latitude to decide on the methods and processes needed to meet the requirements. The documents do not address NPP off-site plans and response capability, or the control room emergency operating procedures and response capability. This report contains only Volume II: Criteria. 55 refs., 2 tabs., 1 fig

Radiology in World War II (Medical Department, United States Army)

Science.gov (United States)

1966-01-01

efornied each wvorkinog dav. bv a roil utie dlevelopied lo1 expiediite till(- elir . t8 ii~ap .11id ~iieiui’iie~hiiloi’ij~i were. facil itated by thle...ETOUSA. The officer sent to the European theater as Chief of Redeployment, a pharmacist by training, made arbitrary decisions on matters in which he was...lgt44 f.4t. wL*r ithi1l14’iI that lo4,keli tiks, pilorlen e-xuldite bill thant wals found14 ote il411’ uti r After f1’,lebidelo’ilt. I cavit v 1II4

Assessment of severe accident prevention and mitigation features: BWR, Mark II containment design

International Nuclear Information System (INIS)

Lehner, J.R.; Hsu, C.J.; Eltawila, F.; Perkins, K.R.; Luckas, W.J.; Fitzpatrick, R.G.; Pratt, W.T.

1988-07-01

Plant features and operator actions, which have been found to be important in either preventing or mitigating severe accidents in BWRs with Mark II containments (BWR Mark II's) have been identified. These features and actions were developed from insights derived from reviews of in-depth risk assessments performed specifically for the Limerick and Shoreham plants and from other relevant studies. Accident sequences that dominate the core-damage frequency and those accident sequences that are of potentially high consequence were identified. Vulnerabilities of the BWR Mark II to severe-accident containment loads were also noted. In addition, those features of a BWR Mark II, which are important for preventing core damage and are available for mitigating fission-product release to the environment were also identified. This report is issued to provide focus to an analyst examining an individual plant. This report calls attention to plant features and operator actions and provides a list of deterministic attributes for assessing those features and actions found to be helpful in reducing the overall risk for Mark II plants. Thus, the guidance is offered as a resource in examining the subject plant to determine if the same, or similar, plant features and operator actions will be of value in reducing overall plant risk. This report is intended to serve solely as guidance

PACE. A Program for Acquiring Competence in Entrepreneurship. Part II: Becoming an Entrepreneur. Unit A: Developing the Business Plan. Research and Development Series No. 194 B-1.

Science.gov (United States)

Ohio State Univ., Columbus. National Center for Research in Vocational Education.

This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but it can be adapted for special groups or vocational teacher education. The emphasis of the seven instructional units in Part II is establishing a business. Unit A focuses on developing a business…

Parametric cost analysis of a HYLIFE-II power plant

International Nuclear Information System (INIS)

Bieri, R.L.

1991-01-01

The SAFIRE (Systems Analysis for ICF Reactor Economics) code was adapted to model a power plant using a HYLIFE-2 reactor chamber. The code was then used to examine the dependence of the plant capital costs and the busbar cost of electricity (COE) on a variety of design parameters (type of driver, chamber repetition rate, and net electric power). The results show the most attractive operating space for each set of driver/target assumptions and quantify the benefits of improvements in key design parameters. The base-case plant was a 1000-MW(e) plant containing a reactor vessel driven by an induction linac heavy-ion accelerator, run at 8 Hz with a driver energy of 6.73 MJ and a target yield of 350 MJ. The total direct cost for this plant was $2.6 billion. (All costs in this paper are given in equivalent 1988 dollars.) The COE was 8.5 cents/(kWh). The COE and total capital costs for a 1000-MW(e) base plant are nearly independent of the chosen combination of repetition rate and driver energy for a driver operating between 4 and 10 Hz. For comparison, the COE for a coal or future fission plant would be 4.5--5.5 cents/(kWh). The COE for a 1000-MW(e) plant could be reduced to 7.5 cents/(kWh) by using advanced targets and could be cut to 6.5 cents/(kWh) with conventional targets, if the driver cost could be cut in half. There is a large economy of scale with heavy-ion-driven inertial confinement fusion (ICF) plants. A 2000-MW(e) plant with a heavy-ion driver and a HYLIFE-2 chamber would have a COE of only 5.8 cents/(kWh)

Radiation effects on resins and zeolites at Three Mile Island Unit II

International Nuclear Information System (INIS)

Reilly, J.K.; Grant, P.J.; Quinn, G.J.; Hofstetter, K.J.

