Turbine Control System Replacement at NPP NEK; System Specifics, Project Experience and Lessons Learned

International Nuclear Information System (INIS)

Mandic, D.; Zilavy, M. J.

2010-01-01

The main intention of this paper is to present feedback from the implementation of the new Turbine Control System (TCS) replacement project at Nuclear Power Plant (NPP) NEK - Krsko. From the plant construction time and the first plant start-up in 1981, the NPP NEK TG (Turbine-Generator) set was controlled and monitored by DEH (Digital Electro Hydraulic) Mod II Control System designed in 70's based on P2500 CPU and number of I/O controllers and modules. The P2500 CPU and associated controllers were built with discrete TTL components (TTL logic chips) and the P2500 CPU had 64k of 16 bit words of ferrite core memory. For that time, DEH Mod II had sophisticated MCR (Main Control Room) HMI (Human Machine Interface) based on digital functional keyboards, one alphanumeric black and white CRT monitor and printer. After twenty eight years of operation and because of several other reasons that are explained in the paper, NEK decided to replace the old DEH Mod II Control system with the new Emerson Ovation based DCS (Distributed Control System) on redundant platform for the control and monitoring of secondary plant systems in the NPP Krsko (NEK), and the new system was named PDEH (Programmable Digital Electro Hydraulic) TCS. In May 2007, NEK signed the turn-key contract with Westinghouse Electric Company (WEC) for the project of replacement of the TCS, Turbine Emergency Trip System (ETS), Moisture Separator Reheater (MSR) control and some other control and monitoring functions. WEC subcontracted a number of other companies for equipment delivery, AE (Architect Engineering Design) activities, specific software development tasks (changes of KFSS - Krsko Full Scope Simulator and PIS - Process Information System interface) and field installation activities. The subject project enveloped implementation of PDEH system on three application platforms: BG KFSS (Background KFSS), FG KFSS (Foreground KFSS) and PDEH system installed in the plant. The HMI for the BG KFSS platform

NPP Krsko full scope simulator verification and qualification

International Nuclear Information System (INIS)

Krajnc, B.; Glaser, B.; Novsak, M.; Spiler, J.

1998-01-01

NPP Krsko (NEK) will, as a part of the Modernization plan, obtain also Krsko Full Scope Simulator (KFSS). Contract has been awarded to CAE Electronics for the design, construction and integration. KFSS will support in real time, the training for the complete range of operation, which can be performed from the main control room and some selected plant areas (remote shutdown panels, etc). Based on the lessons learned on development of NPP Krsko Basic Principle Simulator we decided for active approach. That means that NPP Krsko personnel will be heavily involved into all phases of KFSS development and testing. Since NPP Krsko is going to replace the existing steam generators, raise the nominal power and perform necessary modifications to support the power uprate, it was decided that the development of the KFSS will be conducted in two steps: 1. Development of the models as well as all the hardware interface in the MCR for the existing plant Cycle 15 and then, 2. Models and hardware will be modified, added or replaced as needed to take into account the steam generator replacement and plant uprate projects. In spite of the fact that the simulator will be used for the training of the plant operators for the uprated conditions and with new steam generators, the upper described approach was selected since we want to be sure that the models will at the beginning adequately simulate the existing plant. For the existing conditions we have available reference data for different plant conditions, as well as data for different plant transients. By verifying that simulator will be able adequately simulate the existing conditions the level of confidence for the uprated simulator will be much higher. This is of special importance since it will support initial training for modernized plant conditions. In this paper the plan for verification and qualification of KFSS as well as the amount of the work needed on NPP Krsko side to develop the test acceptance criteria will be presented.(author)

Krsko NPP Periodic Safety Review program

International Nuclear Information System (INIS)

Basic, I.; Spiler, J.; Novsak, M.

2001-01-01

The need for conducting a Periodic Safety Review for the Krsko NPP has been clearly recognized both by the NEK and the regulator (SNSA). The PSR would be highly desirable both in the light of current trends in safety oversight practices and because of many benefits it is capable to provide. On January 11, 2001 the SNSA issued a decision requesting the Krsko NPP to prepare a program and determine a schedule for the implementation of the program for 'Periodic Safety Review of NPP Krsko'. The program, which is required to be in accordance with the IAEA safety philosophy and with the EU practice, was submitted for the approval to the SNSA by the end of March 2001. The paper summarizes Krsko NPP Periodic Safety Review Program [1] including implemented SNSA and IAEA Expert Mission comments.(author)

Operational and safety status of Krsko NPP

International Nuclear Information System (INIS)

Sirola, P.; Kavsek, D.

1998-01-01

Nuclear Power Plants Krsko (NEK) is producing electricity with the high level of reliability, safety and at acceptable price for 17 years. Energy is shared between both Slovenian and Croatian grid. The specifics of sharing the initial investment costs, later covering the operations costs and energy supply between Croatia and Slovenia is causing specific decision making problems about energy cost and future investments, however not influencing the plant safety, by now. NEK is continuously following the international nuclear technology practices, standards' changes and improvements and introducing them into the processes and equipment upgrades. As the member of the most important international integration, NEK is having the possibility of sharing its experience with others. Slovenian Energy Consumption and Supply Strategy is recognizing the NEK as a long term supply of energy in Slovenia being a strong decision making base for the future. According to the above mentioned Slovenian Energy Consumption and Supply Strategy the plant is obliged to keep all the radioactive waste, produced during the plant life, on site. The extensive efforts are taking place to reduce the radioactive waste production and save the area available for temporary waste deposition. The plant is licensed for the period of 40 years of commercial operation which started in 1983, so the Life Time Management is getting more and more important, including the performance tracing of the essential components, their maintenance and surveillance programs and also replacement plans of critical equipment. The major problems the NEK is confronted with at the moment are the Steam Generators which are reaching their and of life, and a very limited radioactive waste storage area. They are excerting influence on the plant availability and operations and maintenance costs. At the moment the process of Modernization is in progress, covering the Steam Generators replacement and a Plant Specific Simulators supply

Trending of Events - Practical Use at Krsko NPP

International Nuclear Information System (INIS)

Skaler, F.; Bach, B.

2008-01-01

Krsko NPP (NEK) in 2004 developed a new application, a corrective action program (CAP) software, to acquire all events within the same environment. In 2006 NEK started to code all acquired records of the events. In 2007 NEK developed within CAP application new tools for analyzing the events. These new tools are common cause analyses Root cause, Direct causes, Processes, and Equipment failures. The new tools are user friendly and easy to use. With these new tools the useful queries are generated easily. The results are presented in graphs, which have drill down options all the way down to the reported event itself. With these new tools many common cause analyses can be done within seconds, which in the past took hours or even days. Also the department leads can easily perform common cause analyses within their departments or processes, they can compare the different periods or projects and they can look for different type of causes. NEK next step is a learning module for the department leads. They have to learn how to use these tools and to understand the results correctly. NEK has to establish the process, where these analyses can be formalized, checked and the most effective correction actions to prevent the events can be taken. Also all the process can be formalized. The presentation will explain the theory of trending the minor events and practical implementation at Krsko NPP. The presentation will also present the new tools in CAP application with some very interesting examples of common cause analyses. The presentation will explain possibilities for the future process at NEK to fully implement these tools in order to prevent the events.(author)

Emergency preparedness exercise ''Posavje 82'' in support of the Krsko Nuclear Power Plant, Krsko, Yugoslavia

International Nuclear Information System (INIS)

Collins, H.E.; Emmerson, B.W.

1983-06-01

In October 1982, the Yugoslavian Government requested the Agency's assistance in observing and evaluating an emergency preparedness exercise (code named ''POSAVJE 82'') on 5 and 6 November 1982, to test emergency plans and arrangements supportive of the KRSKO Nuclear Power Plant. The Krsko Nuclear Power Plant is a single unit pressurized water reactor of United States (Westinghouse) design rated at 664 MWe (Gross) and is located at Krsko, Socialist Republic of Slovenia, Yugoslavia. This assistance was provided by sending a Special Assistance Mission team of experts under the general provisions of the Agency's circular letter SC/651-3 of 7 April 1981 to Member States which offered such assistance upon request. This mission was a follow-up to a previous mission requested by the Yugoslavian Government which was conducted 24 June - 1 July 1981. At that time, the mission consisted of examining the then existing arrangements for emergency planning in support of the KRSKO Nuclear Power Plant at the National, Republic, local and nuclear power plant levels and discussing with Yugoslavian authorities criteria for emergency plan development and improvement. As a result of this 1981 mission, a ''Report to the Goverment of Yugoslavia'' (IAEA TA Report 1827 of 17 September 1981) was transmitted to the Yugoslavian Government. This report set forth a number of recommendations for improving and further developing the various emergency plans and arrangements for the KRSKO Nuclear Power Plant. A summary of the major recommendations contained in the report is given in Section 2.2. The entire report is listed as Reference 1 of Annex A

Upgrade of Common Cause Failure Modelling of NPP Krsko PSA

International Nuclear Information System (INIS)

Vukovic, I.; Mikulicic, V.; Vrbanic, I.

2006-01-01

Over the last thirty years the probabilistic safety assessments (PSA) have been increasingly applied in technical engineering practice. Various failure modes of system of concern are mathematically and explicitly modelled by means of fault tree structure. Statistical independence of basic events from which the fault tree is built is not acceptable for an event category referred to as common cause failures (CCF). Based on overview of current international status of modelling of common cause failures in PSA several steps were made related to primary technical basis for methodology and data used for CCF model upgrade project in NPP Krsko (NEK) PSA. As a primary technical basis for methodological aspects of CCF modelling in Krsko PSA the following documents were considered: NUREG/CR-5485, NUREG/CR-4780, and Westinghouse Owners Group documents (WOG) WCAP-15674 and WCAP-15167. Use of these documents is supported by the most relevant guidelines and standards in the field, such as ASME PRA Standard and NRC Regulatory Guide 1.200. WCAP documents are in compliance with NUREG/CR-5485 and NUREG/CR-4780. Additionally, they provide WOG perspective on CCF modelling, which is important to consider since NEK follows WOG practice in resolving many generic and regulatory issues. It is, therefore, desirable that NEK CCF methodology and modelling is in general accordance with recommended WOG approaches. As a primary basis for CCF data needed to estimate CCF model parameters and their uncertainty, the main used documents were: NUREG/CR-5497, NUREG/CR-6268, WCAP-15167, and WCAP-16187. Use of NUREG/CR-5497 and NUREG/CR-6268 as a source of data for CCF parameter estimating is supported by the most relevant industry and regulatory PSA guides and standards currently existing in the field, including WOG. However, the WCAP document WCAP-16187 has provided a basis for CCF parameter values specific to Westinghouse PWR plants. Many of events from NRC / INEEL database were re-classified in WCAP

Impact of power plant KRSKO on the environment

International Nuclear Information System (INIS)

Hak, Nena; Lulic, Stipe

1993-01-01

The Sava river is among the largest rivers in the Republic of Croatia. It drains 95.000 square kilometers before meeting the Danube River. The Sava river and its surroundings we being exploited in agriculture, forestry, power generation (one nuclear power plant and several thermal power plants), oil transportation, gravel extraction and recreation. At last, the Sava River is the major source of fresh water for industry and population. Different authorized institutions from the Republic of Slovenia and the Republic of Croatia are included in programs of nonradiological and radiological monitoring of Nuclear Power Plant Krsko (NPPK). Quarterly, the institutions from the Republic of Croatia, NPP Krsko and the Ministry of Energy of the Republic of Croatia, submit public information in the Republic of Croatia about NPP Krsko operation and its environmental impact

NPP Krsko periodic safety review. Safety assessment and analyses

International Nuclear Information System (INIS)

Basic, I.; Spiler, J.; Thaulez, F.

2002-01-01

Definition of a PSR (Periodic Safety Review) project is a comprehensive safety review of a plant after ten years of operation. The objective is a verification by means of a comprehensive review using current methods that the plant remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. The overall goals of the NEK PSR Program are defined in compliance with the basic role of a PSR and the current practice typical for most of the countries in EU. This practice is described in the related guides and good practice documents issued by international organizations. The overall goals of the NEK PSR are formulated as follows: to demonstrate that the plant is as safe as originally intended; to evaluate the actual plant status with respect to aging and wear-out identifying any structures, systems or components that could limit the life of the plant in the foreseeable future, and to identify appropriate corrective actions, where needed; to compare current level of safety in the light of modern standards and knowledge, and to identify where improvements would be beneficial for minimizing deviations at justifiable costs. The Krsko PSR will address the following safety factors: Operational Experience, Safety Assessment, EQ and Aging Management, Safety Culture, Emergency Planning, Environmental Impact and Radioactive Waste.(author)

New low pressure (LP) turbines for NE Krsko

International Nuclear Information System (INIS)

Nemcic, K.; Novsak, M.

2004-01-01

During the evaluation of possible future maintenance strategies on steam turbine in very short period of time, engineering decision was made by NE Krsko in agreement with Owners to replace the existing two Low Pressure (LP) Turbines with new upgrading LP Turbines. This decision is presented with review of the various steam turbine problems as: SCC on turbine discs; blades cracking; erosion-corrosion with comparison of various maintenance options and efforts undertaken by the NE Krsko to improve performance of the original low pressure turbines. This paper presents the NEK approach to solve the possible future problems with steam turbine operation in NE Krsko as pro-active engineering and maintenance activities on the steam turbine. This paper also presents improvements involving retrofits, confined to the main steam turbine path, with major differences between original and new LP Turbines as beneficial replacement because of turbine MWe upgrading and return capital expenditures.(author)

Outages 1999 and 2000, investments in safety and long-term operation of NE Krsko

International Nuclear Information System (INIS)

Sirola, P.; Krajnc, J.; Androjna, F.

1999-01-01

Plant outage is an important part of nuclear power plant operation. During that time the conditions are established for the performance of specific activities, such as refueling, tests, inspections, preventive and corrective maintenance and modifications, that are intended to confirm proper condition and availability of safety and other important components and improve overall plant safety and reliability. It is well know that in Nuclear Power Plant Krsko (Nuklearna elektrarna Krsko NEK) during Outage 2000 new Steam Generators (SGs) will be placed in service, while Outage '99 was used for preparatory works. But the importance of those two outages is even greater, because they are implementing a broad number of improvements and establishing a basis for long-term plant operation. Outage '99 required very detailed planning to assure a good control over the outage activities and operational plant systems necessary for safe shutdown. Numerous activities took place in a relatively narrow space in the Reactor Building. Some of these activities will have a big significance for the future. The article treats the status update and summarizes the specifics and importance of the mentioned activities to long-term plant safe and reliable operation.(author)

Overview of Mobile Equipment Used in Case of Beyond Design Basis Accident at NPP Krsko

International Nuclear Information System (INIS)

Lukacevic, H.; Kopinc, D.; Ivanjko, M.

2016-01-01

Terrorist attack in USA in the September 11, 2001 and accident at the Fukushima - Daiichi Nuclear Power Station in the March 11, 2011 highlight the importance of mitigating strategies in responding to Beyond Design Basis Accident (BDBA), while ensuring cooling of reactor core, containment and spent fuel pool. Nuclear Power Plant Krsko (NEK) has acquired additional mobile equipment and made necessary modifications on existing systems for the connection of this equipment (fast couplers). Usage of mobile equipment is not only limited to design basis accident (DBA), but, also to prevent and mitigate the consequences in case of BDBA, when other plant systems are not available. NEK also decided to take steps for upgrade of safety measures and prepared Safety Upgrade Program (SUP), which is consistent with the nuclear industry response to the Fukushima accident and is implementing main projects and modifications related to SUP. NEK mobile equipment is not required to operate under normal reactor plant operation except for periodic surveillance testing and is incorporated into the normal training process. Equipment is dislocated from the reactor building and most of the equipment is located in the new building, able to withstand extreme natural events, including earthquakes and tornadoes. The usage of all mobile equipment is prescribed as an additional option in NEK operating procedures in following cases and enables following options: filling various tanks, filling the steam generators, filling the containment, additional compressed air source, spent fuel pool refilling and spraying, alternative power supply. This document provides an overview of NEK mobile equipment, which consists of various mobile fire protection pumps, air compressors, protective equipment, fire trucks, diesel generators. Sufficient fuel supply for the equipment is provided on site for a minimum three days of operation. (author).

Soundness of Krsko Nuclear Power Plant Performance in Terms of Energy and Finance

International Nuclear Information System (INIS)

Curkovic, A.; Vrankic, K.; Magdic, M.

1998-01-01

Compared to existing conventional thermal power plants in Croatian electric power system, as well as to alternative (potential) imported coal and gas fired thermal power plants, Krsko NPP (nuclear power plant) generates electricity with lower production costs. This cost margin in favour of the Krsko NPP represents the soundness of this nuclear power plant in terms of energy and finance. (author)

Krsko Nuclear Power Plant's Environmental Management System in Compliance with ISO 14001:2004

International Nuclear Information System (INIS)

Kusar, A.; Kavsek, D.

2010-01-01

Krsko Nuclear Power Plant (NPP) pays special attention to environmental protection and practices environmental safety in all plant processes and management. In 2008, Krsko NPP introduced the Environmental Management System in compliance with ISO 14001:2004 standard. The plant management announced the Environmental policy which is a part of the business strategy of Krsko NPP which is an eco-friendly company. The Policy is a commitment of the plant management and all staff to act in compliance with requirements of ISO 14001:2004. The standard served as a basis for developing some new documentation such as Environmental Management System Quality Manual, Environmental planning procedures identifying legal and other requirements, Register of environmental aspects, Register of legal and other requirements etc. When establishing the Register of environmental aspects, all possible environmental impacts of the plant were carefully reviewed and estimated. Following the introduction and certification audit in October and December 2008 of Bureau Veritas Certification, Krsko NPP was awarded certificate ISO 14001:2004 attesting conformity of its Environmental Management System with this standard. The Environmental Certificate means that Krsko NPP will promote a positive environmental culture and maintain a safe, healthy and environmentally-sound workplace for all its employees, contractors and visitors.(author).

Utilization of NPP Krsko plant specific simulator

International Nuclear Information System (INIS)

Fifnja, I.; Pribozic, F.; Krajnc, J.

2002-01-01

NPP Krsko started with licensed operator training using its own plant-specific full scope simulator in April 2000. Today, two years after simulator was completed, the benefits of simulator use are visible in various fields. The simulator was effectively used to conduct licensed operator continuing training and practical examinations. Two-year continuous training program was designed to help maintain and improve operator performance. The simulator was also used to provide just-in-time training prior to plant evolutions. Together with licensed operators the non-licensed operators are also included into simulator training to provide affective team training opportunity and to foster good communication and increase scenario realism. Now, the first group of initial licensed operator training using plant-specific simulator is also almost completed. It is the first time that NPP Krsko training department conducted complete initial training and this will represent the great experience for future training. Besides training, the simulator was also utilized for procedure development and validation, operating standards development, testing of plant modifications and other activities, like emergency preparedness procedures validation and training exercises.(author)

Some Aspects of Process Computers Configuration Control in Nuclear Power Plant Krsko - Process Computer Signal Configuration Database (PCSCDB)

International Nuclear Information System (INIS)

Mandic, D.; Kocnar, R.; Sucic, B.

2002-01-01

During the operation of NEK and other nuclear power plants it has been recognized that certain issues related to the usage of digital equipment and associated software in NPP technological process protection, control and monitoring, is not adequately addressed in the existing programs and procedures. The term and the process of Process Computers Configuration Control joins three 10CFR50 Appendix B quality requirements of Process Computers application in NPP: Design Control, Document Control and Identification and Control of Materials, Parts and Components. This paper describes Process Computer Signal Configuration Database (PCSCDB), that was developed and implemented in order to resolve some aspects of Process Computer Configuration Control related to the signals or database points that exist in the life cycle of different Process Computer Systems (PCS) in Nuclear Power Plant Krsko. PCSCDB is controlled, master database, related to the definition and description of the configurable database points associated with all Process Computer Systems in NEK. PCSCDB holds attributes related to the configuration of addressable and configurable real time database points and attributes related to the signal life cycle references and history data such as: Input/Output signals, Manually Input database points, Program constants, Setpoints, Calculated (by application program or SCADA calculation tools) database points, Control Flags (example: enable / disable certain program feature) Signal acquisition design references to the DCM (Document Control Module Application software for document control within Management Information System - MIS) and MECL (Master Equipment and Component List MIS Application software for identification and configuration control of plant equipment and components) Usage of particular database point in particular application software packages, and in the man-machine interface features (display mimics, printout reports, ...) Signals history (EEAR Engineering

Start-up of NPP Krsko; Pokusno obratovanje NE Krsko

Energy Technology Data Exchange (ETDEWEB)

Spiler, J; Aralica, J [Nuklearna elektrana Krsko, Krsko (Yugoslavia)

1984-07-01

The report describes a review of start-up program and its realisation. There are also described some more significant start-up results with their evaluation. The most significant operation criteria are compared between NPP Krsko and other similar plants in the world. The comparison shows that after the first contractors and operation personnel efforts have been accomplished, our first nuclear power plant is a safe and reliable source of electric power. At the end there are listed NPP Krsko start-up recommendations and experience. (author)

Seismic characterization of the NPP Krsko site

International Nuclear Information System (INIS)

Obreza, J.

2000-01-01

The goal of NPP Krsko PSA Project Update was the inclusion of plant changes (i.e. configuration/operational related) through the period January 1, 1993 till the OUTAGE99 (April 1999) into the integrated Internal/External Level 1/Level 2 NPP Krsko PSA RISK SPECTRUM model. NPP Krsko is located on seismotectonic plate. Highest earthquake was recorded in 1917 with magnitude 5.8 at a distance of 7-9 km. Site (founded) on Pliocene sediments which are as deep as several hundred meters. No surface faulting at the Krsko site has been observed and thus it is not to be expected. NPP Krsko is equipped with seismic instrumentation, which allows it to complete OBE (SSE). The seismic PSA successfully showed high seismic margin at Krsko plant. NPP Krsko seismic design is based on US regulations and standards

Integrated approach to fire safety at the Krsko nuclear power plant - fire protection action plan

International Nuclear Information System (INIS)

Lambright, J.A.; Cerjak, J.; Spiler, J.; Ioannidi, J.

1998-01-01

Nuclear Power Plant Krsko (NPP Krsko) is a Westinghouse design, single-unit, 1882 Megawatt thermal (MWt), two-loop, pressurized water nuclear power plant. The fire protection program at NPP Krsko has been reviewed and reports issued recommending changes and modifications to the program, plant systems and structures. Three reports were issued, the NPP Krsko Fire Hazard Analysis (Safe Shout down Separation Analysis Report), the ICISA Analysis of Core Damage Frequency Due to Fire at the NPP Krsko and IPEEE (Individual Plant External Event Examination) related to fire risk. The Fire Hazard Analysis Report utilizes a compliance - based deterministic approach to identification of fire area hazards. This report focuses on strict compliance from the perspective of US Nuclear Regulatory Commission (USNRC), standards, guidelines and acceptance criteria and does not consider variations to comply with the intent of the regulations. The probabilistic analysis methide used in the ICISA and IPEEE report utilizes a risk based nad intent based approach in determining critical at-risk fire areas. NPP Krsko has already completed the following suggestions/recommendations from the above and OSART reports in order to comply with Appendix R: Installation of smoke detectors in the Control Room; Installation of Emergency Lighting in some plant areas and of Remote Shout down panels; Extension of Sound Power Communication System; Installation of Fire Annunciator Panel at the On-site Fire Brigade Station; Installation of Smoke Detection System in the (a) Main Control Room Panels, (b) Essential Service Water Building. (c) Component Cooling Building pump area, chiller area and HVAC area, (d) Auxiliary Building Safety pump rooms, (e) Fuel Handling room, (f) Intermediate Building AFFW area and compressor room, and (g) Tadwaste building; inclusion of Auxiliary operators in the Fire Brigade; training of Fire Brigade Members in Plant Operation (9 week course); Development of Fire Door Inspection and

Methodology and results of the seismic probabilistic safety assessment of Krsko nuclear power plant

International Nuclear Information System (INIS)

Vermaut, M.K.; Monette, P.; Campbell, R.D.

1995-01-01

A seismic IPEEE (Individual Plant Examination for External Events) was performed for the Krsko plant. The methodology adopted is the seismic PSA (Probabilistic Safety Assessment). The Krsko NPP is located on a medium to high seismicity site. The PSA study described here includes all the steps in the PSA sequence, i.e. reassessment of the site hazard, calculation of plant structures response including soil-structure interaction, seismic plant walkdowns, probabilistic seismic fragility analysis of plant structures and components, and quantification of seismic core damage frequency (CDF). Also relay chatter analysis and soil stability studies were performed. The seismic PSA described here is limited to the analysis of CDF (level I PSA). The subsequent determination and quantification of plant damage states, containment behaviour and radioactive releases to the outside (level 2 PSA) have been performed for the Krsko NPP but are not further described in this paper. The results of the seismic PSA study indicate that, with some upgrades suggested by the PSA team, the seismic induced CDF is comparable to that of most US and Western Europe NPPs. (author)

Plant specific basic principle simulator as a first step to plant specific full scope simulator

International Nuclear Information System (INIS)

Krajnc, B.; Pribozic, F.; Novsak, M.