1984-01-01

Radiation effects on resin and zeolite used in the waste cleanup at Three Mile Island Unit II have been examined both experimentally and in-situ. Hydrogen and organic gases are generated due to absorbed radiation as a function of resin material, curie loading and residual water content. Significant oxygen scavaging was demonstrated in the organic resin liners. Hydrogen and oxygen gases in near stoichiometric quantities are generated from irradiation of residual water in inorganic zeolites. Gas generation was determined to be directly proportional to curie content but correlates poorly with residual water content in zeolite vessels. Results of the gas generation analyses of EPICOR II liners show that vessels with less than 166 curies had almost no hydrogen generated during two years of storage and therefore did not require safety measures for shipment or storage. Experimental measurements done at research laboratories predicted similar results associated with hydrogen gas generation and oxygen depletion. X-ray diffraction examinations and ion exchange capacity measurements indicated no evidence of irradiation effects on the structure or cesium exchange capacity for zeolites exposed to 10 10 rads. Darkening and damage of organic resin due to radiation has been identified. Breaking and agglomeration of the purification demineralizer resin is believed to be the result of temperature effects. No damage was identified from radiation effects on zeolite. Organic and inorganic sorbents used in the processing of contaminated waters at TMI-2 have been shown to be effective in maintaining long-term stability under high radiation conditions. The effects of radiolytic degradation have been shown by direct measurements and simulation tests and are of use in their general application throughout the industry

Planning for closures of hazardous waste land disposal units at the Oak Ridge Y-12 plant

International Nuclear Information System (INIS)

Welch, S.H.; Kelly, B.A.; DeLozier, M.F.P.; Manrod, W.E.

1988-01-01

Eight hazardous waste land disposal units at the Oak Ridge Y-12 Plant are being closed in accordance with the Resource Conservation and Recovery Act (RCRA) under an integrated multi-year program. The units, some of which date back to the early 1950s and include five surface impoundments, two landfills and a land treatment unit, have been used for the management of a variety of types of hazardous wastes. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. The units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. Closure of all eight units must be initiated by November 8, 1988. Funding for the eight closures is being provided by a new Department of Energy budget category, the environmental Restoration Budget Category (ERBC), which is intended to allow for a more rapid response to environmental problems and regulatory requirements. A major project, Closure and Post-Closure Activities (CAPCA) has been identified for ERBC funding to close the land disposal units in accordance with RCRA requirements. Establishing the project scope has required the development of a detailed set of assumptions and a confirmation program for each assumption. Other significant activities in the CAPCA project include risk assessments and the preparation of an integrated project schedule

Photosystem II repair and plant immunity: Lessons learned from Arabidopsis mutant lacking the THYLAKOID LUMEN PROTEIN 18.3

Directory of Open Access Journals (Sweden)

Sari eJärvi

2016-03-01

Full Text Available Chloroplasts play an important role in the cellular sensing of abiotic and biotic stress. Signals originating from photosynthetic light reactions, in the form of redox and pH changes, accumulation of reactive oxygen and electrophile species or stromal metabolites are of key importance in chloroplast retrograde signaling. These signals initiate plant acclimation responses to both abiotic and biotic stresses. To reveal the molecular responses activated by rapid fluctuations in growth light intensity, gene expression analysis was performed with Arabidopsis thaliana wild type and the tlp18.3 mutant plants, the latter showing a stunted growth phenotype under fluctuating light conditions (Biochem. J, 406, 415-425. Expression pattern of genes encoding components of the photosynthetic electron transfer chain did not differ between fluctuating and constant light conditions, neither in wild type nor in tlp18.3 plants, and the composition of the thylakoid membrane protein complexes likewise remained unchanged. Nevertheless, the fluctuating light conditions repressed in wild-type plants a broad spectrum of genes involved in immune responses, which likely resulted from shade-avoidance responses and their intermixing with hormonal signaling. On the contrary, in the tlp18.3 mutant plants there was an imperfect repression of defense-related transcripts upon growth under fluctuating light, possibly by signals originating from minor malfunction of the photosystem II (PSII repair cycle, which directly or indirectly modulated the transcript abundances of genes related to light perception via phytochromes. Consequently, a strong allocation of resources to defense reactions in the tlp18.3 mutant plants presumably results in the stunted growth phenotype under fluctuating light.

A PERFORMANCE MODELING AND DECISION SUPPORT SYSTEM FOR A FEED WATER UNIT OF A THERMAL POWER PLANT

Directory of Open Access Journals (Sweden)

S. Gupta

2012-01-01

Full Text Available

ENGLISH ABSTRACT: The present paper discusses the performance modeling and decision support system for a feed water unit of a thermal power plant using the concept of performance analysis and modeling. A feed water unit ensures a proper supply of water for the sound functioning of a thermal power plant. The decision support system for a feed water unit has been developed with the help of performance modeling using a probabilistic approach. After drawing a transition diagram, differential equations are generated. After that, steady state probabilities are determined. Some decision matrices are also developed, which provide various performance levels for different combinations of failure and repair rates of all subsystems. Based upon various availability values obtained in decision matrices and plots of failure rates / repair rates of various subsystems, the performance of each subsystem is analyzed, and maintenance decisions are made for all subsystems.

AFRIKAANSE OPSOMMING: Vertoningsanalise en –modellering word gedoen vir die toevoerwatersisteem van ‘n termiese kragstasie. Toevoerwater is ‘n belangrike factor vir die doeltreffende bedryf van ‘n kragstasie. Die vertoningsanalise en –model is probalisties van aard. ‘n Toestandoorgangsdiagram en bypassende differensiaalvergelykings word gebruik, gevolg deur bepaling van die bestandige sisteemtoestand. Bykomende aandag word gegee aan relevante subsisteme. Die vertoning van subsisteme word gebasseer op verskeie beskikbaarheidswaardes om sodoende instandhouding to optimiseer.

Land-Use Requirements for Solar Power Plants in the United States

Energy Technology Data Exchange (ETDEWEB)

Ong, S.; Campbell, C.; Denholm, P.; Margolis, R.; Heath, G.

2013-06-01

This report provides data and analysis of the land use associated with utility-scale ground-mounted solar facilities, defined as installations greater than 1 MW. We begin by discussing standard land-use metrics as established in the life-cycle assessment literature and then discuss their applicability to solar power plants. We present total and direct land-use results for various solar technologies and system configurations, on both a capacity and an electricity-generation basis. The total area corresponds to all land enclosed by the site boundary. The direct area comprises land directly occupied by solar arrays, access roads, substations, service buildings, and other infrastructure. As of the third quarter of 2012, the solar projects we analyze represent 72% of installed and under-construction utility-scale PV and CSP capacity in the United States.

Availability of thermal power plants 1981-1990

International Nuclear Information System (INIS)

Nitsch, D.; Schmitz, H.

1991-01-01

The present volume covers the period of 1981 to 1990 and contains availability data of power plants in Germany and abroad. Data are presented on fossil-fuelled units, units with a combined gas/steam cycle, nuclear power plants and gas turbines. The fossil-fuelled units are broken down by unit size, years of operation, fuel, type of combustion (dry, melt) and type (mono, duo units, subcritical and supercritical systems). Nuclear power stations are arranged by type of reactor (PWR, BWR), unit size and years of operation. Combined cycle power plants are listed separately due to their different technical concepts. Apart from availability and utilisation values of gas turbines there are data on reliability and the number of successful and unsuccessful starts. In general the data are first given for all plants and then for the German plants in particular. Performance values are gross values measured at generator terminals and, as the number of plants, they are end-of-the-year figures [de

New Approaches to Ecologically Based, Designed Urban Plant Communities in Britain: Do These Have Any Relevance in the United States?

Directory of Open Access Journals (Sweden)

James Hitchmough

2008-01-01

Full Text Available This paper discusses the reasoning behind the development of a new approach to designed urban planting with grasses, forbs and geophytes that has been undertaken at the University of Sheffield over the past 15 years. The resulting plant communities are the result of applying contemporary ecological science to planting design, to maximize their sustainability while at the same time meeting the aesthetic and functional needs of the users of urban public landscapes. The geographical origin of the plants used in these communities varies according to the physical, ecological, and cultural context in which they are to be used. In some cases species are entirely native, in others entirely non-native. In many cases, a mixture of both is used. In discussing the rationale for the development of this approach in the United Kingdom context, the paper raises important issues about increasing the capacity of urban landscapes to support a greater diversity of native animals and to engage ordinary citizens in these activities at a time of dramatic climatic and social change. The approach we outline addresses some of these issues in the United Kingdom context, but it is uncertain whether there is merit in these approaches in the context of American towns and cities.

Neural networks for sensor validation and plant monitoring

International Nuclear Information System (INIS)

Upadhyaya, B.R.; Eryurek, E.; Mathai, G.

1990-01-01

Sensor and process monitoring in power plants require the estimation of one or more process variables. Neural network paradigms are suitable for establishing general nonlinear relationships among a set of plant variables. Multiple-input multiple-output autoassociative networks can follow changes in plant-wide behavior. The backpropagation algorithm has been applied for training feedforward networks. A new and enhanced algorithm for training neural networks (BPN) has been developed and implemented in a VAX workstation. Operational data from the Experimental Breeder Reactor-II (EBR-II) have been used to study the performance of BPN. Several results of application to the EBR-II are presented

Quantitative comparison of the nuclear power plant sites in the United Kingdom

Energy Technology Data Exchange (ETDEWEB)

Shaw, J; Sina, A M [Queen Mary Coll., London (UK). Dept. of Nuclear Engineering

1976-01-01

A probabilistic method is described for a comparison of nuclear power plant sites in the United Kingdom, which evaluates quantitatively the sites in terms of favourability, by taking into account the real term meteorological conditions, i.e. wind direction, wind speed, and stability distributions, and also the population distribution around the cities. A 'site safety quality factor' is obtained for each site and is used to compare the favourability of each site with respect to releases of radioactivity. The quality factor corresponds to the average number of persons that would be exposed to the specified relative concentration averaged over all weather conditions. The sites compared are Berkeley, Bradwell, Dungeness, Hartlepool, Heysham, Oldbury, Sizewell, and Wylfa.

Thermodynamic analysis of the advanced zero emission power plant

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