1996-01-01

Nuklearna Elektrarna Krsko (NEK) decided to enhance the quality and scope of initial training of NEK technical personnel, mainly in so called Phase 1 and 2 of training for licensed personnel. This training is a prerequisite for further training on the full scope simulator for future operators and is also given to larger number of engineers, working in different important areas where thorough knowledge of nuclear technology and plant systems is required. Due to that it was decided that plant specific Basis Principle Simulators (BPS) should be developed. The other important reason for such decision was an indication that NEK specific full scope simulator will have to be purchased. Based on that it was concluded that BPS should serve as a good opportunity to learn about the state of the art approaches in the modeling area, to see in which direction development of software in conjunction with state of the art hardware is going and in particular to the extent possible verify the existence of required plant documentation in support BPS and later plant specific full scope simulator. In this paper the scope of NEK BPS simulation, experience in initial data gathering, experience with know-how transfer based on direct involvement of NEK and Izobrazevalni Center za Jedrsko Tehnnologijo (ICJT) personnel in modeling of instrumentation and control will be presented. Lessons learned, particularly in light of coming project for NEK full scope simulator, will also be addressed. The future use of the BPS in the NEK training programs will be described. It can be concluded that due to very complex technology, phase approaches in training of key NEK technical personnel, the development of NEK plant specific BPS is justifiable, regardless of the fact that NEK will also obtain specific full scope simulator. It has to be pointed out that BPS can not be supplement for plant specific full scope simulator, due to number of reasons discussed in the paper. (author)

Intranet portal at the Krsko NPP, Slovenia

International Nuclear Information System (INIS)

2016-01-01

The intranet portal (named IntraNEK) at Krsko NPP serves as a single entry point to access the internet and various plant applications and links. The front page consists of the standard internet search bar and links to various applications that can either reside within the technological computer network (TRM) or within the plant business computer network. Access to the TRM applications is read only. Some applications on the business computer network are open to all personnel who log on to the network while some applications are restricted and secured, and require additional login entries. A selected link will open in a new window. Documents will open with the appropriate software tool depending on the document file format. Some categories of documents are available in image form only (e.g. procedures, drawings etc.), while some are available in fully searchable PDF format (e.g. technical specifications, updated safety analysis reports (USARs) etc.). Plant departments (organizational units) have their own pages accessible from the front page. Their pages contain links to their own information resources or links to other resources and applications, tailored to the department needs. During recent years a number of web based applications have been developed that are connected also with a common Oracle database. Some are designed to serve for data entry and browsing while others serve for browsing only

Krsko NPP Quality Assurance Plan Application to Nuclear Safety Upgrade Projects (PCFV System and PAR System)

International Nuclear Information System (INIS)

Biscan, Romeo; Fifnja, Igor

2014-01-01

Nuklearna Elektrarna Krsko (NEK) has undertaken Nuclear Safety Upgrade Projects as a safety improvement driven by the lessons learned from the Fukushima-Daiichi Accident. Among other projects, new modification 1008-VA-L Passive Containment Filtered Vent (PCFV) System has been installed which acts as the last barrier minimizing the release of radioactive material into the environment in case of failure of all safety systems, and to insure containment integrity during beyond design basis accidents (BDBA). In addition, modification 1002-GH-L Severe Accident Hydrogen Control System (PAR) has been implemented to prevent and mitigate the consequences of explosive gas generation (hydrogen and carbon monoxide) in case of reactor core melting. To ensure containment integrity for all design basis accidents (DBA) and BDBA conditions, NEK has eliminated existing safety-related electrical recombiners, replaced them with two safety-related passive autocatalytic recombiners (PARs) and added 20 new PARs designed for the BDBA conditions. Krsko NPP Quality Assurance Plan has been applied to Nuclear Safety Upgrade Projects (PCFV System and PAR System) through the following activities: · Internal audit of modification process was performed. · Supplier audits were performed to evaluate QA program efficiency of the main design organization and engineering organizations. · Evaluation and approval of Suppliers were performed. · QA engineer was involved in the review and approval of 1008-VA-L and 1002-GH-L modification documentation (Conceptual Design Package, Design Modification Package, Installation Package, Field Design Change Request, Problem/Deficiency Report, and Final Documentation Package). · Purchasing documentation for modifications 1008-VA-L and 1002-GH-L (technical specifications, purchase orders) has been verified and approved by QA. · QA and QC engineers were involved in oversight of production and testing of the new 1008-VA-L and 1002-GH-L plant components. �

Model of fire spread around Krsko Power Plant

International Nuclear Information System (INIS)

Vidmar, P.; Petelin, S.

2001-01-01

The idea behind the article is how to define fire behaviour. The work is based on an analytical study of fire origin, its development and spread. The study is based on thermodynamics, heat transfer and the study of hydrodynamics and combustion, which represent the bases of fire dynamics. The article shows a practical example of a leak of hazardous chemicals from a tank. Because of the inflammability of the fluid, fire may start. We have tried to model fire propagation around the Krsko power plant, and show what extended surrounding area could be affected. The model also considers weather conditions, in particular wind speed and direction. For this purpose we have used the computer code Safer Trace, which is based on zone models. That means that phenomena are described by physical and empirical equations. An imperfection in this computer code is the inability to consider ground topology. However in the case of the Krsko power plant, topology is not so important, as the plan is located in a relatively flat region. Mathematical models are presented. They show the propagation of hazardous fluid in the environment considering meteorological data. The work also shows which data are essential to define fire spread and shows the main considerations of Probabilistic Safety Assessment for external fire event.(author)

NPP Krsko Severe Accident Management Guidelines Implementation

International Nuclear Information System (INIS)

Basic, I.; Krajnc, B.; Bilic-Zabric, T.; Spiler, J.

2002-01-01

Severe Accident Management is a framework to identify and implement the Emergency Response Capabilities that can be used to prevent or mitigate severe accidents and their consequences. The USA NRC has indicated that the development of a licensee plant specific accident management program will be required in order to close out the severe accident regulatory issue (Ref. SECY-88-147). Generic Letter 88-20 ties the Accident management Program to IPE for each plant. The SECY-89-012 defines those actions taken during the course of an accident by the plant operating and technical staff to: 1) prevent core damage, 2) terminate the progress of core damage if it begins and retain the core within the reactor vessel, 3) maintain containment integrity as long as possible, and 4) minimize offsite releases. The subject of this paper is to document the severe accident management activities, which resulted in a plant specific Severe Accident Management Guidelines implementation. They have been developed based on the Krsko IPE (Individual Plant Examination) insights, Generic WOG SAMGs (Westinghouse Owners Group Severe Accident Management Guidances) and plant specific documents developed within this effort. Among the required plant specific actions the following are the most important ones: Identification and documentation of those Krsko plant specific severe accident management features (which also resulted from the IPE investigations). The development of the Krsko plant specific background documents (Severe Accident Plant Specific Strategies and SAMG Setpoint Calculation). Also, paper discusses effort done in the areas of NPP Krsko SAMG review (internal and external ), validation on Krsko Full Scope Simulator (Severe Accident sequences are simulated by MAAP4 in real time) and world 1st IAEA Review of Accident Management Programmes (RAMP). (author)

NPP Krsko Periodic Safety Review action plan

International Nuclear Information System (INIS)

Bilic Zabric, T.

2006-01-01

In the current, internationally accepted, safety philosophy Periodic Safety Reviews (PSRs) are comprehensive reviews aimed at the verification that an operating NPP remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain an acceptable level of safety. These reviews are complementary to the routine and special safety reviews. They are long time-scale reviews intended to deal with the cumulative effects of plant ageing, modifications, operating experience and technical developments, which are not so easily comprehended over the shorter time-scale routine of safety reviews. The review was completed in 2005 and the next period will see the implementation of the action plan including some plant upgrades. The action plan lists issues that should be implemented at NPP Krsko together with associated milestones. The milestones were assumed based on best estimate resource availability and their ends can be potentially floated. In some cases, multiple corrective measures may be postulated to provide resolution for a given safety issue. The Slovenian Nuclear Safety Administration by decree approved the first periodic safety review and the implementation plan of activities arising from it. The entire implementation plan must be carried out by 15 October 2010. Report on the second periodic safety review must be submitted by the NEK not later than 15 December 2013. (author)

The new revision of NPP Krsko decommissioning, radioactive waste and spent fuel management program: analyses and results

International Nuclear Information System (INIS)

Zeleznik, Nadja; Kralj, Metka; Lokner, Vladimir; Levanat, Ivica; Rapic, Andrea; Mele, Irena

2010-01-01

The preparation of the new revision of the Decommissioning and Spent Fuel (SF) and Low and Intermediate level Waste (LILW) Disposal Program for the NPP Krsko (Program) started in September 2008 after the acceptance of the Term of Reference for the work by Intergovernmental Committee responsible for implementation of the Agreement between the governments of Slovenia and Croatia on the status and other legal issues related to investment, exploitation, and decommissioning of the Nuclear power plant Krsko. The responsible organizations, APO and ARAO together with NEK prepared all new technical and financial data and relevant inputs for the new revision in which several scenarios based on the accepted boundary conditions were investigated. The strategy of immediate dismantling was analyzed for planned and extended NPP life time together with linked radioactive waste and spent fuel management to calculate yearly annuity to be paid by the owners into the decommissioning funds in Slovenia and Croatia. The new Program incorporated among others new data on the LILW repository including the costs for siting, construction and operation of silos at the location Vrbina in Krsko municipality, the site specific Preliminary Decommissioning Plan for NPP Krsko which included besides dismantling and decontamination approaches also site specific activated and contaminated radioactive waste, and results from the referenced scenario for spent fuel disposal but at very early stage. Important inputs for calculations presented also new amounts of compensations to the local communities for different nuclear facilities which were taken from the supplemented Slovenian regulation and updated fiscal parameters (inflation, interest, discount factors) used in the financial model based on the current development in economical environment. From the obtained data the nominal and discounted costs for the whole nuclear program related to NPP Krsko which is jointly owned by Slovenia and Croatia have

NPP Krsko natural circulation performance evaluation

International Nuclear Information System (INIS)

Segon, Velimir; Bajs, Tomislav; Frogheri, Monica

1999-01-01

The present document deals with an evaluation of the natural circulation performance of the Krsko nuclear power plant. Two calculation have been performed using the NPP Krsko nodalization (both similar to the LOBI A2-77 natural circulation experiment) - the first with the present steam generators at NPP Krsko (Westinghouse, 18% plugged), the second with the future steam generators (Siemens, 0% plugged). The results were evaluated using the natural circulation flow map derived in /1/, and were compared to evaluate the influence of the new steam generators on the natural circulation performance. (author)

Application of the Commercial Grade Item (CGI) Dedication Process for Procurement of Nuclear Safety Related Items at Nuclear Power Plant Krsko (NEK)

International Nuclear Information System (INIS)

Heruc, Z.; Pozar, J.

1998-01-01

CGI procurement is a process whereby parts are brought without imposing Appendix B Quality Assurance requirements on the supplier, and than dedicated for use in safety-related applications. The dedication process involves 1) based upon required safety function, an engineering evaluation to identify critical characteristic of the item and specification of acceptance criteria; and 2) quality control activities to ensure the item(s) supplied meets the acceptance criteria specified. CGI Dedication supports the supply of certified components/parts for the plant operation in an environment where the number of nuclear qualified suppliers diminishes. It requires a more active role of the plant personnel, therefore presenting an additional burden on human resources, but at the same time increases the technical KNOW-HOW and improves the confidence of test and inspection data presented in the certificates. Very often it is also cost beneficial. This paper is a continuation to last year presentation of the introduction of this method into NEK's procurement process and presents the current approach and some practical examples. (author)

On-line maintenance PSA support at NPP Krsko

International Nuclear Information System (INIS)

Prosen, R.; Vrbanic, I.; Kastelan, M.

2000-01-01

In 1997 Krsko NPP initiated the on-line maintenance (OLM) practice. On-line maintenance constitutes of corrective activities, preventive activities, surveillance activities, tests and inspections, as well as calibrations and modifications, taking place during the normal power operations. The on-line maintenance is a multidisciplinary process consisting of activity specification, planning, and preparation and performing of the OLM activity of interest. The primary role of the PSA group is to assess from the r isk perspective , using the plant-specific NEK PSA model, system unavailability and the impact to the plant operational risk. The intent is to support planning of the on-line maintenance activities from the risk perspective. The risk evaluation of the OLM activities is based on the probability of core damage evaluation for the defined discrete plant configuration states, determined by the OLM activities. Within this application, the optimized, plant-specific PSA model is used on Risk Spectrum platform. To perform the risk assessment of the on-line maintenance activities, first the systems to be affected are defined based on the planned OLM activities. The next important step is the assessment of the planned work schedule. To define the final schedule, the co-ordination and optimizing the planned OLM activities needs activation of all participating departments, supported also from PSA group. The P3 (i.e. Primavera) planning tool system windows are defined for different systems and groups of systems, and the activities are sorted in particular weeks according to these windows. (author)

Development of Krsko Severe Accident Management Database (SAMD)

International Nuclear Information System (INIS)

Basic, I.; Kocnar, R.

1996-01-01

Severe Accident Management is a framework to identify and implement the Emergency Response Capabilities that can be used to prevent or mitigate severe accidents and their consequences. Krsko Severe Accident Management Database documents the severe accident management activities which are developed in the NPP Krsko, based on the Krsko IPE (Individual Plant Examination) insights and Generic WOG SAMGs (Westinghouse Owners Group Severe Accident Management Guidance). (author)

SB LOCA analyses for Krsko Full Scope Simulator verification

International Nuclear Information System (INIS)

Prosek, A.; Parzer, I.; Mavko, B.

2000-01-01

Nuclear power plant simulators are intended to be used for training and maintaining competence to ensure safe, reliable operation of nuclear power plants throughout the world. The simulator shall be specified to a reference unit and its performance validation testing shall be provided. In this study a small-break loss-of-coolant accident (SB LOCA) response of Krsko nuclear power plant (NPP) was calculated for full scope simulator verification. The investigation included five cases with varying the break size in the cold leg of reactor coolant system. The plant specific and verified RELAP5/MOD2 model of Krsko nuclear power plant (NPP), developed in the past for 1882 MWt power, was adapted for 2000 MWt power (cycle 17) including the model for replacement steam generators. The results showed that the plant system response to breaks with small break area was slower compared to breaks with larger break area. The core heatup occurred in most of the cases analyzed. The acceptance criteria for emergency core cooling system were also met. The predicted results of the SB LOCA analysis for Krsko NPP suggest that they may be used for verification of the Krsko Full Scope Simulator performance. (author)

Performance of nuclear fuel in the Krsko reactor; Spremljanje delovanja jedrskega goriva v reaktorju NE Krsko

Energy Technology Data Exchange (ETDEWEB)

Jurcevic, M; Kurincic, B; Levstek, M F; Sambo, B; Vrcko, P [Nuklearna elektrana Krsko, Krsko (Yugoslavia)

1987-07-01

In this paper activities to follow performance of the nuclear fuel and operational status of the reactor of Nuclear Power Plant Krsko are presented. Short descriptions of the methods as well as nuclear and process instrumentation used for surveillance of the reactor performance are given. The purpose of the subject activities is to assure safe operation of the reactor in accordance with the Final safety Analysis Report of NPP Krsko. (author)

Process Information System - Nuclear Power Plant Krsko

International Nuclear Information System (INIS)

Mandic, D.; Barbic, B.; Linke, B.; Colak, I.

1998-01-01

Original NEK design was using several Process Computer Systems (PCS) for both process control and process supervision. PCS were built by different manufacturers around different hardware and software platforms. Operational experience and new regulatory requirements imposed new technical and functional requirements on the PCS. Requirements such as: - Acquisition of new signals from the technological processes and environment - Implementation of new application programs - Significant improvement of MMI (Man Machine Interface) - Process data transfer to other than Main Control Room (MCR) locations - Process data archiving and capability to retrieve same data for future analysis were impossible to be implemented within old systems. In order to satisfy new requirements, NEK has decided to build new Process Information System (PIS). During the design and construction of the PIS Project Phase I, in addition to the main foreign contractor, there was significant participation of local architect engineering and construction companies. This paper presents experience of NEK and local partners. (author)

3D model of steam generator of nuclear power plant Krsko

International Nuclear Information System (INIS)

Ravnikar, I.; Petelin, S.

1995-01-01

The Westinghouse Electric Corporation D4 steam generator design was analyzed from a thermal-hydraulic point of view using the 3D PHOENICS computer code. Void fraction, velocity and enthalpy distributions were obtained in the U-tube riser. The boundary conditions of primary side were provided by SMUP 1D code. The calculations were carried out for present operating conditions of nuclear power plant Krsko. (author)

NPP Krsko Living PSA Concept

International Nuclear Information System (INIS)

Vrbanic, I.; Spiler, J.

2000-01-01

NPP Krsko developed PSA model of internal and external initiators within the frame of the Individual Plant Examination (IPE) project. Within this project PSA model was used to examine the existing plant design features. In order to continue with use of this PSA model upon the completion of IPE in various risk-informed applications in support of plant operation and evaluations of design changes, an appropriate living PSA concept needed to be defined. The Living PSA concept is in NPP Krsko considered as being a set of activities pursued in order to update existing PSA model in a manner that it appropriately represents the plant design, operation practice and history. Only a PSA model which is being updated in this manner can serve as a platform for plant-specific risk informed applications. The NPP Krsko living PSA concept is based on the following major ponts. First, the baseline PSA model is defined, which is to be maintained and updated and which is to be reference point for any risk-informed application. Second, issues having a potential for impact on baseline PSA model are identified and procedure and responsibilities for their permanent monitoring and evaluation are established. Third, manner is defined in which consequential changes to baseline PSA model are implemented and controlled, together with associated responsibilities. Finally, the process is defined by which the existing version of baseline PSA model is superseded by a new one. Each time a new version of baseline PSA model is released, it would be re-quantified and the results evaluated and interpreted. By documenting these re-quantifications and evaluations of results in a sequence, the track is being kept of changes in long-term averaged risk perspective, represented by long-term averaged frequencies of core damage and pre-defined release categories. These major topics of NPP Krsko living PSA concept are presented and discussed in the paper. (author)

Perspectives of Living PSA in NPP Krsko

International Nuclear Information System (INIS)

Vrbanic, I.; Kastelan, M.

1996-01-01

Nuclear power plant Krsko has completed the Level 1/Level 2 Probabilistic Safety Analysis (PSA) for internal initiating events and is in the process of completing the same for the external initiators. The analysis completed up to now has provided a valuable insight into a plant risk profile. In NPP Krsko there is a plan to use the PSA model as a permanent tool for the risk based applications and incorporate it into a decision making process. In order to achieve this there is a need to permanently maintain the PSA model in a manner that it reflects both the plan configuration/design at a time point and the operational experience up to the time point. All the activities aimed toward keeping the PSA model up-to-dated in this sense are usually referred to as a Living PSA (LPSA) program. NPP Krsko is in the process of defining and proceduralizing a LPSA program that would be plant specific and based on known world practices. Further, in order to be suitable for risk based applications the PSA model must be flexible in a sense that modifications to the base case model may be done easily and requantifications performed quickly as to evaluate various conditions imposed by real or hypothetical situations. NPP Krsko PSA model has been based on licensing type software. The requirements specified above dictate the transfer of the overall model to an application oriented software of newer generation with larger capabilities. The transfer becomes a part of a mentioned ongoing effort aimed at establishing LPSA model and concept. The paper present this effort and the perspectives of LPSA concept and risk based applications in NPP Krsko. (author)

Implementation of Industry Experience at Nuclear Power Plant Krsko

International Nuclear Information System (INIS)

Heruc, Z.; Kavsek, D.

2002-01-01

Being a standalone comparatively small unit NPP Krsko has adopted a business philosophy to incorporate industry experience into its daily operations. The continuos and safe operation of the unit is supported through feedback from other utilities (lessons learned) and equipment vendors and manufacturers. A permanent proactive approach in monitoring the international nuclear technology practices, standards changes and improvements, and upon feasibility review, introducing them into processes and equipment upgrades, is applied. As a member of the most important international integrations, NPP Krsko has benefited from the opportunity of sharing its experience with others (World Association of Nuclear Operators -WANO, Institute of Nuclear Power Operations - INPO, International Atomic Energy Agency - IAEA, Nuclear Operations Maintenance Information Service - NOMIS, Nuclear Maintenance Experience Exchange - NUMEX, Electric Power Research Institute - EPRI, Westinghouse Owners Group - WOG, etc.). Voluntary activities and good practices related to safety are achieved by international missions (IAEA Assessment of Safety Significant Events Team - ASSET, IAEA Operational Safety Review Team - OSART, WANO Peer Review, International Commission for Independent Safety Analysis - ICISA) and operating experience exchange programs through international organizations. These missions are promoting the highest levels of excellence in nuclear power plant operation, maintenance and support. With time, the practices described in this paper presented themselves as most contributing to safe and reliable operation of our power plant and at the same time supporting cost optimization making it a viable and reliable source of electrical energy in the more and more deregulated market. (author)

Revision of Krsko NPP Quality Assurance Plan

International Nuclear Information System (INIS)

Biscan, R.; Fifnja, I.; Kavsek, D.

2012-01-01

International standards from nuclear power plant operation area are being frequently upgraded and revised in accordance with the continuous improvement philosophy. This philosophy applies also to the area of Quality Assurance, which has also undergone significant improvement since the early 1950s. Besides just nuclear industry, there are also other international quality standards that are being continuously developed and revised, bringing needs for upgrades also in the nuclear application. Since the beginning of Krsko NPP construction, the overall Quality Assurance program and its applicable procedures were in place to assure that all planned and systematic actions necessary to provide adequate confidence that an item or service will satisfy given requirements to quality, are in place. The overall requirements for quality as one of the major objectives for Krsko NPP operation are also set forth in the Updated Safety Analyses Report, the document that serves as a base for operating license. During more than 30 years of Krsko NPP operation, the quality requirements and related documents were revised and upgraded in several attempts. The latest revision 6 of QD-1, Quality Assurance Plan was issued during the year 2011. The bases for the revision were: Changes of the Slovenian regulatory requirements (ZVISJV, JV5, JV9?), Changes of Krsko NPP licensing documents (USAR section 13?), SNSA inspection requirements, Changes of international standards (IAEA, ISO?), Conclusions of first PSR, Implementation of ISO standards in Krsko NPP (ISO14001, ISO17025), Changes of plant procedures, etc. One of the most obvious changes was the enlargement of the QA Plan scope to cover interdisciplinary areas defined in the plant management program MD-1, such as Safety culture, Self-assessment, Human performance, Industrial Safety etc. The attachment of the QA Plan defining relationships between certain standards was also updated to provide matrix for better correlation of requirements of

Supercompaction of radioactive waste at NPP Krsko

International Nuclear Information System (INIS)

Fink, K.; Sirola, P.

1996-01-01

The problem of radioactive waste management is both scientifically and technically complex and also deeply emotional issue. In the last twenty years the first two aspects have been mostly resolved up to the point of safe implementation. In the Republic of Slovenia, certain fundamentalist approaches in politics and the use of radioactive waste problem as a political tool, brought the final radioactive repository siting effort to a stop. Although small amounts of radioactive waste are produced in research institutes, hospitals and industry, major source of radioactive waste in Slovenia is the Nuclear Power Plant Krsko. When Krsko NPP was originally built, plans were made to construct a permanent radioactive waste disposal facility. This facility was supposed to be available to receive waste from the plant long before the on site storage facility was full. However, the permanent disposal facility is not yet available, and it became necessary to retain the wastes produced at the plant in the on-site storage facility for an extended period of time. Temporary radioactive storage capacity at the plant site has limited capacity and having no other options available NPP Krsko is undertaking major efforts to reduce waste volume generated to allow normal operation. This article describes the Radioactive Waste Compaction Campaign performed from November, 1994 through November, 1995 at Krsko NPP, to enhance the efficiency and safety of storage of radioactive waste. The campaign involved the retrieval, segmented gamma-spectrum measurement, dose rate measurement, compaction, re-packaging, and systematic storage of radioactive wastes which had been stored in the NPP radioactive waste storage building since plant commissioning. (author)

Outlet from the condenser of nuclear power plant Krsko into Sava river

International Nuclear Information System (INIS)

Rek, Z.

1990-01-01

Paper deals with hot water outflow from condenser of the Nuclear power plant Krsko into river Sava. We are interested in temperature and velocity field along the river. Boundary-domain integral method is used to solve a system of conservative equations. As a result, the time development of the velocity and temperature field at nodes of discrete model is obtained. (author)

NPP Krsko Aging Management Program

International Nuclear Information System (INIS)

Glaser, B.; Spiler, J.

2002-01-01

As a part of Periodic Safety Review Program (PSR) NEK will review and perform some activities related to Equipment Qualification (EQ) and Aging Management Program (AMP). (EQ) and AMP are safety factors, which need to be assessed during PSR. The goal of PSR and AMP is to determine aging effects and give the conclusion whether the plant has been managed to control aging related degradations and that safety margins are maintained. The parallel goal is also to establish AMP for future plant operation and provide basis for possible Life Extension Program. NEK will develop NEK Aging and Life Cycle Management Program, similar by format and content to one determined by License Renewal program. The bases are in 10CFR54, and NEI 95-10 Industry Guidelines for 10 CFR 54 implementation. The process of establishment the AMP is to be done in two steps. The first step is dealing with SSC's (Systems Structures and Components) scoping and screening and identification of TLAA's (Time Limited Aging Analyses). That means, that a database of all SSC's and TLAA's will be created and then evaluated within AMP program. Based on the scope in first phase an evaluation will be performed in step two. NEK will maintain AMP program as a living program that may be also used for Life Extension and Life Cycle Management. This paper will present and describe AMP, scoping and screening process and the results achieved through the first phase of the project.(author)

NPP Krsko Lifetime Extension - Business Impact for Hrvatska Elektroprivreda

International Nuclear Information System (INIS)

Vrankic, K.; Krejci, M.; Lebegner, J.

2006-01-01

This paper deals with the analysis of possible business impacts for HEP in the case of NPP Krsko life extension. Due to numerous reasons nuclear power plant life extension of ten to twenty years is a common procedure abroad. Having this practise in mind as well as other circumstances in Croatian and Slovenian electric power system, the extension of NPP Krsko lifetime is considered to be a possible scenario. Foreseeable impacts of this decision are evaluated primarily with consideration of its effect on HEPs projected cash flows, though other aspects will be addressed as well. Preserving a well maintained production facility with an extraordinary operational record and stable, or possibly falling overall production costs seems as a very rational choice. This is particularly true having in mind expected rise of electricity demand and energy prices in the region. Having NPP Krsko in operation beyond 2023 implies that no replacement source for NPP Krsko capacity needs to be built. This means avoiding all costs connected with the construction and operation of the replacement plant, assuming it will be fossil fuelled. Due to the high uncertainty of the future fossil fuel prices, the avoidance of replacement plant operational cost is likely to prove as highly rewarding. It should be kept in mind that avoided costs also include the replacement plant greenhouse gases emission costs, thus further enlarging the list of value adding impacts. The latter is valid anticipating the ratification of the Kyoto protocol and joining the European emission trading scheme. In addition to that, the extension of NPP Krsko lifetime would mean that the majority of costs connected with the decommissioning and final waste disposal can be postponed further down the time line. This will have very positive financial and possibly technological impact. Other value creating effects for HEP that are foreseeable as a consequence of the plant lifetime extension include: maintaining the knowledge of

Modernization of the Nuclear Power Plant Krsko with new steam generators

International Nuclear Information System (INIS)

Holz, R.; Stach, U.; Gloaguen, C.

2000-01-01

The contract for the replacement of two steam generators at NPP Krsko was awarded in February 1998 to the Consortium SIEMENS AG FRAMATOME S.A.. The time frame for the replacement outage was scheduled from April to June 2000. The replacement itself started with the plant shut down on 15 th of April 2000 and the plant was back on line on 15 th of June, so that after an intensive engineering period of more than two years the plant was off line only 62 days, as scheduled. This document deals with the various aspects of the replacement phase itself and the techniques used. During the last years conference the engineering and licensing phase of the project have been presented. (author)

Modernization of the Nuclear Power Plant Krsko with new steam generators

Energy Technology Data Exchange (ETDEWEB)

Holz, R; Stach, U [Siemens AG, Erlangen, Offenbach (Germany); Gloaguen, C [Framatome, Paris (France)

2000-07-01

The contract for the replacement of two steam generators at NPP Krsko was awarded in February 1998 to the Consortium SIEMENS AG FRAMATOME S.A.. The time frame for the replacement outage was scheduled from April to June 2000. The replacement itself started with the plant shut down on 15{sup th} of April 2000 and the plant was back on line on 15{sup th} of June, so that after an intensive engineering period of more than two years the plant was off line only 62 days, as scheduled. This document deals with the various aspects of the replacement phase itself and the techniques used. During the last years conference the engineering and licensing phase of the project have been presented. (author)

Regulatory review of NPP Krsko Periodic Safety Review

International Nuclear Information System (INIS)

Lovincic, D.; Muehleisen, A.; Persic, A.

2004-01-01

At the request of the Slovenian Nuclear Safety Administration (SNSA), Krsko NPP prepared a Periodic Safety Review (PSR) program in January 2001. This is the first PSR of NPP Krsko, the only nuclear power plant in Slovenia. The program was reviewed by the IAEA mission in May 2001 and approved by SNSA in July 2001. The program is made in accordance with the IAEA Safety Guide 'Periodic Safety Review of Operational Nuclear Power Plants' No. 50-SG-012 and with European practice. It contains a systematic review of operation of the NPP Krsko, including the review of the changes as a result of the modernization of the facility. The main tasks of PSR are review of plant status for each safety factor, development of aging and life cycle management program, review of seismic design and PSHA analysis and update of regulatory compliance program. The prioritization process of findings and action plan are also important tasks of PSR. The basic safety factors of the PSR review are: Operational Experience, Safety Assessment and Analyses, Equipment Qualification and Ageing Management, Safety Culture, Emergency Planing, Environmental Impact and Radioactive Waste, Compliance with license requirements and Prioritization. It had been agreed that SNSA will have reviewed all PSR reports generated during the PSR process. At the end of 2003 the PSR Summary Report with selected recommendations for action plan was completed and delivered to SNSA for review. The paper presents regulatory review of NPP Krsko PSR with emphasis on the evaluation of the PSR issues ranking process. (author)

Nuklearna Elektrarna Krskoanaging Technical Documentation for the 'Rightsized' 90's and Beyond

International Nuclear Information System (INIS)

Gradisar, D.; Freeland, K. R.

1996-01-01

Nuklearna Elektrarna Krsko was constructed as a turnkey plant, entering commercial service in 1981. NEK operates the plant with a unique management philosophy which has adapted well to the demands of today's business environment. Contributing to this success has been the NEK Management Information System (MIS) that has assisted NEK in 'making more with less'. A key element of the MIS is the Technical Document system, which includes the DCM (Document Control Module) and QRM (Quality Records Management), enabling the successful retrofit of the existing document management and 'turnkey' plant records environment to a new, thoroughly integrated system controlling plant operation and configuration management. The system integrates the Engineering Equipment and Configuration Management data systems, providing immediate, realtime cross-reference of plant equipment and plant modifications with technical documentation. (author)

Nuclear Oversight Function at Krsko NPP

International Nuclear Information System (INIS)

Bozin, B.; Kavsek, D.

2010-01-01

The nuclear oversight function is used at the Krsko NPP constructively to strengthen safety and improve performance. Nuclear safety is kept under constant examination through a variety of monitoring techniques and activities, some of which provide an independent review. The nuclear oversight function at the Krsko NPP is accomplished by Quality and Nuclear Oversight Division (SKV). SKV has completed its mission through a combination of compliance, performance and effectiveness-based assessments. The performance-based assessment is an assessment using various techniques (observations, interviews, walk-downs, document reviews) to assure compliance with standards and regulations, obtain insight into performance, performance trends and also to identify opportunities to improve effectiveness of implementation. Generally, the performance-based approach to oversight function is based on some essential elements. The most important one which is developed and implemented is an oversight program (procedure). The program focuses on techniques, activities and objectives commensurate with their significance to plant operational safety. These techniques and activities are: self-assessments, assessments, audits, performance indicators, monitoring of corrective action program (CAP), industry independent reviews (such as IAEA's OSART and WANO Peer Review), industry benchmarking etc. Graded approach is an inherent product of a performance based program and ranking process. It is important not only to focus on the highest ranked performance based attributes but to lead to effective utilization of an oversight program. The attributes selected for oversight need to be based on plant specific experience, current industry operating experience, supplier's performance and quality issues. Collaboration within the industry and effective utility oversight of processes and design activities are essential for achieving good plant performance. So the oversight program must integrate relevant

CoNekT: an open-source framework for comparative genomic and transcriptomic network analyses.

Science.gov (United States)

Proost, Sebastian; Mutwil, Marek

2018-05-01

The recent accumulation of gene expression data in the form of RNA sequencing creates unprecedented opportunities to study gene regulation and function. Furthermore, comparative analysis of the expression data from multiple species can elucidate which functional gene modules are conserved across species, allowing the study of the evolution of these modules. However, performing such comparative analyses on raw data is not feasible for many biologists. Here, we present CoNekT (Co-expression Network Toolkit), an open source web server, that contains user-friendly tools and interactive visualizations for comparative analyses of gene expression data and co-expression networks. These tools allow analysis and cross-species comparison of (i) gene expression profiles; (ii) co-expression networks; (iii) co-expressed clusters involved in specific biological processes; (iv) tissue-specific gene expression; and (v) expression profiles of gene families. To demonstrate these features, we constructed CoNekT-Plants for green alga, seed plants and flowering plants (Picea abies, Chlamydomonas reinhardtii, Vitis vinifera, Arabidopsis thaliana, Oryza sativa, Zea mays and Solanum lycopersicum) and thus provide a web-tool with the broadest available collection of plant phyla. CoNekT-Plants is freely available from http://conekt.plant.tools, while the CoNekT source code and documentation can be found at https://github.molgen.mpg.de/proost/CoNekT/.

The impact of NPP Krsko steam generator tube plugging on minimum DNBR at nominal conditions

International Nuclear Information System (INIS)

Lajtman, S.

1996-01-01

Typically, steam generator tube plugging (SGTP) both decreases the reactor coolant system (RCS) flow rate and the heat transfer surface area of the steam generator. At a constant thermal power and vessel outlet temperature, as tube plugging increases, the vessel average temperature, vessel inlet temperature and steam generator secondary side steam pressure decrease. This paper presents the analysis of impact of SGTP on Minimum Departure from Nucleate Boiling Ratio (MDNBR) at NPP Krsko (NEK), using the Improved Thermal Design Procedure (ITDP), WRB-1 correlation, and COBRA-III-C computer code. No credit was given to high plugging percentage region power reduction resulting from turbine volumetric flow limitations. MDNBR is found to be decreasing with increasing plugging, but not under the limiting values. (author)

The simulator Neck-Mfgs and its training status

International Nuclear Information System (INIS)

Setnikar, T.; Pribozic, F.; Srebotnjak, E.; Gortnar, O.; Kovacic, J.; Stritar, A.

1998-01-01

This paper presents the status and training possibilities on Krsko NPP Multi-Functional Simulator (NEK-MFS). Since spring 1997 it serves as a training facility in Nuclear Training Center. During first year of operation the simulator NEK-MFS was found to be a very useful Krsko NPP specific tool which is capable to support both the initial operator training program and licensed operator retraining activities.(author)

Configuration management at NEK

International Nuclear Information System (INIS)

Podhraski, M.

1999-01-01

Configuration Management (CM) objectives at NEK are to ensure consistency between Design Requirements, Physical Plant Configuration and Configuration Information. Software applications, supporting Design Change, Work Control and Document Control Processes, are integrated in one module-oriented Management Information System (MIS). Master Equipment Component List (MECL) database is central MIS module. Through a combination of centralized database and process migrated activities it is ensured that the CM principles and requirements (accurate, current design data matching plant's physical configuration while complying to applicable requirements), are followed and fulfilled.(author)

Phylogenetic analysis of the Neks reveals early diversification of ciliary-cell cycle kinases.

Directory of Open Access Journals (Sweden)

Jeremy D K Parker

2007-10-01

Full Text Available NIMA-related kinases (Neks have been studied in diverse eukaryotes, including the fungus Aspergillus and the ciliate Tetrahymena. In the former, a single Nek plays an essential role in cell cycle regulation; in the latter, which has more than 30 Neks in its genome, multiple Neks regulate ciliary length. Mammalian genomes encode an intermediate number of Neks, several of which are reported to play roles in cell cycle regulation and/or localize to centrosomes. Previously, we reported that organisms with cilia typically have more Neks than organisms without cilia, but were unable to establish the evolutionary history of the gene family.We have performed a large-scale analysis of the Nek family using Bayesian techniques, including tests of alternate topologies. We find that the Nek family had already expanded in the last common ancestor of eukaryotes, a ciliated cell which likely expressed at least five Neks. We suggest that Neks played an important role in the common ancestor in regulating cilia, centrioles, and centrosomes with respect to mitotic entry, and that this role continues today in organisms with cilia. Organisms that lack cilia generally show a reduction in the number of Nek clades represented, sometimes associated with lineage specific expansion of a single clade, as has occurred in the plants.This is the first rigorous phylogenetic analysis of a kinase family across a broad array of phyla. Our findings provide a coherent framework for the study of Neks and their roles in coordinating cilia and cell cycle progression.

Limited Releases of Krsko NPP

International Nuclear Information System (INIS)

Breznik, B.; Kovac, A.

2001-01-01

Full text: Krsko Nuclear Power Plant is about 700 MW Pressurised Water Reactor plant located in Slovenia close to the border with Croatia. The authorised limit for the radioactive releases is basically set to 50 μSv effective dose per year to the members of the public. There is also additional limitation of total activities released in a year and concentration. The poster presents the effluents of the year 2000 and evaluated dose referring to the limits and to the natural and other sources of radiation around the plant. (author)

Frequent Nek1 overexpression in human gliomas

Energy Technology Data Exchange (ETDEWEB)

Zhu, Jun [School of Biomedical Engineering, Shanghai Jiao Tong University, Shanghai (China); Neurosurgery Department, Ruijin Hospital, Shanghai Jiao Tong University School of Medicine, Shanghai (China); Cai, Yu, E-mail: aihaozuqiu22@163.com [School of Biomedical Engineering, Shanghai Jiao Tong University, Shanghai (China); Neurosurgery Department, Ruijin Hospital, Shanghai Jiao Tong University School of Medicine, Shanghai (China); Liu, Pin [Med-X Research Institute, Shanghai Jiao Tong University, Shanghai (China); Zhao, Weiguo [Neurosurgery Department, Ruijin Hospital, Shanghai Jiao Tong University School of Medicine, Shanghai (China)

2016-08-05

Never in mitosis A (NIMA)-related kinase 1 (Nek1) regulates cell cycle progression to mitosis. Its expression and potential functions in human gliomas have not been studied. Here, our immunohistochemistry (IHC) assay and Western blot assay results showed that Nek1 expression was significantly upregulated in fresh and paraffin-embedded human glioma tissues. Its level in normal brain tissues was low. Nek1 overexpression in human gliomas was correlated with the proliferation marker (Ki-67), tumor grade, Karnofsky performance scale (KPS) and more importantly, patients’ poor survival. Further studies showed that Nek1 expression level was also increased in multiple human glioma cell lines (U251-MG, U87-MG, U118, H4 and U373). Significantly, siRNA-mediated knockdown of Nek1 inhibited glioma cell (U87-MG/U251-MG) growth. Nek1 siRNA also sensitized U87-MG/U251-MG cells to temozolomide (TMZ), causing a profound apoptosis induction and growth inhibition. The current study indicates Nek1 might be a novel and valuable oncotarget of glioma, it is important for glioma cell growth and TMZ-resistance. - Highlights: • Nek1 is upregulated in multiple human glioma tissues and cell lines. • Nek1 overexpression correlates with glioma grades and patients’ KPS score. • Nek1 overexpression correlates with patients’ poor overall survival. • siRNA knockdown of Nek1 inhibits glioma cell growth. • siRNA knockdown of Nek1 sensitizes human glioma cells to temozolomide.

Frequent Nek1 overexpression in human gliomas

International Nuclear Information System (INIS)

Zhu, Jun; Cai, Yu; Liu, Pin; Zhao, Weiguo

2016-01-01

Never in mitosis A (NIMA)-related kinase 1 (Nek1) regulates cell cycle progression to mitosis. Its expression and potential functions in human gliomas have not been studied. Here, our immunohistochemistry (IHC) assay and Western blot assay results showed that Nek1 expression was significantly upregulated in fresh and paraffin-embedded human glioma tissues. Its level in normal brain tissues was low. Nek1 overexpression in human gliomas was correlated with the proliferation marker (Ki-67), tumor grade, Karnofsky performance scale (KPS) and more importantly, patients’ poor survival. Further studies showed that Nek1 expression level was also increased in multiple human glioma cell lines (U251-MG, U87-MG, U118, H4 and U373). Significantly, siRNA-mediated knockdown of Nek1 inhibited glioma cell (U87-MG/U251-MG) growth. Nek1 siRNA also sensitized U87-MG/U251-MG cells to temozolomide (TMZ), causing a profound apoptosis induction and growth inhibition. The current study indicates Nek1 might be a novel and valuable oncotarget of glioma, it is important for glioma cell growth and TMZ-resistance. - Highlights: • Nek1 is upregulated in multiple human glioma tissues and cell lines. • Nek1 overexpression correlates with glioma grades and patients’ KPS score. • Nek1 overexpression correlates with patients’ poor overall survival. • siRNA knockdown of Nek1 inhibits glioma cell growth. • siRNA knockdown of Nek1 sensitizes human glioma cells to temozolomide.

Industry Operating Experience Process at Krsko NPP

International Nuclear Information System (INIS)

Bach, B.; Bozin, B.; Cizmek, R.

2012-01-01

Experience has shown that number of minor events and near misses, usually without immediate or significant impact to plant safety and reliability, are precursors of significant or severe events due to the same or similar root or apparent cause(s). It is therefore desirable to identify and analyze weaknesses of the precursor problems (events) in order to prevent occurrence of significant events. Theoretically, significant events could be prevented from occurring if the root cause(s) of these precursor problems could be identified and eliminated. The Operating Experience Program identifies such event precursors and by reporting them to the industry, plant specific corrective actions can be taken to prevent events at other operational plants. The intent of the Operating Experience Program is therefore to improve nuclear power plant safety and reliability of the operating nuclear power plants. Each plant develops its own Operating Experience Program in order to learn from the in-house operating experience as well as from the world community of nuclear plants. The effective use of operating experience includes analyzing both plant and industry events in order to identify fundamental weaknesses and then determining appropriate plant-specific actions that will minimize the likelihood of similar events. Learning and applying the lessons from operating experience is an integral part of station safety culture and is encouraged by managers throughout the top plant administrative programs and procedures. Krsko NPP is developed it own Operating Experience Program by using the most relevant INPO/WANO/IAEA guidelines as well as its own knowledge, skills an operating practice. The Operating Experience Program is a part of the Corrective Action Program, which is among top management programs, thus program is strongly encouraged by top management. The purpose of Operating Experience Program is to provide guidance for using, sharing, and evaluating operating experience information

Operating Experience at NPP Krsko

International Nuclear Information System (INIS)

Kavsek, D.; Bach, B.

1998-01-01

Systematic analysis of operational experience by assessment of internal and industry events and the feedback of lessons learned is one of the essential activities in the improvement of the operational safety and reliability of the nuclear power plant. At NPP Krsko we have developed a document called ''Operating Experience Assessment Program''. Its purpose is to establish administrative guidance for the processing of operating events including on-site and industry events. Assessment of internal events is based on the following methods: Event and Causal Factor Charting, Change Analysis, Barrier Analysis, MORT (Management Oversight and Risk Tree Analysis) and Human Performance Evaluation. The operating experience group has developed a sophisticated program entitled ''Operating experience tracking system'' (OETS) in response to the need for a more efficient way of processing internal and industry operating experience information. The Operating Experience Tracking System is used to initiate and track operational events including recommended actions follow up. Six screens of the system contain diverse essential information which allows tracking of operational events and enables different kinds of browsing. OETS is a part of the NPP Krsko nuclear network system and can be easily accessed by all plant personnel. (author)

Modeling of containment response for Krsko NPP Full Scope Simulator verification

International Nuclear Information System (INIS)

Kljenak, I.; Skerlavaj, A.

2000-01-01

Containment responses during the first 10000 s of Anticipated Transient Without Scram and Small Break Loss-of-Coolant Accident scenarios in the Krsko two-loop Westinghouse pressurized water reactor nuclear power plant were simulated with the CONTAIN computer code. Sources of coolant were obtained from simulations with the RELAP5 code. The simulations were carried out so that the results could be used for the verification of the Krsko Full Scope Simulator. (author)

Krsko 2 Project Preparation and Status

International Nuclear Information System (INIS)

Novsak, M.; Spiler, J.; Bergant, R.; Zagar, T.

2008-01-01

The Government of the Republic of Slovenia has adopted a document 'Resolution on National Development Projects for the period 2007 - 2023' in October 2006. Among several projects which all support sustainable development of Slovenia, an option of a new nuclear power plant was proposed. Thus, the Slovenian Government showed obvious intention and direction of Slovenian future energetic situation. The supply of electricity has been sharpening in Slovenia in the last few years. Growing of gross domestic product (GDP) and approaching to the life standard of developed EU countries has caused increased consumption of electricity. Since domestic electricity production does not follow the increased consumption, Slovenia already imports nearly a quarter of its needed electricity. Slovenia would need 400 MW of installed electrical power now for covering of its base load needs only. Based on recent electricity consumption forecasts, Slovenia will need 800 MW of new electricity generation capacities by 2015 and 1500 MW by 2025 respectively. Besides high annual growth rate and high dependence on electricity import, a problem of relatively old power generation objects and realization of new energy and climate package for Europe exists. All together dictates our options for expansion of capacity production of the proposed Nuclear power plant Krsko 2. Experience and knowledge of light water pressurized reactor can be effectively used at NPP Krsko 2. Planned NPP Krsko 2 would have between 1100 and 1600 MW of installed electrical power. If the decision is taken in 2009, construction could start in 2013 and finish in 2017. (author)

Safety Culture Survey in Krsko NPP

International Nuclear Information System (INIS)

Strucic, M.; Bilic Zadric, T.

2008-01-01

The high level of nuclear safety, stability and competitiveness of electricity production, and public acceptability are the main objectives of Krsko Nuclear Power Plant. This is achievable only in environment where strong Safety Culture is taking dominant place in the way how employees communicate, perform tasks, share their ideas and attitudes, and demonstrate their concern in all aspects of work and coexistence. To achieve these objectives, behaviour of all employees as well as specific ethical values must become more transparent and that must arise from the heart of organization. Continuous ongoing and periodic self assessments of Safety Culture in Krsko NPP present major tools in implementation process of this approach. Benefits from Periodic interdisciplinary focused self assessment approach, which main intention is finding the strengths and potential areas for improvements, was used second time to assess the area of Safety Culture in Krsko NPP. Main objectives of self assessment, performed in 2006, were to increase the awareness of the present culture, to serve as a basis for improvement and to keep track of the effects of change or improvement over a longer period of time. For the purpose of effective self assessment, extensive questionnaire was used to obtain information that is representative for whole organization. Wide range of questions was chosen to cover five major characteristics of safety culture: Accountability for safety is clear, Safety is integrated into all activities, Safety culture is learning-driven, Leadership for safety is clear and Safety is a clearly recognized value. 484 Krsko NPP employees and 96 contractors were participated in survey. 70-question survey provided information that was quantified and results compared between groups. Anonymity of participant, as well as their willingness to contribute in this assessment implicates the high level of their openness in answering the questions. High number of participant made analysis of

Arrangement of the Krsko NPP protection scheme for the power system malfunction cases

International Nuclear Information System (INIS)

Omahen, P.; Pavsek, J.; Dirnbek, V.

1996-01-01

The Krsko NPP has been designed with the capability to reject 100% of its rated power and runback to the station electrical load. However, an adequate detection system of the outside network degradation is needed for the activation of the existing load drop anticipated (LDA) function. The Krsko NPP electrical, turbine and generator protection systems were carefully evaluated in order to redesign some of its functions. These additional functions should be able to protect and disconnect the plant from the system whenever some serious trouble of the outside electric power system is detected. On the other side, preventive measures should be introduced to avoid unnecessary plant disconnection or unnecessary power system collapse due to such disconnection. At the end, the paper presents a precise design of additional function possibilities for the Krsko NPP electrical protection system. A critical evaluation of these functions is given and the best option is proposed. (author)

System, economy and ecology viewpoints of the Krsko NPP lifetime extension

International Nuclear Information System (INIS)

Novsak, M.; Spiler, J.; Zagar, T.; Pirs, B.; Bole, A.; Bregar, Z.; Cuhalev, I.; Derganc, B.; Ivanjko, S.; Matvoz, D.; Sustersic, A.; Valencic, L.; Zabric, I.; Zlatarev, G.; Babuder, M.

2007-01-01

Krsko NPP plant life extension was analysed and evaluated with respect to system, economy and ecology viewpoints. From the system perspective it was established that also in the extended lifetime the plant will remain in operation as a base load electricity supplier. The systematic review was performed to determine its overall competitiveness against advanced coal, gas and new nuclear units. The analysis considered also hydro and renewable sources. Analysis and evaluations resulted in the conclusion that the Krsko NPP lifetime extension is the most effective alternative for base load production due to small additional capital investments, low fuel costs, no new siting requirements, lowest climate and environmental impact, and reliable and safe operation. (author)

NPP Krsko core calculations to improve operational safety

International Nuclear Information System (INIS)

Ivekovic, I.; Grgic, D.; Nemec, T.

2007-01-01

Calculation tools and methodology used to perform independent calculations of cumulative influence of different changes related to fuel and core operation of NPP Krsko were described. Some examples of steady state and transient results are used to illustrate potential improvements to understanding and reviewing plant safety. (author)

NPP Krsko simulator training for operations personnel

International Nuclear Information System (INIS)

Pribozic, F.; Krajnc, J.

2000-01-01

Acquisition of a full scope replica simulator represents an important achievement for Nuclear power Plant Krsko. Operating nuclear power plant systems is definitely a set of demanding and complex tasks. The most important element in the goal of assuring capabilities for handling such tasks is efficient training of operations personnel who manipulate controls in the main control room. Use of a simulator during the training process is essential and can not be substituted by other techniques. This article gives an overview of NPP Krsko licensed personnel training historical background, current experience and plans for future training activities. Reactor operator initial training lasts approximately two and a half years. Training is divided into several phases, consisting of theoretical and practical segments, including simulator training. In the past, simulator initial training and annual simulator retraining was contracted, thus operators were trained on non-specific full scope simulators. Use of our own plant specific simulator and associated infrastructure will have a significant effect on the operations personnel training process and, in addition, will also support secondary uses, with the common goal to improve safe and reliable plant operation. A regular annual retraining program has successfully started. Use of the plant specific simulator assures consistent training and good management oversight, enhances conformity of operational practices and supports optimization of operating procedures. (author)

Reracking Possibilities of the NPP Krsko Spent Fuel Pool

International Nuclear Information System (INIS)

Bace, M.; Pevec, D.; Smuc, T.

1998-01-01

Using the SCALE-4 code package reracking possibilities of the NPP Krsko spent fuel pool were analyzed. Two cases were considered: the first case assuming the 40 years lifetime of the plant, and the second case assuming the 50 years lifetime of the plant. It was shown that it is possible to design the additional racks in free space of the spent fuel pool with the sufficient total capacity to store all the spent fuel generated during the 40 years lifetime of the plant. In the case of 50 years plant lifetime, completely new racks (capacity of 1890 spent fuel assemblies), containing 4mm boral in storage cell walls, were proposed for the NPP Krsko spent fuel pool. The effective multiplication factor of the spent fuel pool fully loaded with new racks containing spent fuel assemblies of initial enrichment 4.3 w/o, burned to 40 GWd/tU and cooled 2 years is lower than the value required by standard. It showed the possibility of the safe disposal of all spent fuel accumulated during more than 50 years lifetime of the plant. (author)

Transition cycle fuel management problems of NPP Krsko; Problemi gospodarenje gorivom u prijelaznim ciklusima NE Krsko

Energy Technology Data Exchange (ETDEWEB)

Petrovic, B [Institut ' Rudjer Boskovic' , Zagreb (Yugoslavia); Pevec, D [Elektrotehnicki fakultet, Zagreb (Yugoslavia); Smuc, T; Urli, N [Institut ' Rudjer Boskovic' , Zagreb (Yugoslavia)

1989-07-01

Transition cycle fuel management problems are described and illustrated using results and experience attained during core reload design of NPP Krsko. Improved version of computer code package PSU-LEOPARD/Mcrac is successfully applied to NPP Krsko loading pattern design. (author)

Equipment Reliability Process in Krsko NPP

International Nuclear Information System (INIS)

Gluhak, M.

2016-01-01

To ensure long-term safe and reliable plant operation, equipment operability and availability must also be ensured by setting a group of processes to be established within the nuclear power plant. Equipment reliability process represents the integration and coordination of important equipment reliability activities into one process, which enables equipment performance and condition monitoring, preventive maintenance activities development, implementation and optimization, continuous improvement of the processes and long term planning. The initiative for introducing systematic approach for equipment reliability assuring came from US nuclear industry guided by INPO (Institute of Nuclear Power Operations) and by participation of several US nuclear utilities. As a result of the initiative, first edition of INPO document AP-913, 'Equipment Reliability Process Description' was issued and it became a basic document for implementation of equipment reliability process for the whole nuclear industry. The scope of equipment reliability process in Krsko NPP consists of following programs: equipment criticality classification, preventive maintenance program, corrective action program, system health reports and long-term investment plan. By implementation, supervision and continuous improvement of those programs, guided by more than thirty years of operating experience, Krsko NPP will continue to be on a track of safe and reliable operation until the end of prolonged life time. (author).

Calculation of Environmental Conditions in NEK Intermediate Building Following HELB

International Nuclear Information System (INIS)

Grgic, D.; Spalj, S.; Basic, I.

1998-01-01

The purpose of Equipment Qualification (EQ) in nuclear power plants is to ensure the capability of safety related equipment to perform its function on demand under postulated service conditions, including harsh accident environment (e.g. Loss of Coolant Accident - LOCA, High Energy Line Break - HELB). The determination of the EQ conditions and zones is one of the basic steps in the frame of the overall EQ project. The EQ parameters (temperature, pressure, relative humidity, chemical spray, submergence, radiation) should be defined for all locations of the plant containing equipment important to safety. This paper presents the calculation of thermohydraulic environmental parameters (pressure and temperature) inside Intermediate Building (IB) of Krsko NPP after the postulated HELB. The RELAP5/mod2 computer code was used for the determination of HELB mass and energy release and computer code GOTHIC was used to calculate pressure and temperature profiles inside NPP Krsko IB. (author)

Performance assessment for Nuclear Power Plant Krsko intermediate and low-level rad-waste repository

International Nuclear Information System (INIS)

Jelavic, V.; Skanata, D.; Plecjas, I.

1990-01-01

Performance safety Assessment for NPP Krsko radwaste repository was performed (LLW/ILW). Shallow land and tunnel type concept were analyzed. Because it was based on two unknown referent sites, one for the shallow land concept and the other for the tunnel type, analysis was generic in nature. Scenario selecting process and consequence analysis were performed by using deterministic approach. Results for both concepts of disposal suggests that proposed NPP Krsko radwaste repository reference site and disposal technology will fully meet radiation limits imposed by the Yugoslav regulations and ICRP guidelines. (author)

Central alarm system replacement in NPP Krsko

International Nuclear Information System (INIS)

Cicvaric, D.; Susnic, M.; Djetelic, N.

2004-01-01

Current NPP Krsko central alarm system consists of three main segments. Main Control Board alarm system (BETA 1000), Ventilation Control Board alarm system (BETA 1000) and Electrical Control Board alarm system (BETA 1100). All sections are equipped with specific BetaTone audible alarms and silence, acknowledge as well as test push buttons. The main reason for central alarm system replacement is system obsolescence and problems with maintenance, due to lack of spare parts. Other issue is lack of system redundancy, which could lead to loss of several Alarm Light Boxes in the event of particular power supply failure. Current central alarm system does not provide means of alarm optimization, grouping or prioritization. There are three main options for central alarm system replacement: Conventional annunciator system, hybrid annunciator system and advanced alarm system. Advanced alarm system implementation requires Main Control Board upgrade, integration of process instrumentation and plant process computer as well as long time for replacement. NPP Krsko has decided to implement hybrid alarm system with patchwork approach. The new central alarm system will be stand alone, digital, with advanced filtering and alarm grouping options. Sequence of event recorder will be linked with plant process computer and time synchronized with redundant GPS signal. Advanced functions such as link to plant procedures will be implemented with plant process computer upgrade in outage 2006. Central alarm system replacement is due in outage 2004.(author)

Brief Assessment of Krsko NPP Decommissioning Costs

International Nuclear Information System (INIS)

Skanata, D.; Medakovic, S.; Debrecin, N.

2000-01-01

The first part of the paper gives a brief description of decommissioning scenarios and models of financing the decommissioning of NPPs. The second part contains a review of decommissioning costs for certain PWR plants with a brief description of methods used for that purpose. The third part of the paper the authors dedicated to the assessment of decommissioning costs for Krsko NPP. It does not deal with ownership relations and obligations ensuing from them. It starts from the simple point that decommissioning is an structure of the decommissioning fund is composed of three basic cost items of which the first refers to radioactive waste management, the second to storage and disposal of the spent nuclear fuel and the third to decommissioning itself. The assessment belongs to the category of preliminary activities and as such has a limited scope and meaning. Nevertheless, the authors believe that it offers a useful insight into the basic costs that will burden the decommissioning fund of Krsko NPP. (author)

Radiation protection programme at Krsko nuclear power plant

International Nuclear Information System (INIS)

Breznik, B.

1996-01-01

Krsko NPP, a Westinghouse two-loop PWR of 632 M We power, is in commercial operation since 1982. Reduction of radioactive releases to the environment and the reduction of doses to workers is the basic goal in the plant radiological protection. The radiation protection programme is established to ensure that the radiation exposures to workers and members of the public are minimized according to the As Low As Reasonably Achievable approach and controlled in accordance with international safety standards and Slovenian regulations. The basis for the operational and technical measures has been provided according to the industrial good practice. The effluent control is based on the Standard Radioactive Effluent Technical Specifications, and environmental surveillance is established according to the programme defined by the regulations. The dose constraints and performance indicators are used to assure the effectiveness of the radiation protection programme and provide a convenient follow-up tool. The monitoring programme results of each year show that there is no measurable dose to the public due to radioactive releases. The commitment to the dose burden of any member of a critical group is assessed to be below the dose constraint. Individual and collective doses of the workers are within a range typical for the PWRs of a similar type. (author)

Performance assessment for Nuclear Power Plant Krsko intermediate and low-level rad-waste repository; Provjera sigurnosnih performansi odlagalishta radioaktivnog otpada niske i srednje aktivnosti nuklearne elektrane Krsko

Energy Technology Data Exchange (ETDEWEB)

Jelavic, V [Inst. za Elektroprivredu, Zagreb. (Yugoslavia).; Tankosic, Dj [Bechtel Inc., San Francisco (United States); Skanata, D [Nuklearna elektrana Krshko, Krshko (Yugoslavia); Plecjas, I [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

1990-07-01

Performance safety Assessment for NPP Krsko radwaste repository was performed (LLW/ILW). Shallow land and tunnel type concept were analyzed. Because it was based on two unknown referent sites, one for the shallow land concept and the other for the tunnel type, analysis was generic in nature. Scenario selecting process and consequence analysis were performed by using deterministic approach. Results for both concepts of disposal suggests that proposed NPP Krsko radwaste repository reference site and disposal technology will fully meet radiation limits imposed by the Yugoslav regulations and ICRP guidelines. (author)

Quality of Industry Support to NPP Krsko

International Nuclear Information System (INIS)

Nemcic, K.

2008-01-01

NPP Krsko developed program for Supplier evaluation and performance. During the regular control of suppliers and evaluation of industry support to NPP Krsko quality problems were reported. Different quality systems were evaluated and different suppliers as: design organizations, equipment manufacturers, material vendors were audited or surveillance was performed. This paper discuss and report various cases where quality issues were problems based on audit results and present actions and efforts undertaken by the NE Krsko Quality Assurance Department to improve performance of the contractors, vendors, suppliers. New and different quality standards as approach in numerous articles are described as improvement or quality changes but also 'different opinion exist'. This paper also presents the author view and approach how to solve the possible future problems with different quality systems and organisations used by industry who support daily operation of NE Krsko and give recommendations for future nuclear projects.(author)

Shutdown Safety in NEK

International Nuclear Information System (INIS)

Gluhak, Mario; Senegovic, Marko

2014-01-01

Industry performance analysis since 2004 has revealed that 23% of the events reported to WANO occurred during outage periods. Given the fact that a plant is in the outage only 5 percent of the time, this emphasizes the importance of shutdown safety and measures station staffs undertake to maintain effective barriers to safety margins during the outage. Back in 1990s, the industry adopted guidance to meet safety requirements by focusing on safety functions. Both WANO and INPO released various documents, reports and guidelines to help accomplish those requirements. However, in the last decade inadequate 'defence in depth' has led to several events affecting shutdown safety and challenging one of the most important nuclear safety principles: 'The special characteristics of nuclear technology are taken into account in all decisions and actions. Reactivity control, continuity of core cooling, and integrity of fission product barriers are valued as essential, distinguishing attributes of nuclear station work environment'. NEK has recognized the importance of 'defence in depth'Industry performance analysis since 2004 has revealed that 23% of the events reported to WANO occurred during outage periods. Given the fact that a plant is in the outage only 5 percent of the time, this emphasizes the importance of shutdown safety and measures station staffs undertake to maintain effective barriers to safety margins during the outage. Back in 1990s, the industry adopted guidance to meet safety requirements by focusing on safety functions. Both WANO and INPO released various documents, reports and guidelines to help accomplish those requirements. However, in the last decade inadequate 'defence in depth' has led to several events affecting shutdown safety and challenging one of the most important nuclear safety principles: 'The special characteristics of nuclear technology are taken into account in all decisions and actions. Reactivity

Neutron doze distribution in capsules for surveillance of radiation embrittlement of pressure vessel in Krsko nuclear power plant; Porazdelitev nevtronske doze v sondah za kontrolo povecanja krhkosri tlacne posode JE Krsko

Energy Technology Data Exchange (ETDEWEB)

Najzer, M; Remec, I; Kodeli, I [Institut Jozef Stefan, Ljubljana (Yugoslavia)

1984-07-01

Calculation of neutron fluence and spectrum distribution in the capsule with samples for radiation embrittlement of PWR pressure vessel surveillance program of Krsko nuclear power plant is presented. Two dimensional computer code DOT 3 has been used and neutron cross sections were taken from DLC-2D library. result is that fluence magnitude in the capsules changes for up to 70%, so when evaluating results of mechanical tests of samples it is necessary to take into account actual position of samples within the capsule. (author)

Axial blanket enrichment optimization of the NPP Krsko fuel

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

2001-01-01

In this paper optimal axial blanket enrichment of the NPP Krsko fuel is investigated. Since the optimization is dictated by economic categories that can significantly vary in time, two step approach is applied. In the first step simple relationship between the equivalent change in enrichment of axial blankets and central fuel region is established. The relationship is afterwards processed with economic criteria and constraints to obtain optimal axial blanket enrichment. In the analysis realistic NPP Krsko conditions are considered. Except for the fuel enrichment all other fuel characteristics are the same as in the fuel used in the few most recent cycles. A typical reload cycle after the plant power uprate is examined. Analysis has shown that the current blanket enrichment is close to the optimal. Blanket enrichment reduction results in an approximately 100 000 US$ savings per fuel cycle.(author)

Use of the deterministic safety analyses in support to the NPP Krsko modification

International Nuclear Information System (INIS)

Feretic, D.; Cavlina, N.; Debrecin, N.; Grgic, D.; Bajs, T.; Spalj, S.

2004-01-01

The ultimate goal of the safety analysis is to verify that Nuclear Power Plant (NPP) meets safety and operational requirements. To this aim it is necessary to demonstrate that plant safety has not been deteriorated in the case of the modifications to the plant Systems, Structures and Components (SSC) or changes to the plant procedures. In addition, safety analyses are needed in the case of reassessment of an existing plant. The reasons for reassessment may be different, e.g. due to the changes in the methodology and assumptions used in the original design, if the original design basis or acceptance criteria may no longer be adequate, if the safety analysis tools used may have been superseded by more sophisticated methods or if the original design basis may no longer be met. The operation of the NPP Krsko has experienced numerous changes from the original design for the majority of the reasons that have been mentioned before. On the other side, the application of the large best-estimate thermalhydraulic codes has evolved to the wide spread support in the operation of the NPP: compliance with the regulatory goals, support to the PSA studies, analysis of the operational transients, plant modifications studies, equipment qualification, training of the operators, preparation of the operating procedures, etc. This trend has been followed at the Faculty of Electrical Engineering Zagreb (FER) and applied to the on-going needs due to the modifications and changes at NPP Krsko. In this paper, an overview of the deterministic safety analyses performed at FER in the support to the NPP Krsko modifications and changes is presented.(author)

Anks3 alters the sub-cellular localization of the Nek7 kinase

Energy Technology Data Exchange (ETDEWEB)

Ramachandran, Haribaskar; Engel, Christina; Müller, Barbara [Renal Division, Department of Medicine, University Freiburg Medical Center, Hugstetter Str. 55, 79106 Freiburg (Germany); Dengjel, Jörn [Department of Dermatology, University Freiburg Medical Center and Center of Biological Systems Analysis, Habsburgerstr. 49, 79104 Freiburg (Germany); Walz, Gerd [Renal Division, Department of Medicine, University Freiburg Medical Center, Hugstetter Str. 55, 79106 Freiburg (Germany); Center for Biological Signaling Studies (BIOSS), Albertstr. 19, 79104 Freiburg (Germany); Yakulov, Toma A., E-mail: toma.antonov.yakulov@uniklinik-freiburg.de [Renal Division, Department of Medicine, University Freiburg Medical Center, Hugstetter Str. 55, 79106 Freiburg (Germany)

2015-08-28

Nephronophthisis (NPH) is an autosomal recessive cystic kidney disease, and a frequent cause of end-stage renal failure in children. To date, 17 NPH-associated gene products (NPHPs) have been identified. Most NPHPs participate in large multi-protein complexes that localize to the cilium and/or basal body; however, the precise composition of these complexes and their biological function remain largely unknown. We recently observed that the ankyrin repeat protein Anks3 interacts with the NPH family member Anks6. Both Anks3 and Anks6 form complexes with multiple other NPHPs, suggesting that both proteins function in similar or overlapping signaling pathways. Here, we show that Anks3, but not Anks6 interacted with the NIMA-related kinase Nek7, and was heavily modified in the presence of Nek7, resulting in an approximately 20 kD increase in molecular weight. Although mass spectrometry revealed increased serine and threonine phosphorylation of Anks3 primarily within the N-terminal ankyrin repeats also required for Nek7 interaction, the molecular weight increase occurred even in the presence of a kinase-dead Nek7 mutant, indicating that this modification was not caused by Nek7-dependent Anks3 phosphorylation. Furthermore, the Anks3 modification was specific for Nek7, and did not occur in the presence of Nek8. Importantly, Anks3 retained Nek7 in the cytoplasm, suggesting that, Nek7 triggers the modification of Anks3, which in turn prevents the nuclear localization of Nek7. - Highlights: • Anks3 interacted with Nek7 kinase, and was heavily modified in the presence of Nek7. • Anks3 N-terminal ankyrin repeats, but not SAM domain required for Nek7 interaction. • Nek7 increased Ser/Thr phosphorylation of Anks3 primarily within ankyrin domain. • Interaction with Anks3 led to cytoplasmic retention and nuclear exclusion of Nek7.

Transition cycle fuel management problems of NPP Krsko

International Nuclear Information System (INIS)

Petrovic, B.; Pevec, D.; Smuc, T.; Urli, N.

1989-01-01

Transition cycle fuel management problems are described and illustrated using results and experience attained during core reload design of NPP Krsko. Improved version of computer code package PSU-LEOPARD/Mcrac is successfully applied to NPP Krsko loading pattern design. (author)

NPP Krsko on-line low pressure containment tightness monitoring implementation

International Nuclear Information System (INIS)

Dudas, M.; Basic, I.

2004-01-01

Containment Integrated Leak Rate Test (CILRT) 1999 in NPP Krsko was completely performed following regulation of 10CFR50 Appendix J Option A and ANSI/ANS 56.8-1987 at a design pressure (3.15 kp/cm2). In 2001 NPP Krsko proposed to Slovenian Nuclear Safety Administration (SNSA) the Technical Specification (TS) and Updated Safety Analysis Report (USAR) changes that describe implementation of new test intervals for Type A, B and C tests according to 10CFR50, Appendix J, Option B. After the positive final independent review of proposed changes by Authorized Institution, NPP Krsko received the License Amendment requiring from NPP Krsko to define technical solution for surveillance of containment tightness between two 10-years CILRT. This paper intends to discuss proposed methods by NPP Krsko, test equipment, performed measurements in 2004, associated analyses and evaluation.(author)

NEK containment integrated leak rate test at full pressure

International Nuclear Information System (INIS)

Skaler, F.; Planinc, V.; Gregoric, D.; Cicvaric, D.

1999-01-01

NPP Krsko is a Pressure Water Reactor (PWR) Plant which has four barriers to prevent release of radioactive fission products. These four barriers are following: Fuel itself, Fuel Clad, Reactor Coolant System and Containment Building. Containment is the last barrier which can prevent release of fission product when other barriers have been already broken. To find out the real condition of containment vessel and to prove its ability of withstanding increased parameters during accident we have to perform Containment Integrated Leak Rate Test at least three times in every ten years of operation. CILRT 1999 in NPP Krsko was completely performed following regulation of 10CFR50 App. J Option A and ANSI/ANS 56.8-1987. The main goal of CILRT is to prove that the leakage of containment pathways and wall structures are within limits prescribed in Technical Specifications by pressurization of containment building above peak accident pressure Pa and measuring the mass changes of air using Ideal Gas Law.(author)

Evaluation of rod insertion issue for NPP Krsko

International Nuclear Information System (INIS)

Gunstek, A.; Kurincic, B.

1998-01-01

The last couple of years incident with control rods sticking in lower part of the fuel assemblies have been reported of several reactor operators and fuel vendors throughout of the world. Several activities were initiated immediately to determine the root cause of incomplete rod insertion. The purpose of this activities were to collect plants trip history data and testing results, review of available worldwide experience, review of plant operation and fuel management, detailed review of manufacturing and material property and to maintain detailed mechanical model. In this paper, we will present activities in Nuclear Power Plant Krsko which have been performed after NRC initiated the Root Cause Process (NRC Bulletin 96-01). NPP Krsko has not experienced rod insertion anomaly yet but anyway the additional tests were carried out. Rod drop time measurements that were performed normally at beginning of cycle at nominal temperature and pressure (HSB mode) have been extended also to end of cycle. Rod drop time, velocity of dropped rods and magnitudes of the initial recoil bounces vs. burnup were also analyzed. Also RCCA drag test with upper internals in place and drive shafts attached to RCCAs has been performed since then. At last two outages (1997 and 1998) drag test were carried out with digital scale meter to gather additional information. In addition to that, the reload core design has been performed with new constrains on rodded fuel assembly burnup as proposed by the industry.(author)

Long Term Management of Spent Fuel from NEK

International Nuclear Information System (INIS)

Kegel, L.; Zeleznik, N.; Lokner, V.

2012-01-01

In 2008 Slovenian national agency for radioactive waste management ARAO started together with Croatian sister organization APO elaboration of a new revision of Decommissioning, Radioactive waste and Spent fuel management program for NPP Krsko. In scope of this work also new studies for spent fuel storage and disposal were prepared in which technical solutions were analyzed and proposed for specific spent fuel (SF) from NPP Krsko. Time schedules for main activities of SF disposal development were elaborated for two alternative scenarios which correspond to normal NPP Krsko operation and 20 - year lifetime extension. All technical activities were financially assessed and costs estimates of SF storage and geological disposal development provided. The prepared studies were verified by international experts in order to confirm the correctness of technical inputs, proposed solutions, time schedules of activities and costs evaluations. The calculated nominal and discounted costs of spent fuel management served for the recalculation of annuities in the integral scenarios of interrelated activities on NPP Krsko decommissioning, LILW and SF management. Besides new first proposal of long-term management of spent fuel from NPP Krsko the joint work also opened additional questions. One of this is time schedule of proposed activities for long term SF management - what were the criteria used in the determination of actions and are they optimal for both countries. How the process of site selection for SF storage or disposal should be prepared having in mind that it will bring many questions in both countries? Is direct disposal of SF still the best solution in current development of nuclear prospects? The paper will present the current development and solutions for SF management from NPP Krsko and will try to answer questions which need to be solved and future development in the SF management.(author).

Tritium in organic matter around Krsko Nuclear Power Plant

International Nuclear Information System (INIS)

Kristof, Romana; Zorko, Benjamin; Kozar Logar, Jasmina; Kosenina, Suzana

2017-01-01

The aim of the research was to obtain first results of tritium in the organic matter of environmental samples in the vicinity of Krsko NPP. The emphasis was on the layout of suitable sampling network of crops and fruits in nearby agricultural area. Method for determination of tritium in organic matter in the form of Tissue Free Water Tritium (TFWT) and Organically Bound Tritium (OBT) has been implemented. Capabilities of the methods were tested on real environmental samples and its findings were compared to modeled activities of tritium from atmospheric releases and literature based results of TFWT and OBT. (author)

New version of NPP Krsko Decommissioning program and LILW and spent fuel management

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.; Jenko, T.; Lokner, V.; Levanat, I.; Rapic, A.

2004-01-01

According to the requirements of the bilateral agreement between Republic of Slovenia and Republic of Croatia on the legal and other obligations for Nuclear power plant (NPP) Krsko the Decommissioning program was prepared. The main purpose of the program was to estimate the overall expenses of the future decommissioning, radioactive waste and spent fuel management of the NPP Krsko in order to establish separate fund in Croatia and to correct the rate per kWh collected in the existing decommissioning fund in Slovenia. The program looked at all possible scenarios of dismantling, radioactive waste and spent fuel management and proposed the most plausible two scenarios which are technically possible and financially feasible. (author)

Risk assessment of the Krsko NPP normal operation on the public in the Zagreb area

International Nuclear Information System (INIS)

Skanata, D.; Pevec, D.

1994-01-01

In the paper, a very short review of the ICRP recommendations related to effective dose limitation for the workers as well as for the public, is given. Particular attention is paid to the risk coefficients values. In the short manner, description of the applied methodology and achieved result related to the risk assessment of the Krsko NPP normal operation on the public in the Zagreb Area, are given too. The mentioned assessment was performed as an activity within the Case Study Zagreb Project developed under the Inter-Agency Programme on the Assessment and Management of Health and Environmental Risks from Energy and Other Complex Industrial Systems (UNEP, WHO, IAEA and UNIDO). Making comparison between assessment risk of the Krsko NPP normal operation and risks to which inhabitants of the City of Zagreb are normally exposed, it is concluded that living in the vicinity of such nuclear power plant as it is Krsko NPP (PWR, 664 MWe), is not so risky as risky are some everyday activities

Use of MAAP code for identification of key plant vulnerabilities for the beyond design accidents and their mitigation at NPP Krsko

International Nuclear Information System (INIS)

Krajnc, B.

1995-01-01

NPP Krsko performed according to GL 88-20, Supplement 1-4 and RUJV requirement the Individual Plant Examination analyses. For the required deterministic analyses the MAAP 3.0B code was used. It was proven that such severe accident analysis can be used for evaluation of the overall level of safety improvement that can be gained with the different modifications and alternate design. In this paper one such important outcomes from these analyses will be presented. (author)

Environmental Qualification Program for NPP Krsko

International Nuclear Information System (INIS)

Cerjak, J.; Klenovsek, P.; Pavsek, J.; Spalj, S.; Colovic, G.

1998-01-01

The functionality the equipment important to safety is deteriorated during its service due to ageing and harsh environment conditions. Since the environment is a potential for common cause failures, the purpose of Environmental Qualification (EQ) is to demonstrate the capability of safety-related equipment to perform its safety function in aged conditions and under extreme conditions after design bases event (DBE). EQ is one of the steps in licensing process according to US regulatory documents and standards (10CFR50.49, RG 1.89, NUREG-0588, IEEE-323). This paper presents the efforts in establishing the EQ program in the Krsko nuclear power plant. (author)

NPP Krsko Containment Response Following Main Steam Line Break

International Nuclear Information System (INIS)

Spalj, S.; Grgic, D.; Cavlina, N.

2000-01-01

This paper presents the calculation of thermohydraulic environmental parameters (pressure and temperature) inside containment of Krsko NPP after postulated Main Steam Line Break (MSLB) accident. This analysis was done as a part of the ambient parameters specification in the frame of the NPP Krsko Equipment Qualification (EQ) project. The RELAP5/mod2 computer code was used for the determination of MSLB mass and energy release and computer code GOTHIC was used to calculate pressure and temperature profiles inside NPP Krsko containment. The analysis was performed for spectrum of break sizes to account for possible steam superheating during accidents with smaller break sizes. (author)

ATWS thermal-hydraulic analysis for Krsko Full Scope Simulator validation

International Nuclear Information System (INIS)

Parzer, I.; Kljenak, I.

2005-01-01

The purpose of this analysis was to simulate Anticipated Transient without Scram transient for Krsko NPP. The results of these calculations were used for annual ANSI/ANS validation of reactor coolant system thermal-hydraulic response predicted by Krsko Full Scope Simulator. For the thermal-hydraulic analyses the RELAP5/MOD3.3 code and the input model for NPP Krsko, delivered by NPP Krsko, was used. In the presented paper the most severe ATWS scenario has been analyzed, starting with the loss of Main Feedwater at both steam generators. Thus, gradual loss of secondary heat sink occurred. On top of that, control rods were not supposed to scram, leaving the chain reaction to be controlled only by inherent physical properties of the fuel and moderator and eventual actions of the BOP system. The primary system response has been studied assuming AMSAC availability. (author)

Containment Leakage Rate Testing Program in NPP Krsko

International Nuclear Information System (INIS)

Dudas, M.; Heruc, Z.

2002-01-01

NPP Krsko adopted new regulations for testing of the reactor building containment as stipulated by 10CFR50 (Code of Federal Regulation) Appendix J, Option B instead of the previous requirement 10CFR50 Appendix J now renamed to 10CFR50 Appendix J, Option A. In the USA a thorough analyses of nuclear power plants reactor building containment testing was conducted. As part of these analyses the test results obtained from testing of various reactor-building containments in the last ten years were reviewed. It was concluded that it would be meaningful to, based on test results historical data, reconsider possibility of redefining testing intervals. The official proposal of such approach was reviewed and approved by the NRC and published in September of 1995 in the FR Vol.60 No.186. Based on directions from 10CFR50 Appendix J, Option B, the new criteria for definition of test intervals were created. Criteria were based upon past performance during testing (Performance-based Requirements) and safety impact. At NPP Krsko, the analyses of the Reactor Building Containment. Integrity Test results was performed . This included test results of the Containment Integrated Leak Rate Testing (CILRT or Type A tests), Containment Isolation Valves Local Leak Rater Tests (Type C tests) and Mechanical and Electrical Penetrations Local Leak Rate tests (Type B tests). In accordance with instructions from NEI 94-01 and based on analyses of test results, NPP Krsko created Containment Leakage Rate Testing Program with the purpose to establish the performance-based definition of test intervals, inspection scope, trending and reporting. Equally, the program gives instructions how to evaluate test results and how to deal with the containment penetration or isolation valve repair contingency. All changes caused with transition from Option A to Option B are marginal to public safety. (author)

NPP Krsko small break LOCA analysis

International Nuclear Information System (INIS)

Mavko, B.; Petelin, S.; Peterlin, G.

1987-01-01

Parametric analysis of small break loss of coolant accident for the Krsko NPP was calculated by using RELAP5/MOD1 computer code. The model that was used in our calculations has been improved over several years and was previously tested in simulation (s) of start-up tests and known NPP Krsko transients. In our calculations we modelled automatic actions initiated by control, safety and protection systems. We also modelled the required operator actions as specified in emergency operating instructions. In small-break LOCA calculations, we varied break sizes in the cold leg. The influence of steam generator tube plugging on small break LOCA accidents was also analysed. (author)

Expression of Nek1 during kidney development and cyst formation in multiple nephron segments in the Nek1-deficient kat2J mouse model of polycystic kidney disease.

Science.gov (United States)

Chen, Yumay; Chiang, Huai-Chin; Litchfield, Patricia; Pena, Michelle; Juang, Charity; Riley, Daniel J

2014-07-17

Neks, mammalian orthologs of the fungal protein kinase never-in-mitosis A, have been implicated in the pathogenesis of polycystic kidney disease. Among them, Nek1 is the primary protein inactivated in kat2J mouse models of PKD. We report the expression pattern of Nek1 and characterize the renal cysts that develop in kat2J mice. Nek1 is detectable in all murine tissues but its expression in wild type and kat2J heterozygous kidneys decrease as the kidneys mature, especially in tubular epithelial cells. In the embryonic kidney, Nek1 expression is most prominent in cells that will become podocytes and proximal tubules. Kidney development in kat2J homozygous mice is aberrant early, before the appearance of gross cysts: developing cortical zones are thin, populated by immature glomeruli, and characterized by excessive apoptosis of several cell types. Cysts in kat2J homozygous mice form postnatally in Bowman's space as well as different tubular subtypes. Late in life, kat2J heterozygous mice form renal cysts and the cells lining these cysts lack staining for Nek1. The primary cilia of cells lining cysts in kat2J homozygous mice are morphologically diverse: in some cells they are unusually long and in others there are multiple cilia of varying lengths. Our studies indicate that Nek1 deficiency leads to disordered kidney maturation, and cysts throughout the nephron.

ATWS analyses for Krsko Full Scope Simulator verification

Energy Technology Data Exchange (ETDEWEB)

Cerne, G; Tiselj, I; Parzer, I [Reactor Engineering Div., Inst. Jozef Stefan, Ljubljana (Slovenia)

2000-07-01

The purpose of this analysis was to simulate Anticipated Transient without Scram transient for Krsko NPP. The results of these calculations were used for verification of reactor coolant system thermal-hydraulic response predicted by Krsko Full Scope Simulator. For the thermal-hydraulic analyses the RELAP5/MOD2 code and the input card deck for NPP Krsko was used. The analyses for ATWS were performed to assess the influence and benefit of ATWS Mitigation System Actuation Circuitry (AMSAC). In the presented paper the most severe ATWS scenarios have been analyzed, starting with the loss of Main Feedwater at both steam generators. Thus, gradual loss of secondary heat sink occurred. On top of that, control rods were not supposed to scram, leaving the chain reaction to be controlled only by inherent physical properties of the fuel and moderator and eventual actions of the BOP system. The primary system response has been studied regarding the AMSAC availability. (author)

Nek1 silencing slows down DNA repair and blocks DNA damage-induced cell cycle arrest.

Science.gov (United States)

Pelegrini, Alessandra Luíza; Moura, Dinara Jaqueline; Brenner, Bethânia Luise; Ledur, Pitia Flores; Maques, Gabriela Porto; Henriques, João Antônio Pegas; Saffi, Jenifer; Lenz, Guido

2010-09-01

Never in mitosis A (NIMA)-related kinases (Nek) are evolutionarily conserved proteins structurally related to the Aspergillus nidulans mitotic regulator NIMA. Nek1 is one of the 11 isoforms of the Neks identified in mammals. Different lines of evidence suggest the participation of Nek1 in response to DNA damage, which is also supported by the interaction of this kinase with proteins involved in DNA repair pathways and cell cycle regulation. In this report, we show that cells with Nek1 knockdown (KD) through stable RNA interference present a delay in DNA repair when treated with methyl-methanesulfonate (MMS), hydrogen peroxide (H(2)O(2)) and cisplatin (CPT). In particular, interstrand cross links induced by CPT take much longer to be resolved in Nek1 KD cells when compared to wild-type (WT) cells. In KD cells, phosphorylation of Chk1 in response to CPT was strongly reduced. While WT cells accumulate in G(2)/M after DNA damage with MMS and H(2)O(2), Nek1 KD cells do not arrest, suggesting that G(2)/M arrest induced by the DNA damage requires Nek1. Surprisingly, CPT-treated Nek1 KD cells arrest with a 4N DNA content similar to WT cells. This deregulation in cell cycle control in Nek1 KD cells leads to an increased sensitivity to genotoxic agents when compared to WT cells. These results suggest that Nek1 is involved in the beginning of the cellular response to genotoxic stress and plays an important role in preventing cell death induced by DNA damage.

Disposal of spent nuclear fuel from NPP Krsko

International Nuclear Information System (INIS)

Mele, I.

2004-01-01

In order to get a clear view of the future liabilities of Slovenia and Croatia regarding the long term management of radioactive waste and spent nuclear fuel produced by the NPP Krsko, an estimation of disposal cost for low and intermediate level waste (LILW) as well as for spent nuclear fuel is needed. This cost estimation represents the basis for defining the target value for the financial resources to be accrued by the two national decommissioning and waste disposal funds, as determined in the agreement between Slovenia and Croatia on the ownership and exploitation of the NPP Krsko from March 2003, and for specifying their financial strategies. The one and only record of the NPP Krsko spent fuel disposal costs was made in the NPP Krsko Decommissioning Plan from 1996 [1]. As a result of incomplete input data, the above SF disposal cost estimate does not incorporate all cost elements. A new cost estimation was required in the process of preparation of the Joint Decommissioning and Waste Management Programme according to the provisions of the above mentioned agreement between Slovenia and Croatia. The basic presumptions and reference scenario for the disposal of spent nuclear fuel on which the cost estimation is based, as well as the applied methodology and results of cost estimation, are presented in this paper. Alternatives to the reference scenario and open questions which need to be resolved before the relevant final decision is taken, are also briefly discussed. (author)

Annual and seasonal variations In the gamma activities in Sava river sediments upstream and downstream of NPP Krsko

International Nuclear Information System (INIS)

Stipe, Lulic

2006-01-01

Results of the five years monitoring of artificial and natural occurring radionuclides in the Sava river sediments are presented. Measurements were conducted as a part of the regular Krsko Nuclear Power Plant radioactivity control and the independent supervisions of the input of radionuclides into larger environment (immission). In order to estimate seasonal variations samples were taken from seven locations (one upstream and five downstream of the Krsko NPP) during four sampling period (seasonal) in each year. Selected radionuclides in the sediment fraction less than 0.5 mm were determined with gamma spectrometer equipped with BE3830 model High Purity Ge detector with 30% relative efficiency. (authors)

Annual and seasonal variations In the gamma activities in Sava river sediments upstream and downstream of NPP Krsko

Energy Technology Data Exchange (ETDEWEB)

Stipe, Lulic [Rudjer Boskovic Institute, Lab. for radioecology, Zagreb (Croatia)

2006-07-01

Results of the five years monitoring of artificial and natural occurring radionuclides in the Sava river sediments are presented. Measurements were conducted as a part of the regular Krsko Nuclear Power Plant radioactivity control and the independent supervisions of the input of radionuclides into larger environment (immission). In order to estimate seasonal variations samples were taken from seven locations (one upstream and five downstream of the Krsko NPP) during four sampling period (seasonal) in each year. Selected radionuclides in the sediment fractiess than 0.5 mm were determined with gamma spectrometer equipped with BE3830 model High Purity Ge detector with 30% relative efficiency. (authors)

Re-racking the spent fuel pit in nuclear power plant Krsko

International Nuclear Information System (INIS)

Volaric, B.; Krajnc, B.

2003-01-01

Krsko NPP was designed to temporary store a limited number of spent fuel assemblies (SFA). They were planned to be either removed for reprocessing or permanently stored. By the design the plant would run out of capacity for temporary storing of SFAs in 2003. This means that the plant could not operate further without additional changes since valid regulations require the Spent Fuel Pit (SFP) free storage capacity for the whole emergency core unloading (ECU). The purpose of the SFP Reracking Project is to assure a safe storage of all SFAs in the existing SFP during the plant lifetime. Design solutions and related analysis did not only consider the quantity of spent fuel for the plant lifetime, i.e. up to the year 2023, but also a possibility of the SFP extension for eventually extended plant lifetime of 20 years. According to the project, racks were designed to provide up to 1694 cells for storage of FAs in Phase I which is sufficient for normal NPP operation up to its lifetime, i.e. the year 2023. The extension of temporary storage capacity of SFAs in the SFP was made by a combination of existing and new high-density racks. Three modules from the existing 12 were eliminated. Thus leaving 621 cells. There are nine new racks added with up to 1073 supercompacted cells installed in the empty part of the pool. The spacing between new cells is smaller than the one between existing cells because of special plates, made of borated stainless steel. The design of the racks fulfils all the applicable requirements to ensure sub-criticality of all stored SFAs, enriched up to 5 % U 235 with peak pellet burnup above 40 GWD/MTU. Besides static and dynamic seismic loading of both, the racks and the fuel handling building, sufficient cooling of FAs is provided as well as accident conditions precluded. Greater cooling capacity is achieved by installing the third heat exchanger, connected in parallel to existing two exchangers. The design and manufacturing of the new heat exchanger

SNSA surveillance over the ageing effects and ability for long term operation at Krsko NPP

International Nuclear Information System (INIS)

Savli, S.; Ferjancic, M.; Pavlin, D.; Lovincic, D.

2007-01-01

The paper presents the Slovenian Nuclear Safety Administration (SNSA) tools used for verification the adequacy of management of ageing effects and assuring suitability for long term operation at the Krsko NPP. In addition to tools commonly used as PSR (Periodic Safety Review), assessment of plant modifications, regular inspections, the SNSA applies some special methods like monitoring the condition of important plant structures, systems and components (SSC) through special designed software, review and assessment of important plant programmes and its own set of performance indicators

Analysis of the network protection devices action connected with the Krsko NPP operation safety

International Nuclear Information System (INIS)

Omahen, P.; Struc, S.

1995-01-01

The example of failure that took place in Zagreb on 30 March, 1995, has been investigated in order to obtain appropriate answers to the unexpected electric power system (ESP) response and consecutive outage of the Krsko nuclear power plant (NPP). The analysis has been made of particular operating and stability conditions, related to the functioning of distance relays line protection. Using a consequent simulation model of the EPS (European interconnection) under specified fault condition, the research of EPS operation (relays action) and stability has been done. The appropriate simulation results have been compared to the available measured data which had been collected by the SOREL on-line data acquisition system. In the end, a practise proposal for measures to be taken with the target of achieving the foreseen and expected operation of the EPS equipment that effects operation of the Krsko NPP is given. (author)

Relationship towards Engineering, Quality Assurance and 10CFR50.59 in the Design Change Process at the Krsko NPP

International Nuclear Information System (INIS)

Basic, I.; Krajnc, B.

1998-01-01

The paper discusses the relationship between the Krsko NPP design change engineering practice, quality assurance and the USA Nuclear Regulatory Commission 10 Code Federal Rule 50.59 (10CFR50.59). Together these controls ensure that plant design bases are maintained and yield a safe design. The 10CFR50.59 has been applied in Krsko NPP plant specific procedure entitled ESP-2.303 ''Authorization of Changes, Tests and Experiments'' (Safety Evaluation Screening) since 1994. All proposed changes requiring Safety Evaluations are being submitted to the SNSA (Slovenian Nuclear Safety Administration). If the proposed change is constituting an ''Unreviewed Safety Question'' the formal licensing procedure shall be completed before design change can be implemented otherwise the proposed design change is rejected. The procedure(ESP-2.303) provides the methodology to be followed in determining if a proposed activity involves an unreviewed safety question. An ''Unreviewed Safety Question'' is essentially the same as defined in 10CFR50.59(a)(2): ''A proposed change, test or experiment shall be deemed to involve an unreviewed safety question (1) if the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the (updated) safety analysis report may be increased; or (2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the (updated) safety analysis report may be created; or (3) if the margin of safety as defined in the basis for any technical specification is reduced.'' This paper discusses the Following Krsko NPP Safety Evaluation aspects: 1. Defense in Depth Design Philosophy 2. Methodology 3. Definitions and Applicability of Terms 4. Evaluation Process Guidance and Documentation Process 5. Krsko NPP Lessons Learned. (author)

NEK11: linking CHK1 and CDC25A in DNA damage checkpoint signaling

DEFF Research Database (Denmark)

Sørensen, Claus Storgaard; Melixetian, Marina; Klein, Ditte Kjaersgaard

2010-01-01

The DNA damage induced G(2)/M checkpoint is an important guardian of the genome that prevents cell division when DNA lesions are present. The checkpoint prevents cells from entering mitosis by degrading CDC25A, a key CDK activator. CDC25A proteolysis is controlled by direct phosphorylation events...... is required for beta-TrCP mediated CDC25A polyubiquitylation and degradation. The activity of NEK11 is in turn controlled by CHK1 that activates NEK11 via phosphorylation on serine 273. Since inhibition of NEK11 activity forces checkpoint-arrested cells into mitosis and cell death, NEK11 is, like CHK1...

External Reactor Vessel Cooling Evaluation for Severe Accident Mitigation in NPP Krsko

International Nuclear Information System (INIS)

Mihalina, M.; Spalj, S.; Glaser, B.

2016-01-01

The In-Vessel corium Retention (IVR) through the External Reactor Vessel Cooling (ERVC) is mean for maintaining the reactor vessel integrity during a severe accident, by cooling and retaining the molten material inside the reactor vessel. By doing this, significant portion of severe accident negative phenomena connected with reactor vessel failure could be avoided. In this paper, analysis of NPP Krsko applicability for IVR strategy was performed. It includes overview of performed plant related analysis with emphasis on wet cavity modification, plant's site specific walk downs, new applicable probabilistic and deterministic analysis, evaluation of new possibilities for ERVC strategy implementation regarding plant's post-Fukushima improvements and adequacy with plant's procedures for severe accident mitigation. Conclusion is that NPP Krsko could perform in-vessel core retention by applying external reactor vessel cooling strategy with reasonable confidence in success. Per probabilistic and deterministic analysis, time window for successful ERVC strategy performance for most dominating plant damage state scenarios is 2.5 hours, when onset of core damage is observed. This action should be performed early after transition to Severe Accident Management Guidance's (SAMG). For loss of all AC power scenario, containment flooding could be initiated before onset of core damage within related emergency procedure. To perform external reactor vessel cooling, reactor water storage tank gravity drain with addition of alternate water is needed to be injected into the containment. ERVC strategy will positively interfere with other severe accident strategies. There are no negative effects due to ERVC performance. New flooding level will not threaten equipment and instrumentation needed for long term SAMGs performance and eventually diluted containment sump borated water inventory will not cause return to criticality during eventual recirculation phase due to the

Presentation of common cause failures in fault tree structure of Krsko PSA : an historical overview

International Nuclear Information System (INIS)

Vrbanic, I.; Kosutic, I.; Vukovic, I.; Simic, Z.

2003-01-01

Failure of multiple components due to a common cause represents one of the most important issues in evaluation of system reliability or unavailability. The frequency of such events has relatively low expectancy, when compared to random failures, which affect individual components. However, in many cases the consequence is a direct loss of safety system or mitigative safety function. For this reason, the modeling of a common cause failure (CCF) and its presentation in fault tree structure is of the uttermost importance in probabilistic safety analyses (PSA). During the past decade, PSA model of Krsko NPP has undergone many small changes and a couple of major ones in fulfilling its basic purpose, which was serving as a tool for providing an appropriate information on the risk associated with actual plant design and operation. All changes to Krsko PSA model were undertaken in order to make it a better tool and / or to make it represent the plant in more accurate manner. The paper provides an overview of changes in CCF modeling in the fault tree structure from the initial PSA model development till present. (author)

Strengthening ALARA approach in work management at Krsko NPP

International Nuclear Information System (INIS)

Breznik, B.; Kovac, Z.; Sirola, P.

1999-01-01

As Low As Reasonably Achievable (ALARA) occupational exposures at nuclear power plants should be included in work management as a concept. There are world-wide trends required by the utilities for improved design, operation and maintenance. Within the period of seventeen years of plant operation maintaining low radiation exposures requires additional efforts. The benefit of this effort should be reducing risks to nuclear workers, better work planning and performance. The Krsko Plant ALARA organisations has been revised recently and built on different levels of the hierarchy. The goal is to promote good industry practice and the management of work on primary systems. The established ALARA programme describes the objectives and defines the procedures and tools for its implementation. Brief presentation of the programme as well as organisational responsibilities of dedicated ALARA committee and working groups is the scope of this paper. The management tools and ALARA indicators are discussed to implement the programme and to evaluate the results.(author)

Determination of the NPP Krsko reactor core safety limits using the COBRA-III-C code

International Nuclear Information System (INIS)

Lajtman, S.; Feretic, D.; Debrecin, N.

1989-01-01

This paper presents the NPP Krsko reactor core safety limits determined by the COBRA-III-C code, along with the methodology used. The reactor core safety limits determination is a part of reactor protection limits procedure. The results obtained were compared to safety limits presented in NPP Krsko FSAR. The COBRA-III-C NPP Krsko design core steady state thermal hydraulics calculation, used as the basis for the safety limits calculation, is presented as well. (author)

Radioactivity monitoring programme of Krsko nuclear power plant

International Nuclear Information System (INIS)

Miklavzic, U.; Martincic, R.; Kanduc, M.; Lulic, S.; Kovac, J.; Breznik, B.

1996-01-01

As a successor to the preoperational surveillance programme, the regular offsite radioactivity monitoring programme (RMP) of the Krsko Nuclear Power Plant (NPP) was implemented in 1982, when the power plant formally commenced operating. Observations collected during the first years of its operation were later also the basis for setting up the official 'Regulatory guide on monitoring of nuclear installations', issued not earlier than in 1986. The basic criterion which governed the selection of measuring methods, sampling techniques and locations, was the extent to which the data obtained could serve for the realistic assessment of the committed dose to a member of the population, and later on to members of a representative (critical) group. To be able to differentiate the radioactivity released through the liquid and gaseous effluents of the NPP from other radiation sources (natural radioactivity, global contamination), and especially because of the varying radiotoxicity of different radionuclides, in principle monitoring in the environment, as at the source, had to provide activity data for each individual radionuclide appearing in the effluents. Therefore, as early as 1982 the programme attributed the main weight to high resolution gamma spectrometry, combined with specific radiochemical analytical methods (e.g. 90 Sr/ 89 Sr, 3 H, 14 C, alpha spectrometry of Pu isotopes) which together made feasible determination of individual specific activities of the most significant man-made and natural radionuclides. By weighting the specific activities of the radionuclides identified and measured in the media surveyed by dose factors for intake, the quantity 'B' - the so-called 'radiological burden', was calculated and introduced in the yearly-summary tables. Expressed in relative units, from which the committed dose could be readily calculated, the burden B very lucidly disclosed the relative importance of different artificial pollutants and natural radioactivity present in

Nek2A destruction marks APC/C activation at the prophase-to-prometaphase transition by spindle-checkpoint-restricted Cdc20.

Science.gov (United States)

Boekhout, Michiel; Wolthuis, Rob

2015-04-15

Nek2 isoform A (Nek2A) is a presumed substrate of the anaphase-promoting complex/cyclosome containing Cdc20 (APC/C(Cdc20)). Nek2A, like cyclin A, is degraded in mitosis while the spindle checkpoint is active. Cyclin A prevents spindle checkpoint proteins from binding to Cdc20 and is recruited to the APC/C in prometaphase. We found that Nek2A and cyclin A avoid being stabilized by the spindle checkpoint in different ways. First, enhancing mitotic checkpoint complex (MCC) formation by nocodazole treatment inhibited the degradation of geminin and cyclin A, whereas Nek2A disappeared at a normal rate. Second, depleting Cdc20 effectively stabilized cyclin A but not Nek2A. Nevertheless, Nek2A destruction crucially depended on Cdc20 binding to the APC/C. Third, in contrast to cyclin A, Nek2A was recruited to the APC/C before the start of mitosis. Interestingly, the spindle checkpoint very effectively stabilized an APC/C-binding mutant of Nek2A, which required the Nek2A KEN box. Apparently, in cells, the spindle checkpoint primarily prevents Cdc20 from binding destruction motifs. Nek2A disappearance marks the prophase-to-prometaphase transition, when Cdc20, regardless of the spindle checkpoint, activates the APC/C. However, Mad2 depletion accelerated Nek2A destruction, showing that spindle checkpoint release further increases APC/C(Cdc20) catalytic activity. © 2015. Published by The Company of Biologists Ltd.

Implementation of procedures to NPP Krsko INTRANEK

International Nuclear Information System (INIS)

Gradisar, D.; Krajnc, M.; Kocnar, R.; Spiler, J.

1999-01-01

Part of NEK documentation has already been presented on NEK Intranet such as USAR, Technical Specifications, QA Plan as well as some frequently used series of drawings. At the time being the process of presentation of all procedures (thereinafter INTRANEK procedures) is in progress. The purpose of this project is the presentation of 1600 procedures with average size of 30 pages what is more than 48000 pages altogether. ADOBE PDF (Portable Document Format) has been chosen as the most suitable format for the presentation of procedures on INTRANEK. PDF format meets the following criteria: the outlook of a document page is always the same as an original one and cannot be changed without control. In addition to this, full text search is available as well as easy jump from procedure to procedure. Some changes of working process on internal procedures have to be made before the project start, which determine the responsibility of individual users in the process. The work flow, which enables easy daily maintenance, has been prepared, the rules of both procedure numbering as well as folder contents/name have been set and the server selected. The project was managed and implemented with the extensive use of compute-aided management, document distribution and control, databases, electronics mail and Intranet tools. The results of practical implementation of NEK procedures and our experience with INTRANEK are presented in this paper.(author)

LWRA analysis of inadvertent closing of the main steam isolation valve in NPP Krsko

International Nuclear Information System (INIS)

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

1996-01-01

The paper describes the use of system code RELAP5/mod2 and analyzer code LWRA in analysis of inadvertent closing of the main steam isolation valve that happened in NPP Krsko on September, 25 1995. Three cases were calculated in order to address different aspects of the modelled transient. This preliminary calculation showed that, even though the real plant behaviour was not completely reproduced, such kind of analysis can help to better understand plant behaviour and to identify important phenomena in the plant during transient. The results calculated by RELAP5 and LWRA were similar and both codes indicated lack of better understanding of the plant systems status. The LWRA was more than 5 times faster than real time. (author)

Some aspects of programmable digital systems usage in nuclear power plants

International Nuclear Information System (INIS)

Mandic, D.; Smolej, M.; Sucic, B.

2004-01-01

During the operation of the NPP Krsko - NEK and other nuclear power plants, it has been recognized that certain issues related to the usage of digital equipment and associated software in NPP technological process protection, control and monitoring, are usually not adequately addressed in the existing programs and procedures. Moreover, often the problems related to the programmable digital systems usage are not understood correctly, which means that they can not be treated properly. Owing to the specifics of the programmable digital systems usage they have to be treated in a different way than other plant equipment and related documentation. The term as well as the process of Process Computers Configuration Control was introduced to control, among other issues, three 10CFR50 Appendix B quality requirements related to the Process Computers application in NPP: Design Control, Document Control, Identification and Control of Materials, Parts and Components. Based on the experience from NEK and published experience from other NPP and other organizations, this paper sheds light on specifics of the programmable digital systems usage in nuclear power plants. The wording Programmable Digital Systems was used rather than Process Computers, to emphasize wide area of applicability of this term: from simple digital components with burned-in programs to the PLC (Programmable Logic Controllers) and large process computer systems. In order to satisfy requirements of the Process Computer Configuration Control, specific characteristics and specific problems related to the usage of programmable digital systems require specific treatment of these issues. This paper describes those specific characteristics and traditional misunderstandings, false beliefs, false expectations and common errors that are most frequently committed in the life cycle of the programmable digital systems, as well as consequences and problems that could develop. The paper also refers to the regulations, industry

New iteration of decommissioning program for NPP Krsko

International Nuclear Information System (INIS)

Lokner, V.; Levanat, I.; Rapic, A.; Zeleznik, N.; Mele, I.; Jenko, T.

2004-01-01

As required by the paragraph 10 of the Agreement between the governments of Slovenia and Croatia on status and other legal issues related to investment, exploitation, and decommissioning of Nuclear power plant Krsko, Decommissioning program for Krsko NPP including LILW and spent fuel management was drafted. The Intergovernmental body required that the Program should be extensive revision of existing program as one of several iterations to be prepared before the final version. The purpose of the Program is to estimate the expenses of the future decommissioning, radioactive waste and spent fuel management for Krsko NPP. Costing estimation would be the basis for establishment of a special fund in Croatia and for adjustment of the annual rates for the existing decommissioning fund in Slovenia. The Program development was entrusted to specialized organizations both in Croatia and Slovenia, which formed the Project team as the operative body. Consulting firms from Croatia and Slovenia were involved as well as experts from the International Atomic Energy Agency (through short visits to Zagreb and Ljubljana) for specialized fields (e.g. economic aspects of decommissioning, pre-feasibility study for spent fuel repository in crystalline rock, etc.). The analysis was performed in several steps. The first step was to develop rational and feasible integral scenarios (strategies) of decommissioning and LILW and spent fuel management on the basis of detailed technical analysis and within defined boundary conditions. Based on technological data, every scenario was attributed with time distribution of expenses for all main activities. In the second step, financial analysis of the scenarios was undertaken aiming at estimation of total discounted expense and the related annuity (19 installments to the single fund, empty in 2003) for each of the scenarios. The third step involves additional analysis of the chosen scenarios aiming at their (technical or financial) improvements even at

Conversion of NEK standard technical specifications into improved technical specifications

International Nuclear Information System (INIS)

Glaser, B.

2003-01-01

Neck is currently using a standard format of operation's Technical Specifications - STS (based on NUREG-0452), which are planned to be converted into Improved Technical Specifications - ITS (based on NUREG-1431). To facilitate the development of individual ITS, each reactor vendor owners group (OG) and the NRC staff developed improved standard TS (ISTS). For Westinghouse plants, the ISTS are published as NUREG-1431, and this document is going to be the basis for the new NEK ITS. It has been recognized that nuclear safety in all plants would benefit from improvement and standardization of ITS, so this was also addressed and recognized by the NRC. There are several plants around Europe and US, which have replaced the format into ITS which brings a lot of improvements and practical value in operations. The main objective of conversion is to completely rewrite, reformat, and streamline the existing STS. Emphasis is placed on human factors principles to improve clarity and understanding. The Bases section will be significantly expanded to clarify and better explain the purpose and foundation of each specification. There might be some proposed changes to the existing STS that deviated from the ITS in NUREG-1431 and constitute a relaxation of the existing STS. Each of these additional proposed changes will be described and evaluated in amendment application and justified on a case-by-case basis. Since the NEK is going to operate for more than 20 year without considering life extension, such conversion will be beneficial for operation personnel as well as regulation, surveillance and focus on operation's safety. At the present, only preliminary plan of STS conversion exists, showing the time frame of approximately 2 years of conversion process and numerous tasks that need to be performed. The plan is to begin with process in year 2004 and finish project in 2006, which means use of new ITS in main control room in year 2007. Beside the main process of conversion, there are

ORIGEN2.1 Cycle Specific Calculation of Krsko Nuclear Power Plant Decay Heat and Core Inventory

International Nuclear Information System (INIS)

Vukovic, J.; Grgic, D.; Konjarek, D.

2010-01-01

This paper presents ORIGEN2.1 computer code calculation of Krsko Nuclear Power Plant core for Cycle 24. The isotopic inventory, core activity and decay heat are calculated in one run for the entire core using explicit depletion and decay of each fuel assembly. Separate pre-ori application which was developed is utilized to prepare corresponding ORIGEN2.1 inputs. This application uses information on core loading pattern to determine fuel assembly specific depletion history using 3D burnup which is obtained from related PARCS computer code calculation. That way both detailed single assembly calculations as well as whole core inventory calculations are possible. Because of the immense output of the ORIGEN2.1, another application called post-ori is used to retrieve and plot any calculated property on the basis of nuclide, element, summary isotope or group of elements for activation products, actinides and fission products segments. As one additional possibility, with the post-ori application it is able to calculate radiotoxicity from calculated ORIGEN2.1 inventory. The results which are obtained using the calculation model of ORIGEN2.1 computer code are successfully compared against corresponding ORIGEN-S computer code results.(author).

Radioactive control of Krsko Nuclear Power Plant in the year 1995

International Nuclear Information System (INIS)

Lulic, S.; Miklavzic, U.; Franic, Z.; Kanduc, M.

1996-01-01

Regular Krsko Nuclear Power Plant (NPPK) radioactivity control comprises the supervisions of the inventory of liquid and gaseous emissions at the source, and the independent supervisions of the input of radionuclides into larger environment. The controlled environment area consist primarily of a 12 kilometers large circle around the object, where the largest values of immission could be expected, and where possible changes in the Sava river and the underground waters could first be noticed. The circle has been enlarged upon the territory of the Republic of Croatia (RC) from Jesenice on Dolenjsko until Podsused (30 km of air-line distance). As reference points relevant for the readiness in the case of accident, especially for detection of iodine and aerosol air transport, the program comprises also measuring points in the RC at larger distances (from 14 to 27 km) in the direction of Zagreb its larger western surroundings (passive Thermoluminescent (TL) dosimeters in each 42 km long). Continuous of control of emission is performed by the radiological service of (KNPP) by routine procedures, supplemented by adequate measurements from other authorized institutions. Summarized results of radioactive measurements for man-made and natural radionuclides are presented for different transfer media and exposure pathways in the form of assessed effective doses. Conservatively estimated dose burdens received by a member of the reference (critical) population group as the result of NPP emissions amount to a value of the committed effective dose equivalent smaller than 20 μSv/year. This value represents less than 1% of the annual dose received on average from natural and artificial sources by a member of the general public in the normal environment. The yearly doses from natural radioactivity, global contamination , non-nuclear industries and hospitals are also estimated from the measured data in some media. (author)

The profile of quantitative risk indicators in Krsko NPP

International Nuclear Information System (INIS)

Vrbanic, I.; Basic, I.; Bilic-Zabric, T.; Spiler, J.

2004-01-01

During the past decade strong initiative was observed which was aimed at incorporating information on risk into various aspects of operation of nuclear power plants. The initiative was observable in activities carried out by regulators as well as utilities and industry. It resulted in establishing the process, or procedure, which is often referred to as integrated decision making or risk informed decision making. In this process, engineering analyses and evaluations that are usually termed traditional and that rely on considerations of safety margins and defense in depth are supplemented by quantitative indicators of risk. Throughout the process, the plant risk was most commonly expressed in terms of likelihood of events involving damage to the reactor core and events with radiological releases to the environment. These became two commonly used quantitative indicators or metrics of plant risk (or, reciprocally, plant safety). They were evaluated for their magnitude (e.g. the expected number of events per specified time interval), as well as their profile (e.g. the types of contributing events). The information for quantitative risk indicators (to be used in risk informing process) is obtained from plant's probabilistic safety analyses or analyses of hazards. It is dependable on issues such as availability of input data or quality of model or analysis. Nuclear power plant Krsko has recently performed Periodic Safety Review, which was a good opportunity to evaluate and integrate the plant specific information on quantitative plant risk indicators and their profile. The paper discusses some aspects of quantitative plant risk profile and its perception.(author)

Tritium liquid effluents from the Krsko NPP

International Nuclear Information System (INIS)

Savli, S.; Krizman, M.; Nemec, T.; Cindro, M.; Stritar, A.; Vokal Nemec, B.; Janzekovic, H.

2007-01-01

In the past, 12-months' fuel cycles in the Krsko NPP had not caused any problems regarding compliance with its Technical Specifications and license limits on liquid tritium releases (20 TBq/year, 8 TBq/three months). The first 18-months' fuel cycle, which was introduced in 2004, required fuel with higher enrichment, higher boron concentration in the primary coolant and more fuel rods with burnable poisons. In 2005, the NPP operated without refueling outage for the whole year and produced the highest amount of energy so far. Due to these facts and a few unplanned shutdowns and power reductions, production of tritium and releases increased strongly in 2005. As a result, the Krsko NPP hardly succeeded to stay within regulatory limits on tritium releases. However, the three-months' limit was exceeded in the first quarter of 2006. On the basis of conclusions acquired from the SNSA's study and practice of other European countries the SNSA considerably increased the annual limit of permitted liquid tritium releases (from 20 TBq to 45 TBq) and abolished the three-months' limit. At the same time, the SNSA reduced the limit of fission and activation products by halves. (author)

Quality Control Activities Related to Mechanical Maintenance of Safety Related Components at Krsko NPP

International Nuclear Information System (INIS)

Djakovic, D.

2016-01-01

For successful, safe and reliable operation of nuclear power plant, maintenance processes have to be systematically controlled and procedures for quality control of maintenance activities shall be established. This is requested by the quality assurance program, which shall provide control over activities affecting the quality of structures, systems, and components, considering their importance to safety. As a part of Quality and Nuclear Oversight Division (QNOD; SKV), the Quality Control Department (QC) provides quality control activities, which are deeply involved in maintenance processes at Krsko NPP, both on safety related and non-safety related (non-nuclear safety) components. QC activities on safety related components have to fulfil all requirements, which will enable the components to perform their intended safety functions. This paper describes quality control activities related to mechanical maintenance of safety related components at Krsko NPP and significant role of the Krsko plant QC Department in three particular maintenance cases connected with safety related components. In these three specific cases, the QC has confirmed its importance in compliance with quality assurance program and presented its significant added value in providing safe and reliable operation of the plant. The first maintenance activity was installation of nozzle check valves in the scope of a modification for improving regulation of spent fuel pit pumps. The QC Department performed receipt inspection of the valves. Using non-destructive examination methods and X-ray spectrometry, it was found out that the valve diffuser was made of improper material, which could cause progressive corrosion of the valve diffuser in borated water and consequently a loss of safety function of the valves followed by long-term consequences. The second one was the receipt inspection of containment ventilation fan coolers. The coolers were claimed and sent back to the supplier because the QC Department

Radioactive Control of Krsko Nuclear Power Plant Environment in the Year 1997

International Nuclear Information System (INIS)

Lulic, S.; Miklavzic, U.; Franic, Z.; Kanduc, M.

1998-01-01

Regular Krsko Nuclear Power Plant (NPPK) radioactivity control comprises the supervisions of the inventory of liquid and gaseous emissions at the source, and the independent supervisions of the input of radionuclides into larger environment (imisson). The controlled environment area consists primarily of a 12 kilometers large circle around the object, where the largest values of imission could be expected, and where possible changes in the Sava river and the underground waters could first be noticed. The circle has been enlarged upon the territory of the Republic of Croatia (RC) from Jesenice on Dolenjsko until Podsused (30 km of air - line distance). As reference points relevant for the readiness in the case of accident, especially for detection of iodine and aerosol air transport, the program comprises also measuring points in the RC at larger distances (from 14 to 27 km) in the direction of Zagreb its larger western surroundings (passive Thermoluminescent (TL) dosimeters in the each 42 km long). Continuous control of emission is performed by the radiological service of KNPP by routine procedures, supplemented by adequate measurements from other authorized institutions (intercomparisons, parallel measurements of representative and other samples). Summarised results of radioactive measurements for man-made and natural radionuclides are presented for different transfer media and exposure pathways in the form of assessed effective doses. Conservatively estimated dose burdens received by a member of the reference (critical) population group as the result of NPP emissions amount to a value of the committed effective dose equivalent smaller than 20 μSv/year. This value represents less than 1 % of the annual dose received on average from natural and artificial sources by a member of the general public in the normal environment. The yearly doses from natural radioactivity, global contamination (Chernobyl, atmospheric nuclear explosions), non-nuclear industries and

Criticality safety analysis of the NPP Krsko storage racks

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

2002-01-01

NPP Krsko is going to increase the capacity of the spent fuel storage pool by replacement of the existing racks with high-density racks. This will be the second reracking campaign since 1983 when storage was increased from 180 to 828 storage locations. The pool capacity will increase from 828 to 1694 with partial reracking by the spring 2003. The installed capacity will be sufficient for the current design plant lifetime. Complete reracking of the spent fuel pool will additionally increase capacity to 2321 storage locations. The design, rack manufacturing and installation has been awarded to the Framatome ANP GmbH. Burnup credit methodology, which was approved by the Slovenian Nuclear Safety Administration in previous licensing of existing racks, will be again implemented in the licensing process with the recent methodology improvements. Specific steps of the criticality safety analysis and representative results are presented in the paper.(author)

NLRP3 activation and mitosis are mutually exclusive events coordinated by NEK7, a new inflammasome component.

Science.gov (United States)

Shi, Hexin; Wang, Ying; Li, Xiaohong; Zhan, Xiaoming; Tang, Miao; Fina, Maggy; Su, Lijing; Pratt, David; Bu, Chun Hui; Hildebrand, Sara; Lyon, Stephen; Scott, Lindsay; Quan, Jiexia; Sun, Qihua; Russell, Jamie; Arnett, Stephanie; Jurek, Peter; Chen, Ding; Kravchenko, Vladimir V; Mathison, John C; Moresco, Eva Marie Y; Monson, Nancy L; Ulevitch, Richard J; Beutler, Bruce

2016-03-01

The NLRP3 inflammasome responds to microbes and danger signals by processing and activating proinflammatory cytokines, including interleukin 1β (IL-1β) and IL-18. We found here that activation of the NLRP3 inflammasome was restricted to interphase of the cell cycle by NEK7, a serine-threonine kinase previously linked to mitosis. Activation of the NLRP3 inflammasome required NEK7, which bound to the leucine-rich repeat domain of NLRP3 in a kinase-independent manner downstream of the induction of mitochondrial reactive oxygen species (ROS). This interaction was necessary for the formation of a complex containing NLRP3 and the adaptor ASC, oligomerization of ASC and activation of caspase-1. NEK7 promoted the NLRP3-dependent cellular inflammatory response to intraperitoneal challenge with monosodium urate and the development of experimental autoimmune encephalitis in mice. Our findings suggest that NEK7 serves as a cellular switch that enforces mutual exclusivity of the inflammasome response and cell division.

Equipment performance monitoring in NPP Krsko (Summarized system health report)

International Nuclear Information System (INIS)

Djetelic, N.; Cicvaric, D.

2004-01-01

Management common goal is safe, reliable, effective, acceptable to public and conservative/cautious operation of NPP Krsko. A set of programs, including Corrective Action Program, Performance Indicators, Operating Experience, Self Assessment and System Health Report, is developed to assist NPP Krsko management in fulfilling those goals. System Health Report is a tool that management can use to quickly assess how selected systems are performing, to determine where additional management attention is required and to determine if appropriate corrective actions have been established. Summarized System Health Report is developed for management's quick overview of systems status, important system malfunctions and problems as well as major changes from previous assessment period. Summarized Report contains nine sections: status difference including brief explanation, selected performance indicators, new equipment problems, functional failures, important problem analyses, action plan for systems with Potential Danger (RED) status, maintenance rule status overview and systems availability (planned and unplanned).(author)

NEK1 genetic variability in a Belgian cohort of ALS and ALS-FTD patients.

Science.gov (United States)

Nguyen, Hung Phuoc; Van Mossevelde, Sara; Dillen, Lubina; De Bleecker, Jan L; Moisse, Matthieu; Van Damme, Philip; Van Broeckhoven, Christine; van der Zee, Julie

2018-01-01

We evaluated the genetic impact of the amyotrophic lateral sclerosis (ALS) risk gene never in mitosis gene a-related kinase 1 (NEK1) in a Belgian cohort of 278 patients with ALS (n = 245) or ALS with frontotemporal dementia (ALS-FTD, n = 33) and 609 control individuals. We identified 2 ALS patients carrying a loss-of-function (LOF) mutation, p.Leu854Tyrfs*2 and p.Tyr871Valfs*17, that was absent in the control group. A third LOF variant p.Ser1036* was present in 2 sibs with familial ALS but also in an unrelated control person. Missense variants were common in both patients (3.6%) and controls (3.0%). The missense variant, p.Arg261His, which was previously associated with ALS risk, was detected with a minor allele frequency of 0.90% in patients compared to 0.33% in controls. Taken together, NEK1 LOF variants accounted for 1.1% of patients, although interpretation of pathogenicity and penetrance is complicated by the observation of occasional LOF variants in unaffected individuals (0.16%). Furthermore, enrichment of additional ALS gene mutations was observed in NEK1 carriers, suggestive of a "second hit" model were NEK1 variants may modify disease presentation of driving mutations. Copyright © 2017 The Author(s). Published by Elsevier Inc. All rights reserved.

Insight into Nek2A activity regulation and its pharmacological ...

African Journals Online (AJOL)

Ambuj Kumar

2012-11-28

Nov 28, 2012 ... mechanism of Nek2A dynamics was proposed where the phos- phorylation of ..... [36] Aleksandrov A, Simonson T. Molecular dynamics simulations show that ... mutant and its affect on the recruitment of centromere protein J.

Discovery of Novel Inhibitors for Nek6 Protein through Homology Model Assisted Structure Based Virtual Screening and Molecular Docking Approaches

Directory of Open Access Journals (Sweden)

P. Srinivasan

2014-01-01

Full Text Available Nek6 is a member of the NIMA (never in mitosis, gene A-related serine/threonine kinase family that plays an important role in the initiation of mitotic cell cycle progression. This work is an attempt to emphasize the structural and functional relationship of Nek6 protein based on homology modeling and binding pocket analysis. The three-dimensional structure of Nek6 was constructed by molecular modeling studies and the best model was further assessed by PROCHECK, ProSA, and ERRAT plot in order to analyze the quality and consistency of generated model. The overall quality of computed model showed 87.4% amino acid residues under the favored region. A 3 ns molecular dynamics simulation confirmed that the structure was reliable and stable. Two lead compounds (Binding database ID: 15666, 18602 were retrieved through structure-based virtual screening and induced fit docking approaches as novel Nek6 inhibitors. Hence, we concluded that the potential compounds may act as new leads for Nek6 inhibitors designing.

Corrective action program at Krsko NPP

International Nuclear Information System (INIS)

Skaler, F.; Divjak, G.; Kavsek, D.

2004-01-01

The Krsko NPP develops software that enables electronic reporting of all kind of deviations and suggestions for improvement at the plant. All the employees and permanent subcontractors have the access to the system and can report deviations. NPP has centralized decision process for the distribution of reported deviation. At this point all direct actions are electronically tracked. The immediate benefits of this new tool were: Reporting threshold has been lowered; Number of reporting people has increased; One computerized form for all processes; Decision, which process will solve the deviation, is centralized; All types of deviation are in the same environment; Our experiences of the processes are incorporated in the program; Control of work that has been done; Archiving is electronic only. Software basic data: Application system Corrective action program is a WEB application. Data is stored in Oracle 8.1.7 i database. Users access application through PL/SQL gateway on Oracle 9i Application Server 1.0.2. using Microsoft Internet Explorer browsers(Version 5 or later). Reports are implemented by Oracle Reports 6i. Menus are designed by Apycom Java Menus and Buttons v4.23. Our Presentation will include: Basic idea; Implementation change management; Demonstration of the program.(author)

Corrective action program at Krsko NPP

Energy Technology Data Exchange (ETDEWEB)

Skaler, F; Divjak, G; Kavsek, D [NPP Krsko, Krsko (Slovenia)

2004-07-01

The Krsko NPP develops software that enables electronic reporting of all kind of deviations and suggestions for improvement at the plant. All the employees and permanent subcontractors have the access to the system and can report deviations. NPP has centralized decision process for the distribution of reported deviation. At this point all direct actions are electronically tracked. The immediate benefits of this new tool were: Reporting threshold has been lowered; Number of reporting people has increased; One computerized form for all processes; Decision, which process will solve the deviation, is centralized; All types of deviation are in the same environment; Our experiences of the processes are incorporated in the program; Control of work that has been done; Archiving is electronic only. Software basic data: Application system Corrective action program is a WEB application. Data is stored in Oracle 8.1.7 i database. Users access application through PL/SQL gateway on Oracle 9i Application Server 1.0.2. using Microsoft Internet Explorer browsers(Version 5 or later). Reports are implemented by Oracle Reports 6i. Menus are designed by Apycom Java Menus and Buttons v4.23. Our Presentation will include: Basic idea; Implementation change management; Demonstration of the program.(author)

Krsko NPP radioactive waste characteristics

International Nuclear Information System (INIS)

Skanata, D.; Kroselj, V.; Jankovic, M.

2007-01-01

In May 2005 Krsko NPP initiated the Radioactive Waste Characterization Project and commissioned its realization to the consulting company Enconet International, Zagreb. The Agency for Radwaste Management was invited to participate on the Project. The Project was successfully closed out in August 2006. The main Project goal consisted of systematization the existing and gathering the missing radiological, chemical, physical, mechanical, thermal and biological information and data on radioactive waste. In a general perspective, the Project may also be considered as a part of broader scope of activities to support state efforts to find a disposal solution for radioactive waste in Slovenia. The operational low and intermediate level radioactive waste has been structured into 6 waste streams that contain evaporator concentrates and tank sludges, spent ion resins, spent filters, compressible and non-compressible waste as well as specific waste. For each of mentioned waste streams, process schemes have been developed including raw waste, treatment and conditioning technologies, waste forms, containers and waste packages. In the paper the main results of the Characterization Project will be briefly described. The results will indicate that there are 17 different types of raw waste that have been processed by applying 9 treatment/conditioning technologies. By this way 18 different waste forms have been produced and stored into 3 types of containers. Within each type of container several combinations should be distinguished. Considering all of this, there are 34 different types of waste packages altogether that are currently stored in the Solid Radwaste Storage Facility at the Krsko NPP site. Because of these findings a new identification system has been recommended and consequently the improvement of the existing database on radioactive waste has been proposed. The potential areas of further in depth characterization are indicated. In the paper a brief description on the

Marcel Rejmánek at 60 - the man and his work

Czech Academy of Sciences Publication Activity Database

Krahulec, F.; Lepš, Jan; Richardson, D. M.

2006-01-01

Roč. 78, - (2006), s. 361-374 ISSN 0032-7786 Institutional research plan: CEZ:AV0Z50070508 Keywords : Marcel Rejmánek Subject RIV: AJ - Letters, Mass-media, Audiovision Impact factor: 2.119, year: 2006

RELAP5/MOD3.3 assessment against MSIV closure events in Krsko NPP

International Nuclear Information System (INIS)

Parzer, I.

2002-01-01

The paper presents RELAP5/MOD3.3 analysis of two abnormal events occurred in Krsko NPP originating from sudden closure of Main Steam Isolation Valve (MSIV). Both events occurred before the SG replacement in 2000, the first one in September 1995 and the second one in January 1997. Valuable plant data were obtained from real plant transients and the RELAP5 code assessment was performed. Recently the last frozen version RELAP5/MOD3.3 has been released, before merging with another best-estimate thermalhydraulic system code TRAC into an integrated code. It is thus of utmost importance to assess models built in RELAP5 code against real plant transients before the code merger. A full twoloop plant model, developed at Jozef Stefan Institute (JSI), has been used for the analyses. The model includes old Westinghouse D4 type steam generators (SGs) with assumed 18% Utubes plugged in both steam generators. In the first case a malfunction in the MSIV in SG-1 caused inadvertent valve closure, while in the second case the valve stem has been broken in the SG-2, which also caused sudden valve closure.(author)

Development of Krsko Severe Accident Management Guidance (SAMG)

International Nuclear Information System (INIS)

Cizel, F.

1999-01-01

In this lecture development of severe accident management guidances for Krsko NPP are described. Author deals with the history of severe accident management and implementation of issues (validation, review of E-plan and other aspects SAMG implementation guidance). Methods of Westinghouse owners group, of Combustion Engineering owners group, of Babcock and Wilcox owners group, of the BWR owners group, as well as application of US SAMG methodology in Europe and elsewhere are reviewed

Establishment of ''Internal Rules'' and EDMS - Electronic Document Management System at NPP NEK

International Nuclear Information System (INIS)

Mandic, D.

2012-01-01

The main purpose of this paper is to present NPP's plans regarding the on-going project that started in November 2011, and that is related to the establishment of ''Internal Rules'' and EDMS - Electronic Document Management System.The term ''Internal Rules'' has been directly translated from Slovenian language (''Notranja pravila'') and adopted from the translated version of appropriate Slovenian national codes (ZVDAGA [1] in Slovenian language or PDAAIA [2] in English version). ''Internal Rules on capture and storage of materials in digital form'' refer to the rules adopted by a person as his/her internal act with reference to storage of his/her material. The main purpose for the establishment of the Internal Rules is to be able to justify that Krsko NPP is organized in compliance with the national codes covering that subject and strictly performing according to those Internal Rules. Once a Slovenian company achieves recognized and registered status in accordance with the Internal Rules document that has been certified and approved by the ARS (Archives of the Republic Slovenia), such company can utilize e-documents in the same way as they would utilize physical documents. Furthermore, a Slovenian company with approved Internal Rules can use e-documents in any legal aspect associated with the document's life cycle and the document's content as they would use the physical document or an authorized and approved copy of the physical document. Related to the nuclear regulatory background, NEK operates in compliance with the Slovenian legislation and also the US codes, regulations and guidelines; therefore, regarding the NPP specific documents, the Internal Rules and EDMS must also be in compliance with them. Since early 1990's, NEK has implemented document/records management system oriented towards supporting storage and management of physical documents/records and controlling distribution of active document copies. Document/records management system was supported by

Revision 2 of the Program of NPP Krsko Decommissioning and SF and LILW Disposal

International Nuclear Information System (INIS)

Levanat, I.; Lokner, V.; Rapic, A.

2010-01-01

First joint Slovenian-Croatian Program of NPP Krsko Decommissioning and SF and LILW Disposal (DP) was completed in 2004 and formally adopted in 2005. As bilateral agreement on the NPP requires periodic revisions at least each 5 years, revision 2 of DP was started in September 2008, with the purpose to incorporate relevant developments since the 1st revision, to improve the level of details and reliability of DP, and to propose updated and more accurate cost estimates and appropriate financing models. In the first phase of the revision, new supporting studies for DP modules were prepared. Among these studies, the most demanding was the NPP Krsko specific Preliminary Decommissioning Plan (PDP), complying with the IAEA-recommended format, which included development of the NPP decommissioning inventory database. For upgrade of SF management, new and more detailed descriptions with improved cost estimates were prepared. Update of LILW disposal concept was based on new developments and projects prepared for the Slovenian repository. In the second phase of the revision, integrated DP scenarios were formulated and analyzed. They integrate NPP decommissioning together with RW and SF management/disposal into rationally inter-related sequences. Boundary conditions for this revision required: (a) that the reference scenario from the previous revision should be re-examined, with appropriate variations or new alternatives; (b) that the option of the NPP Krsko life extension should also be included; and (c) that the possibility of diverging interests of the contracting parties should also be analyzed (i.e. waste division and separate management). Finally, scenario evaluation is intended to compare the analyzed scenarios taking into account both their feasibility and estimated costs. It should provide the basis for determining future financing of DP, namely the annuities to be paid by the NPP Krsko owners into the national decommissioning funds.(author).

Krsko: A case study for western nuclear power issues

International Nuclear Information System (INIS)

Bizal, M.R.

1996-01-01

This article is a review of issues surrounding the operation of the Krsko reactor in the former Yugoslav state of Slovenia. This reactor, a Westinghouse-supplied 632-MWe PWR, supplies 25% of Slovenia's electrical energy and is therefore a major element in the country's energy mix. There are environmental issues and political issues noted, and the project is currently evaluating the need for costly steam generator replacement

Analysis of steam generator plugging on core thermohydraulic performance of NPP Krsko; Analiza vpliva cepljenja cevi v upravljaniku na termohidravliko sredice JE Krsko

Energy Technology Data Exchange (ETDEWEB)

Kostadinov, V; Petelin, S; Sarler, B [Institut Jozef Stefan, Ljubljana (Yugoslavia)

1988-07-01

Nuclear safety analysis of NPP Krsko core operating at full power with 4% steam generator tubes plugged have been performed. Influence of individual parameters on core thermohydraulic performance have been evaluated. Using COBRA-III-C computer code we have analysed a core design (evaluation) model. The DNBR change was calculated as a consequence of 4% plugging. The influence of thermohydraulic parameters change on DNBR was analysed. (author)

Mechanisms controlling the temporal degradation of Nek2A and Kif18A by the APC/C-Cdc20 complex

DEFF Research Database (Denmark)

Sedgwick, G.G.; Hayward, D.G.; Nilsson, J.

2013-01-01

The Anaphase Promoting Complex/Cyclosome (APC/C) in complex with its co-activator Cdc20 is responsible for targeting proteins for ubiquitin-mediated degradation during mitosis. The activity of APC/C-Cdc20 is inhibited during prometaphase by the Spindle Assembly Checkpoint (SAC) yet certain...... substrates escape this inhibition. Nek2A degradation during prometaphase depends on direct binding of Nek2A to the APC/C via a C-terminal MR dipeptide but whether this motif alone is sufficient is not clear. Here, we identify Kif18A as a novel APC/C-Cdc20 substrate and show that Kif18A degradation depends...... by the APC/C. Nek2A and the mitotic checkpoint complex (MCC) have an overlap in APC/C subunit requirements for binding and we propose that Nek2A binds with high affinity to apo-APC/C and is degraded by the pool of Cdc20 that avoids inhibition by the SAC....

Radiation doses estimation for hypothetical NPP Krsko accidents without and with PCFV using RASCAL software

International Nuclear Information System (INIS)

Vukovic, Josip; Konjarek, Damir; Grgic, Davor

2014-01-01

Calculation is done using Source Term to Dose module of RASCAL (Radiological Assessment System Consequence Analysis) software to estimate projected radiation doses from a radioactive plume to the environment. Utilizing this module, it is possible to do preliminary assessment of consequences to the environment in case of adverse reactor conditions or releases from other objects containing radioactive materials before the emergency situation has happened or in the early phase. RASCAL is simple, easy to use, fast-running tool able to provide initial estimate of radiological consequences of nuclear accidents. Upon entering rather limited amount of input parameters for the Krsko NPP, mostly key plant parameters, time dependent source term calculation is executed to determine radioactive inventory release rates for different plant conditions, release paths and availability of protective measures. These rates given for each radionuclide as a function of time are used as an input to atmospheric dispersion and transport model. Together with release rates, meteorological conditions dataset serve as input to determine the behavior of the radioactive releases that is plume in the atmosphere. So as an output, RASCAL produces a 'dispersion envelope' of radionuclide concentrations in the atmosphere. These concentrations of radionuclides in the atmosphere are further used for estimating the doses to the environment and the public downwind the release point. Throughout this paper, dose assessment is performed for two distances, close-in distance and distance out to 40 km from the source, for hypothetical NPP Krsko accidents without and with Passive Containment Filtered Vent (PCFV) system used. Obvious difference is related to released radioactivity of Iodine isotopes. Results of radioactive effluents deposition in the environment are displayed via various doze parameters, radionuclide concentrations and materials exposure rates in this particular case. (authors)

Potential need for re-definition of the highest priority recovery action in the Krsko SAG-1

International Nuclear Information System (INIS)

Bilic Zabric, T.; Basic, I.

2005-01-01

Replacement of old SG (Steam Generators) [7] and the characteristic of new ones throws the question of proper accident management strategy, which leans on philosophy that repair and recovery actions have first priority. In the current NPP Krsko SAMGs (Severe Accident Management Guidelines), water supply to the SG has priority over re-injection water into the core. NPP Krsko reconsidered the highest priority of SAG-1 (inject water to the SG), against the WOG (Westinghouse Owners Group) generic approach (inject water into the core) and potential revision of Severe Accident Phenomenology Evaluations using MAAP (Modular accident Analysis Program) 4.0.5 code. (author)

NPP Krsko containment environmental conditions during postulated accident

International Nuclear Information System (INIS)

Kozaric, M.; Cavlina, N.; Spalj, S.

1989-01-01

This paper presents NPP Krsko containment pressure and temperature increase during Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB). Containment environmental condition calculation was performed by CONTEMPT4/MOD4 computer code. Design accident calculations were performed by RELAP4/MOD6 and RELAP5/MOD1 computer codes. Calculational abilities and application methodology of these codes are presented. The CONTEMPT code is described in more detail. The containment pressure and temperature time distribution are presented as well. (author)

Definice vnitřních zisků jako okrajových podmínek pro energetickou simulaci administrativních budov

NARCIS (Netherlands)

Duska, M; Drkal, F.; Hensen, J.L.M.

2006-01-01

Clánek zduraznuje význam volby vhodných okrajových podmínek pro správnost energetických simulacních výpoctu. Okrajové podmínky musí být vázány na úcel, pro který se simulacní výpocty provádí. Je predložen teoretický rozbor, metodologie a výsledky výpoctu ruzných okrajových podmínek stanovených z

Developing Effective Corrective Action Plan in Krsko NPP

International Nuclear Information System (INIS)

Bach, Bruno; Cizmek, Rudi; Bozin, Bojan

2014-01-01

Experience shows that many events could have been prevented if lessons had been learned from previous incidents. Event reporting thus has become an increasingly important aspect of the operation and regulation of all safety-related and public health industries. Different industries such as aeronautics, chemicals, transport and of course nuclear depend on Operating Experience (OE) feedback programs to provide lessons learned about safety. The information available under an OE programme for these organizations comprises internal event reports and analysis and external operating experience including reports on low level events and near misses and other relevant operating performance information. The worldwide OE programme (such as WANO OE) in nuclear power plants provides opportunity to learn from events at other plants. In particular, it alerts plants to mistakes or events that have occurred at other nuclear power plants and enables them to take corrective actions to prevent similar occurrences at their own plant. The intent of the effective and efficient OE program is therefore to improve personnel/plant safety, reliability and commercial performance of the operating nuclear power plants. Such a programme ensures that operating experience is analysed, events important to safety are reviewed in depth, lessons learned are disseminated to the staff and to the relevant national and international organizations and corrective actions are effectively implemented. Learning and applying the lessons from operating experience is an integral part of station safety culture and is encouraged by managers throughout the top plant administrative programs and procedures. Krsko NPP is developed its own OE program by using the most relevant INPO/WANO/IAEA guidelines as well as its own knowledge, skills an operating practice. The OE is a part of the Corrective Action Program (CAP), which is among top management programs. The purpose of this article is to present a part of the Krško NPP

Discovery of 4-aryl-N-arylcarbonyl-2-aminothiazoles as Hec1/Nek2 inhibitors. Part I: optimization of in vitro potencies and pharmacokinetic properties.

Science.gov (United States)

Lee, Ying-Shuan E; Chuang, Shih-Hsien; Huang, Lynn Y L; Lai, Chun-Liang; Lin, Yu-Hsiang; Yang, Ju-Ying; Liu, Chia-Wei; Yang, Sheng-chuan; Lin, Her-Sheng; Chang, Chia-chi; Lai, Jun-Yu; Jian, Pei-Shiou; Lam, King; Chang, Jia-Ming; Lau, Johnson Y N; Huang, Jiann-Jyh

2014-05-22

A series of 4-aryl-N-arylcarbonyl-2-aminothiazoles of scaffold 4 was designed and synthesized as Hec1/Nek2 inhibitors. Structural optimization of 4 led to compound 32 bearing C-4' 4-methoxyphenoxy and 4-(o-fluoropyridyl)carbonyl groups that showed low nanomolar in vitro antiproliferative activity (IC50: 16.3-42.7 nM), high intravenous AUC (64.9 μM·h, 2.0 mg/kg) in SD rats, and significant in vivo antitumor activity (T/C = 32%, 20 mg/kg, IV) in mice bearing human MDA-MB-231 xenografts. Cell responses resulting from Hec1/Nek2 inhibition were observed in cells treated with 32, including a reduced level of Hec1 coimmunoprecipitated with Nek2, degradation of Nek2, mitotic abnormalities, and apoptosis. Compound 32 showed selectivity toward cancer cells over normal phenotype cells and was inactive in a [(3)H]astemizole competitive binding assay for hERG liability screening. Therefore, 32 is as a good lead toward the discovery of a preclinical candidate targeting Hec1/Nek2 interaction.

Internal Audits and Quality Assurance Surveillance in NPP Krsko

International Nuclear Information System (INIS)

Cavajda, M.; Bracic, I.

1996-01-01

This paper is describing establishment of the requirements for the development and execution of the Internal Audit and Quality Assurance Surveillance Program in the NPP Krsko, to identify relevant regulatory commitment and other documents, and to exhibit different functional areas, levels and work categories and factors that impact selecting and scheduling an audit or surveillance. It is not intention of this paper to explain how and by whom an audit or surveillance has to be done. (author)

Some results of Krsko NPP core calculations and comparison with measurements

International Nuclear Information System (INIS)

Trkov, A.; Zefran, B.; Kromar, M.; Ravnik, M.; Slavic, S.

1996-01-01

Current status of the CORD-2 package is described. Results of the predictions of some important reactor core parameters are presented for the 12 th operation cycle of the Krsko NPP. Comparison with measurements is made to illustrate that the accuracy of the calculations is acceptable. Some comments are made on the enhancements, which are currently being implemented on the package. (author)

Engineering safety review mission Krsko NPP external events PSA. Ljubljana, Slovenia 19-23 February 1996. Final report

International Nuclear Information System (INIS)

Budnitz, R.J.; Smith, P.

1996-01-01

Within the scope of the TC Project RER/9/035, a review mission visited Ljubljana, Slovenia, 19-23 February 1996. Two outside experts, Messrs. R.J. Budnitz (USA) and Paul Smith (USA), as well as a staff member, A. Guerpinar (ESS-NSNI) took part in the review. The purpose of the mission was to assist the Slovenian Nuclear Safety Administration to review the external events PSA prepared by Krsko NPP consultants Westinghouse Energy Systems Europe and EQE International. Another seismic safety review was performed concurrently in Ljubljana involving the investigations in relation to the tectonic stability and reassessment of the design basis ground motion characterization for the Krsko NPP site

RELAP5 Low Temperature Overpressurization Analysis for NPP Krsko

International Nuclear Information System (INIS)

Basic, I.; Krajnc, B.; Bajs, T.

2000-01-01

NEK has expressed interest in the acceptability of removing the autoclosure interlock (ACI) on the Residual Heat Removal System (RHRS) suction/isolation valves. This interest is in response to growing concerns about the loss of residual heat removal capability during cold shutdown and refueling operations. This article describes effort done to justify removal of the ACI in the light of low temperature overpressure protection of Reactor Coolant System (RCS) and RHRS and interfacing system LOCA potential. The intent of this article is to review the NEK RHRS relief valves sizing design basis and verify if the relief valves provide RHRS overpressure protection for the events possible at cold shutdown. Inadvertent isolation of RHRS during hot and cold shutdown (with reactor coolant system closed and temperatures below 177o Code 4 and5) presents one of the major safety concerns in this mode of operation. Detailed RELAP5 model of NPP Kriko following steam generator (SG) replacement and core uprate has been used in the frame of this analysis verification of RHRS relief valves sizing. The following limiting cases for cold shutdown with RCS solid conditions have been analyzed: - ransients that affect the system input/output mass balance, - ransients that affect the heat input/removal balance. (author)

Integration of the Ovation Based Distributed Turbine Control System into the Existing Process Information System and Full Scope Simulator at NPP Krsko

International Nuclear Information System (INIS)

Cicvaric, D.

2010-01-01

Programmable Digital Electro Hydraulic System (PDEH) is Turbine Control System (TCS), built on Emerson OVATION Distributed Control System (DCS) platform and installed by the Westinghouse Electric Company at the Krsko Nuclear Power Plant as the replacement for the DEH Mod II turbine control system. Core of the PDEH system consist of three pairs of redundant controllers (ETS, OA/OPC and ATC/MSR) configured for the Turbine Generator (TG) set protection, control and monitoring functions. Existing serial data link between replaced DEH Mod II and Process Information System (PIS) was removed and replaced with redundant bi-directional Ethernet TCP/IP data link via two Data Link servers in client-server architecture configuration. All hardwired signals and some of the important calculated signals are being transferred from PDEH to PIS. Main purpose of PIS data link is trending utilization at the existing PIS workstations with pre-configured trend groups and centralized data archiving. Most of the PDEH display screens (mimics) were also replicated on the PIS platform, so that TG set monitoring and operation overview can be performed over the PIS network as well as over the Process Computer Network (PCN) with PMSNT-view utility. The simulator is implemented using a stimulated Windows based Ovation platform and a SGI IRIX based Plant Model Computer (PMC) using the L-3 MAPPS simulation software platform. Two PDEH stimulated systems are installed at the Krsko Full Scope Simulator (KFSS), one for foreground and another for background simulation. Stimulated PDEH hardware is essentially identical to that installed in the plant with the exception of hardware redundancy, isolation features and interface with physical plant I/O. The Ovation control logic sheets are executed with virtual controllers hosted on a simulator specific Virtual Controller Host (VCH) Workstation. The data interface between the simulator Ovation system and the PMC is accomplished through the Ethernet

Heat and radiation analysis of NPP Krsko irradiated fuel

International Nuclear Information System (INIS)

Lalovic, M.

1986-01-01

Radioactive and heat potential for irradiated fuel in the region 2 with burnup of 13400 MWd/tHM, and in the region 4A with burnup of 9360 MWd/tHM for NPP KRSKO, was calculated. Computer code KORIGEN (Karlsruhe Oak Ridge Isotope Generation and Depletion Code) was used. The aspects of radiation (mainly gamma and neutrons) and of heat production was considered with respect to their impact on fuel handing and waste management. Isotopic concentrations for irradiated fuel was calculated and compared with Westinghouse data. (author)

Croatian Capacity for Management of the NPP Krsko Radioactive Waste

International Nuclear Information System (INIS)

Levanat, Ivica; Lokner, Vladimir

2014-01-01

Together with Slovenia, Croatia is responsible for management of the NPP Krsko radioactive waste and spent fuel. So far, no firm agreement on specific solutions has been reached between the two countries. On the contrary, all activities related to revision and development of the joint Program of the NPP decommissioning and spent fuel and radioactive waste management were discontinued several years ago. Unless Slovenia and Croatia definitely agree on joint solutions in the meantime, Croatia will have to begin transfer of one half of the NPP Krsko spent fuel and radioactive waste into its territory in about nine years. Presently, however, Croatian capacities for such an undertaking are seriously inadequate in several respects, and they are not developing in any promising way. For no rational reason, this state of the Croatian capacities has been maintained (recently even deteriorating in some respects) for at least a decade, disregarding also for at least two years the explicit requirements of the EU Directive 2011/70/EURATOM aimed at establishing a Community framework for the responsible and safe management of spent fuel and radioactive waste. In fall of 2012, Fund for financing the NPP Krsko decommissioning and spent fuel and radioactive waste disposal was appointed as the Croatian expert organization for revision and development of the program of these same activities it had originally been supposed only to finance. In 2013 the Fund expanded its activities to a low-profile attempt at revitalization of the Croatian radioactive waste repository project, although the Fund is not yet properly capacitated for either of these tasks. The above is hardly in compliance with the Directive requirements, such as to establish 'a national legislative, regulatory and organisational framework' 'that allocates responsibility... between relevant competent bodies'. The lack of competent experts in the field appears to affect the quality of Croatian legislative

Reactor Coolant Pump Motor Maintenance Experience in Krsko NPP

International Nuclear Information System (INIS)

Vukovic, J.; Besirevic, A.; Boljat, Z.

2016-01-01

After thirty years of service as well as maintenance in Krsko NPP both original Reactor Coolant Pump (RCP) motors are remanufactured by original vendor Westinghouse and a new one was purchased. Design function of the RCP motor is to drive Reactor Coolant Pump and for coast-down feature during Design Basis Accident. This paper will give a view on maintenance issues of RCP motor during the thirty years of service and maintenance in Krsko NPP to be kept functionally operational. During the processes of remanufacturing inspection and disassembly it was made possible to get a deeper perspective in the motor condition and the wear or fatigue of the motor parts. Parameters like bearing & winding temperature, absolute and relative vibration greatly affect motor operation if not kept inside design margins. Rotational speed causes heat generation at the bearings which is then associated with oil temperatures and as a consequence bearing temperatures. That is why the most critical parts of the motor are the components of upper and lower bearing assembly. The condition of motor stator and rotor assembly technical characteristics shall be explained with respect to influence of demanding environmental conditions that the motor is exposed. Assessment shall be made how does the wear of critical RCP motor parts can influence reliable performance of the motor if not maintained in proper way. Information on upgrades that were done on RCP motor shall be shared: Oil Spillage Protection System (OSPS), Stator upgrades, Dynamic Port, etc. (author).

Plant safety and performance indicators for regulatory use

International Nuclear Information System (INIS)

Ferjancic, M.; Nemec, T.; Cimesa, S.

2004-01-01

Slovenian Nuclear Safety Administration (SNSA) supervises nuclear and radiological safety of Krsko NPP. This SNSA supervision is performed through inspections, safety evaluations of plant modifications and event analyses as well as with the safety and performance indicators (SPI) which are a valuable data source for plant safety monitoring. In the past SNSA relied on the SPI provided by Krsko NPP and did not have a set of SPI which would be more appropriate for regulatory use. In 2003 SNSA started with preparation of a new set of SPI which would be more suitable for performing the regulatory oversight of the plant. New internal SNSA procedure which is under preparation will define use and evaluation of SPI and will include definitions for the proposed set of SPI. According to the evaluation of SPI values in comparison with the limiting values and/or trending, the procedure will define SNSA response and actions. (author)

Jaroslav Pánek - představitel české historiografie v Polsku

Czech Academy of Sciences Publication Activity Database

Baron, Roman

2017-01-01

Roč. 115, č. 1 (2017), s. 47-78 ISSN 0862-6111 Institutional support: RVO:67985963 Keywords : historiography * Czech-Polish Relations * Polish-Czech history studies * Jaroslav Pánek Subject RIV: AB - History OBOR OECD: History ( history of science and technology to be 6.3, history of specific sciences to be under the respective headings)

A novel mutation causing nephronophthisis in the Lewis polycystic kidney rat localises to a conserved RCC1 domain in Nek8

Directory of Open Access Journals (Sweden)

McCooke John K

2012-08-01

Full Text Available Abstract Background Nephronophthisis (NPHP as a cause of cystic kidney disease is the most common genetic cause of progressive renal failure in children and young adults. NPHP is characterized by abnormal and/or loss of function of proteins associated with primary cilia. Previously, we characterized an autosomal recessive phenotype of cystic kidney disease in the Lewis Polycystic Kidney (LPK rat. Results In this study, quantitative trait locus analysis was used to define a ~1.6Mbp region on rat chromosome 10q25 harbouring the lpk mutation. Targeted genome capture and next-generation sequencing of this region identified a non-synonymous mutation R650C in the NIMA (never in mitosis gene a- related kinase 8 ( Nek8 gene. This is a novel Nek8 mutation that occurs within the regulator of chromosome condensation 1 (RCC1-like region of the protein. Specifically, the R650C substitution is located within a G[QRC]LG repeat motif of the predicted seven bladed beta-propeller structure of the RCC1 domain. The rat Nek8 gene is located in a region syntenic to portions of human chromosome 17 and mouse 11. Scanning electron microscopy confirmed abnormally long cilia on LPK kidney epithelial cells, and fluorescence immunohistochemistry for Nek8 protein revealed altered cilia localisation. Conclusions When assessed relative to other Nek8 NPHP mutations, our results indicate the whole propeller structure of the RCC1 domain is important, as the different mutations cause comparable phenotypes. This study establishes the LPK rat as a novel model system for NPHP and further consolidates the link between cystic kidney disease and cilia proteins.

USAR managing and updating process

International Nuclear Information System (INIS)

Prah, M.; Spiler, J.

1996-01-01

In this paper basis and background of the FSAR (Final Safety Analysis Report) document and its conversion process to the USAR (Updated Safety Analysis Report) document are described. In addition, there are internal and external reviews as approval process presented. The following is included in our new approach to manage USAR changes: initiating the USAR change, technical reviewing, preparing a safety evaluation, KSC (Krsko Safety Committee) and KOC (Krsko Operating Committee) review, ESD Director approval, and the Regulatory Body review or approval. The intensive technological modification activities started in the year 1992 when the NEK Engineering Services Division was established. These activities are one of the most important reason for a very intensive USAR items change. The other reason for its conversation to an electronic format is a possibility for easier and faster searching, updating and changing process and introducing a new systematic USAR managing approach as mentioned above. (author)

The APC/C Coordinates Retinal Differentiation with G1 Arrest through the Nek2-Dependent Modulation of Wingless Signaling.

Science.gov (United States)

Martins, Torcato; Meghini, Francesco; Florio, Francesca; Kimata, Yuu

2017-01-09

The cell cycle is coordinated with differentiation during animal development. Here we report a cell-cycle-independent developmental role for a master cell-cycle regulator, the anaphase-promoting complex or cyclosome (APC/C), in the regulation of cell fate through modulation of Wingless (Wg) signaling. The APC/C controls both cell-cycle progression and postmitotic processes through ubiquitin-dependent proteolysis. Through an RNAi screen in the developing Drosophila eye, we found that partial APC/C inactivation severely inhibits retinal differentiation independently of cell-cycle defects. The differentiation inhibition coincides with hyperactivation of Wg signaling caused by the accumulation of a Wg modulator, Drosophila Nek2 (dNek2). The APC/C degrades dNek2 upon synchronous G1 arrest prior to differentiation, which allows retinal differentiation through local suppression of Wg signaling. We also provide evidence that decapentaplegic signaling may posttranslationally regulate this APC/C function. Thus, the APC/C coordinates cell-fate determination with the cell cycle through the modulation of developmental signaling pathways. Copyright © 2017 The Author(s). Published by Elsevier Inc. All rights reserved.

Validation of the CORD-2 System for the Nuclear Design Calculations of the NPP Krsko Core

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

2016-01-01

The CORD-2 package intended for core design calculations of PWRs has be recently updated with some improved models. Since the modifications could substantially influence the obtained results, a technical validation process is required. This paper presents comparison of some calculated and measured parameters of the NPP Krsko core needed to qualify the package. Critical boron concentrations at hot full power for selected cycle burnup points and several parameters obtained during the start-up testing at the beginning of each cycle (hot zero power critical concentration, isothermal temperature coefficient and rods worth) for all 27 finished cycles of operation are considered. In addition, assembly-wise power distribution for some selected cycles is checked. Comparison has shown very good agreement of the CORD-2 calculated values with the selected measured parameter of the NPP Krsko core.(author).

Evaluation of the safety margins during shutdown for NPP Krsko

International Nuclear Information System (INIS)

Bencik, V.; Sadek, S.; Bajs, T.

2004-01-01

In the paper the results of RELAP5/mod3.3 calculations of critical parameters during shutdown for NPP Krsko are presented. Conservative evaluations have been performed at NPP Krsko to determine the minimum configuration of systems required for the safe shutdown operation. Critical parameters in these evaluations are defined as the time to start of the boiling and the time of the core dry-out. In order to have better insight into the available margins, the best estimate code RELAP5/mod3.3 has been used to calculate the same parameters. The analyzed transient is the loss of the Residual Heat Removal (RHR) system, which is used to remove decay heat during shutdown conditions. Several configurations that include open and closed Reactor Coolant System (RCS) were considered in the evaluation. The RELAP5/mod3.3 analysis of the loss of the RHR system has been performed for the following cases: 1) RCS closed and water solid, 2) RCS closed and partially drained, 3) Pressurizer manway open, Steam Generator (SG) U tubes partially drained, 4) Pressurizer and SG manways open, SG U tubes completely drained, 5) Pressurizer manway open, SGs drained, SG nozzle dams installed and 6) SG nozzle dams installed, pressurizer manway open, 1 inch break at RHR pump discharge in the loop with pressurizer. Both RHR trains were assumed in operation prior to start of the transient. The maximum average steady state temperature for all analyzed cases was limited to 333 K. (author)

Development towards optimization of emergency countermeasures

International Nuclear Information System (INIS)

Susnik, J.

1995-01-01

We report on severe accident scenarios consequences evaluation in connection to the applied emergency countermeasures and use of the PC COSYMA code. We present some of the results for the reactor core melt accident assumed to happen at the 632 MWE PWR Krsko Nuclear Power Plant in Slovenia. The efficiency of several potential countermeasures in limiting the late health effects was studied. Regarding the source term, the majority of release parameters are as specified for category 2 in the German Risk Study. Site specific data were used. As the outside (meteorologic) conditions during the potential accident onset can be very different, the study limited to the deterministic runs, assuming the wind direction upstream the Sava river into the WNW direction, wind speed of 5 ms -1 and the C Pasquill stability category. The population distribution file was formed from the NEK-FSAR data for the 1991. (author)

Training courses for the staff of the nuclear power station KRSKO conducted at the TRIGA reactor center in Ljubljana

International Nuclear Information System (INIS)

Pregl, G.; Najzer, M.

1976-01-01

The training program for the Nuclear Power Station Krsko was divided into two modules: fundamentals of nuclear engineering and specialized training according to duties that candidates are supposed to take at the power station. Basic training was organized at the TRIGA Reactor Center in Ljubljana in two different versions. The first version intended for plant operators and all engineers lasted for six months and included about 500 hours of classroom lessons and seminars and 31 laboratory experiments. The educational program was conventional. The following topics were covered: nuclear and atomic physics, reactor theory, reactor dynamics, reactor instrumentation and control, heat transfer in nuclear power plants, nuclear power plant systems, reactor materials, reactor safety, and radiation protection. Until now, two groups, consisting of 37 candidates altogether, have attended this basic course. Plans have been made to conduct two additional courses of about 20 students each for technicians other than operators. The program of this second version will be reduced, with the emphasis on reactor core physics and radiation protection. Classroom lessons will be strongly supported by laboratory experiments. (author)

NPP Krsko analysis of the loss of the RHR system during mid-loop operation

International Nuclear Information System (INIS)

Bencik, V.; Feretic, D.; Debrecin, N.

2002-01-01

In the paper the results of the NPP Krsko analysis of the loss of the Residual Heat Removal (RHR) system at mid-loop conditions using RELAP5/MOD 3.2.2 Gamma and RELAP5/MOD 3.3 Beta code are presented. Both pressurizer and Steam Generator (SG) 1 manway were open. The facility was open to the containment atmosphere and filled with air above liquid level. Loss of the RHR system when Reactor Coolant System (RCS) is open causes quick boiling in the core and loss of the inventory available for the cooling of the core through the openings. Aims of the analysis were threefold. First, the consequences of the transient for NPP Krsko, i.e., the time to core uncovery was determined. Secondly, the influence of the applied RELAP5 code version (MOD 3.2.2 Gamma and MOD 3.3 Beta) in the analysis of that particular transient with noncondensable gases was assessed. Third, the analysis with SG secondary sides under wet lay-up conditions was performed in order to assess the influence of condensation in the SG U tubes on liquid inventory in the system and core cooling capability.(author)

Computer system for nuclear power plant parameter display

International Nuclear Information System (INIS)

Stritar, A.; Klobuchar, M.

1990-01-01

The computer system for efficient, cheap and simple presentation of data on the screen of the personal computer is described. The display is in alphanumerical or graphical form. The system can be used for the man-machine interface in the process monitoring system of the nuclear power plant. It represents the third level of the new process computer system of the Nuclear Power Plant Krsko. (author)

Jaroslav Pánek a Český historický ústav v Římě

Czech Academy of Sciences Publication Activity Database

Semotanová, Eva

2017-01-01

Roč. 115, č. 1 (2017), s. 91-97 ISSN 0862-6111 Institutional support: RVO:67985963 Keywords : Jaroslav Pánek * Czech Historical Institute in Rome * historiography Subject RIV: AB - History OBOR OECD: History (history of science and technology to be 6.3, history of specific sciences to be under the respective headings)

Determination of BEACON Coupling Coefficients using data from Xenon transient

International Nuclear Information System (INIS)

Bozic, M.; Kurincic, B.

2007-01-01

NEK uses BEACO TM code (BEACO TM - Westinghouse Best Estimate Analyzer for Core Operating Nuclear) for core monitoring, analysis and core behaviour prediction. Coupling Coefficients determine relationship between core response and excore instrumentation. Measured power distribution using incore moveable detectors during Xenon transient with sufficient power axial offset change is the most important data for further analysis. Classic methodology and BEACO TM Conservative methodology using established Coupling Coefficients are compared on NPP Krsko case. BEACON TM Conservative methodology with predefined Coupling Coefficients is used as a surveillance tool for verification of relationship between core and excore instrumentation during power operation. (author)

Transition from 12 months to 18 months cycles at Krsko in a core physics perspective

International Nuclear Information System (INIS)

Jensen-Tornehed, J.

2004-01-01

Krsko has historically been operating in 12 months cycles with an annual outage for refuelling and maintenance work. Krsko is now in a transition from 12 months to 18 months cycles. Cycle 19, June 2002 - May 2003, was the last 12 month cycle. Cycle 20, June 2003 - September 2004 is a 15 month transition cycle and cycle 21, September 2004 - April 2006 will be the first 18 month cycle. This paper will describe the effects of the transition in a core physics perspective. There are big differences in how to design an 18 month cycle in comparison with a 12 month cycle. The required number of feed assemblies increases, as well as the content of burnable absorbers in the fuel. The strategy of the loading pattern has to be changed with the increased number of fresh fuel assemblies. The most limiting margins can be different for different cycle lengths which also affect the fresh assembly design and loading pattern during the transition. During the core design for cycle 21 the Moderator Temperature Coefficient was the main issue, which caused the need for extra amount of burnable absorbers. (author)

Parameter estimation of component reliability models in PSA model of Krsko NPP

International Nuclear Information System (INIS)

Jordan Cizelj, R.; Vrbanic, I.

2001-01-01

In the paper, the uncertainty analysis of component reliability models for independent failures is shown. The present approach for parameter estimation of component reliability models in NPP Krsko is presented. Mathematical approaches for different types of uncertainty analyses are introduced and used in accordance with some predisposed requirements. Results of the uncertainty analyses are shown in an example for time-related components. As the most appropriate uncertainty analysis proved the Bayesian estimation with the numerical estimation of a posterior, which can be approximated with some appropriate probability distribution, in this paper with lognormal distribution.(author)

Whole-exome sequencing in amyotrophic lateral sclerosis suggests NEK1 is a risk gene in Chinese.

Science.gov (United States)

Gratten, Jacob; Zhao, Qiongyi; Benyamin, Beben; Garton, Fleur; He, Ji; Leo, Paul J; Mangelsdorf, Marie; Anderson, Lisa; Zhang, Zong-Hong; Chen, Lu; Chen, Xiang-Ding; Cremin, Katie; Deng, Hong-Weng; Edson, Janette; Han, Ying-Ying; Harris, Jessica; Henders, Anjali K; Jin, Zi-Bing; Li, Zhongshan; Lin, Yong; Liu, Xiaolu; Marshall, Mhairi; Mowry, Bryan J; Ran, Shu; Reutens, David C; Song, Sharon; Tan, Li-Jun; Tang, Lu; Wallace, Robyn H; Wheeler, Lawrie; Wu, Jinyu; Yang, Jian; Xu, Huji; Visscher, Peter M; Bartlett, Perry F; Brown, Matthew A; Wray, Naomi R; Fan, Dongsheng

2017-11-17

Amyotrophic lateral sclerosis (ALS) is a progressive neurological disease characterised by the degeneration of motor neurons, which are responsible for voluntary movement. There remains limited understanding of disease aetiology, with median survival of ALS of three years and no effective treatment. Identifying genes that contribute to ALS susceptibility is an important step towards understanding aetiology. The vast majority of published human genetic studies, including for ALS, have used samples of European ancestry. The importance of trans-ethnic studies in human genetic studies is widely recognised, yet a dearth of studies of non-European ancestries remains. Here, we report analyses of novel whole-exome sequencing (WES) data from Chinese ALS and control individuals. WES data were generated for 610 ALS cases and 460 controls drawn from Chinese populations. We assessed evidence for an excess of rare damaging mutations at the gene level and the gene set level, considering only singleton variants filtered to have allele frequency less than 5 × 10 -5 in reference databases. To meta-analyse our results with a published study of European ancestry, we used a Cochran-Mantel-Haenszel test to compare gene-level variant counts in cases vs controls. No gene passed the genome-wide significance threshold with ALS in Chinese samples alone. Combining rare variant counts in Chinese with those from the largest WES study of European ancestry resulted in three genes surpassing genome-wide significance: TBK1 (p = 8.3 × 10 -12 ), SOD1 (p = 8.9 × 10 -9 ) and NEK1 (p = 1.1 × 10 -9 ). In the Chinese data alone, SOD1 and NEK1 were nominally significantly associated with ALS (p = 0.04 and p = 7 × 10 -3 , respectively) and the case/control frequencies of rare coding variants in these genes were similar in Chinese and Europeans (SOD1: 1.5%/0.2% vs 0.9%/0.1%, NEK1 1.8%/0.4% vs 1.9%/0.8%). This was also true for TBK1 (1.2%/0.2% vs 1.4%/0.4%), but

Applicability of coupled code RELAP5/GOTHIC to NPP Krsko MSLB calculation

International Nuclear Information System (INIS)

Keco, M.; Debrecin, N.; Grgic, D.

2005-01-01

Usual way to analyze Main Steam Line Break (MSLB) accident in PWR plants is to calculate core and containment responses in two separate calculations. In first calculation system code is used to address behaviour of nuclear steam supply system and containment is modelled mainly as a boundary condition. In second calculation mass and energy release data are used to perform containment analysis. Coupled code R5G realized by direct explicit coupling of system code RELAP5/MOD3.3 and containment code GOTHIC is able to perform both calculations simultaneously. In this paper R5G is applied to calculation of MSLB accident in large dry containment of NPP Krsko. Standard separate calculation is performed first and then both core and containment responses are compared against corresponding coupled code results. Two versions of GOTHIC code are used, one old ver 3.4e and the last one ver 7.2. As expected, differences between standard procedure and coupled calculations are small. The performed analyses showed that classical uncoupled approach is applicable in case of large dry containment calculation, but that new approach can bring some additional insight in understanding of the transient and that can be used as simple and reliable procedure in performing MSLB calculation without any significant calculation overhead. (author)

Analysis of Rod Withdrawal at Power (RWAP) Accident using ATHLET Mod 2.2 Cycle A and RELAP5/mod 3.3 Codes

International Nuclear Information System (INIS)

Bencik, V.; Cavlina, N.; Grgic, D.

2012-01-01

The system code ATHLET is being developed at Gesellschaft fuer Anlagen-und Reaktorsicherheit (GRS) in Germany. In 1996, the NPP Krsko (NEK) input deck for ATHLET Mod 1.1 Cycle C has been developed at Faculty of Electrical Engineering (FER), University of Zagreb. The input deck was tested by analyzing the realistic plant event 'Main Steam Isolation Valve Closure' and the results were assessed against the measured data. The input deck was established before plant modernization that took place in 2000 and included the power uprate and SG replacement. The released ATHLET version (Mod 2.2 Cycle A) is now being available at FER Zagreb. Accordingly, the NEK input deck for ATHLET Mod 2.2 Cycle A has been developed. A completely new input deck has been created taking into account the large number of changes due to power uprate and SG replacement as well as taking advantage of developmental work on NEK data base performed at FER. The new NEK input deck for ATHLET code has been tested by analyzing the Rod Withdrawal Power (RWAP) accident and the results were assessed against the analysis performed by RELAP5/mod 3.3 code. The RWAP accident can be either Departure from Nucleate Boiling (DNB) ratio or overpower limiting accident depending on initial power and reactivity insertion rate. Since the automatic rod control system is assumed unavailable, the only negative reactivity is due to Doppler and moderator feedback. Consequently, the nuclear power and the transferred heat in the steam generators (SGs) increase. Since the steam flow to the turbine and the extracted power from the SGs remain constant, the SG secondary pressure and the temperatures on the primary side increase. Unless terminated by manual or automatic action, the power mismatch between primary and secondary side and the resultant coolant temperature rise could eventually result in DNB ratio and/or fuel centreline melt. In order to avoid core damage, the reactor protection system is designed to automatically

Some possibilities for improvement of fuel utilization in nuclear power plants

International Nuclear Information System (INIS)

Kocic, A.; Marinkovic, N.

1983-01-01

Methods for improving the nuclear fuel utilization with the emphasis on LWRs are being dealt with in this paper. Some basic results concerning tubular fuel pellets of the Krsko nuclear power plants are presented, showing promising possibilities for uranium saving from the neutronics point of view. (author)

A Social Media-Based Acute Alcohol Consumption Behavior (NekNomination): Case Series in Italian Emergency Departments.

Science.gov (United States)

Barbieri, Stefania; Feltracco, Paolo; Lucchetta, Vittorio; Gaudio, Rosa Maria; Tredese, Alberto; Bergamini, Mauro; Vettore, Gianna; Pietrantonio, Vincenzo; Avato, Francesco Maria; Donato, Daniele; Boemo, Deris Gianni; Nesoti, Maria Vittoria; Snenghi, Rossella

2018-01-31

NekNomination, also known as NekNominate, Neck and Nominate, or Neck Nomination, is a social network-based drinking game which is thought to have originated in Australia and spread all over the world between 2013 and 2014. Individuals record videos of themselves while rapidly drinking excessive quantities of alcoholic drinks (necking) and then nominate friends to outdo them within 24 hours; the videos are then posted on social media such as Facebook or YouTube. The consequences of this drinking game have been very dangerous; at least 5 people under age 30 years have died after drinking deadly cocktails, and many others have suffered from alcohol intoxication. The goal of the research is to evaluate data about clinically important acute alcohol intoxication among teenagers and young adults and inform and educate the general public, especially parents, teachers, and health workers, about the spreading craze of dangerous Internet-related behavior among today's teenagers and young people up to the age of 23 years. Patients aged 15 to 23 years with acute alcohol intoxication who came to the emergency department (ED) of 2 major hospitals in Italy from January 1, 2011, to June 30, 2014, were included in this study. Data were retrieved from prehospital and intrahospital medical records and included personal information, methods of intoxication, triage color code, date and time of access to the ED, any relevant signs and symptoms, blood alcohol concentration, and diagnosis at discharge. A total of 450 young patients (male 277/450, 61.5%, female 173/450, 38.5%; age 15 to 16 years 15/450, 3.3%, age 17 to 18 years 184/450, 40.9%, age 19 to 23 years 251/450, 55.8%) were recruited. The causes of intoxication were happy hour, binge drinking, NekNominate, eyeballing, other alcoholic games, or a mix of them. Happy hour was found to be more common among the older patients, whereas NekNominate accounted for almost half of the youngest group of hospitalizations. Eyeballing occurred in

Jaroslav Pánek, místopředseda Akademie věd České republiky

Czech Academy of Sciences Publication Activity Database

Petráňová, Lydia

2017-01-01

Roč. 115, č. 1 (2017), s. 84-90 ISSN 0862-6111 Institutional support: RVO:68378076 Keywords : Jaroslav Pánek * Scientific-organizational Activities * Czech Academy of Science s Subject RIV: AB - History OBOR OECD: History (history of science and technology to be 6.3, history of specific science s to be under the respective headings)

Bohuslav Havránek očima svých současníků

Czech Academy of Sciences Publication Activity Database

Dvořáčková, Věra

2017-01-01

Roč. 9, č. 1 (2017), s. 22-38 ISSN 1804-1221 R&D Projects: GA ČR(CZ) GA17-22085S Institutional support: RVO:67985921 Keywords : structuralism * Bohuslav Havránek Subject RIV: AB - History OBOR OECD: History (history of science and technology to be 6.3, history of specific sciences to be under the respective headings)

Whole-exome sequencing in amyotrophic lateral sclerosis suggests NEK1 is a risk gene in Chinese

Directory of Open Access Journals (Sweden)

Jacob Gratten

2017-11-01

Full Text Available Abstract Background Amyotrophic lateral sclerosis (ALS is a progressive neurological disease characterised by the degeneration of motor neurons, which are responsible for voluntary movement. There remains limited understanding of disease aetiology, with median survival of ALS of three years and no effective treatment. Identifying genes that contribute to ALS susceptibility is an important step towards understanding aetiology. The vast majority of published human genetic studies, including for ALS, have used samples of European ancestry. The importance of trans-ethnic studies in human genetic studies is widely recognised, yet a dearth of studies of non-European ancestries remains. Here, we report analyses of novel whole-exome sequencing (WES data from Chinese ALS and control individuals. Methods WES data were generated for 610 ALS cases and 460 controls drawn from Chinese populations. We assessed evidence for an excess of rare damaging mutations at the gene level and the gene set level, considering only singleton variants filtered to have allele frequency less than 5 × 10–5 in reference databases. To meta-analyse our results with a published study of European ancestry, we used a Cochran–Mantel–Haenszel test to compare gene-level variant counts in cases vs controls. Results No gene passed the genome-wide significance threshold with ALS in Chinese samples alone. Combining rare variant counts in Chinese with those from the largest WES study of European ancestry resulted in three genes surpassing genome-wide significance: TBK1 (p = 8.3 × 10–12, SOD1 (p = 8.9 × 10–9 and NEK1 (p = 1.1 × 10–9. In the Chinese data alone, SOD1 and NEK1 were nominally significantly associated with ALS (p = 0.04 and p = 7 × 10–3, respectively and the case/control frequencies of rare coding variants in these genes were similar in Chinese and Europeans (SOD1: 1.5%/0.2% vs 0.9%/0.1%, NEK1 1.8%/0.4% vs 1.9%/0.8%. This

Prospects for the NPP Krsko Radioactive Waste Management

International Nuclear Information System (INIS)

Knapp, A.; Levanat, I.; Saponja-Milutinovic, D.

2016-01-01

Croatia adopted Strategy of radioactive waste, used sources and spent fuel management in 2014, and its Law on radiological and nuclear safety was accordingly modified in 2015. The Strategy foresees (though with some flexibility) and the Law declares decidedly that Croatia will establish a Center for radioactive waste management, in which all necessary facilities for storage and subsequent disposal of the Croatian share of the NPP Krsko radioactive waste and spent fuel will be developed. However, Slovenia and Croatia have recently agreed that a long-term dry storage for spent fuel will be established on the NPP premises by the year 2019. Therefore, only the issues of low and intermediate level waste (LILW) are addressed here. In Slovenia, the LILW repository site Vrbina in Krsko municipality was officially confirmed in 2009. Based on the 2013 investment program for a silo-type disposal facility, preparation of the repository project documentation was contracted with a national engineering company in 2014. Slovenian repository concept has been developed in two variants: one for the Slovenian LILW only, and the other intended to accept the Croatian share of LILW from the NPP as well. In the summer of 2015 Slovenia for the first time made an official offer to Croatia to use Vrbina repository for that purpose. However, the Croatian Strategy also does not preclude the option of management of all LILW from the NPP in Croatia. Therefore, present plan of activities for the third revision of the NPP radioactive waste and spent fuel management program outlines hypothetically symmetrical LILW management options: all in Slovenia, or all in Croatia, or one half in each country. So, what shall it be? This paper discusses the prospects for each of the three above mentioned options. The major problem of the Slovenian disposal plan is its high cost, mostly due to high compensations to the local community, which will be hard to finance without Croatian participation. The simplest

Determination of source term for Krsko NPP extended fuel cycle

International Nuclear Information System (INIS)

Nemec, T.; Persic, A.; Zagar, T.; Zefran, B.

2004-01-01

The activity and composition of the potential radioactive releases (source term) is important in the decision making about off-site emergency measures in case of a release into environment. Power uprate of Krsko NPP during modernization in 2000 as well as changing of the fuel type and the core design have influenced the source term value. In 2003 a project of 'Jozef Stefan' Institute and Slovenian nuclear safety administration determined a plantspecific source term for new conditions of fuel type and burnup for extended fuel cycle. Calculations of activity and isotopic composition of the core have been performed with ORIGEN-ARP program. Results showed that the core activity for extended 15 months fuel cycle is slightly lower than for the 12 months cycles, mainly due to larger share of fresh fuel. (author)

Trends of degradation in steam generator tubes of Krsko NPP before the last planned inspection

International Nuclear Information System (INIS)

Cizelj, L.; Dvorsek, T.; Androjna, F.

1998-01-01

Full-length inspection of all active tubes in both Krsko steam generators resulted in a huge amount of inspection records. A computerized database was developed by Reactor Engineering division to accelerate the management of about 200.000 records. The database was designed to support the development and decision related to the plugging criteria for damaged tubes and is utilized to gain as much experience concerning the degradation of SG tube as possible. In this paper, two prevailing group of data are statistically analyzed: the axial cracks in expansion transitions at the top of tube sheet (TTS) and Outside Diameter Stress Corrosion Cracking at tube support plates (TSP). Especially ODSCC caused a vast majority of repaired tubes (e.g., plugs and sleeves). The influence of plant startups involving oxidizing transient on the repair rates of tubes affected by ODSCC is analyzed in some detail. The results are promising and show excellent correlation in SG 2 and reasonable fit in SG 1. Predictions of maximum expected number of tubes repaired due to ODSCC at the last planned inspection is given as 67 in SG 1 and 400 in SG 2. (author)

Integrated use of Primavera and ORAM codes in outage 1999 at NPP Krsko

International Nuclear Information System (INIS)

Krajnc, J.; Skaler, F.; Basic, I.; Kocnar, R.

1999-01-01

The paper deals with the following postulated main goals of outage scheduling with Primavera tool at Krsko NPP: planning and controlling of resources (people, equipment, locations, sources), controlling the safety aspects of an outage and assuring defense-in-depth philosophy (through integrated safety assessment by ORAM code), diversity use of the plan during preparations period and outage progress (MCB, work leaders, management, planning Dept., subcontractors, support, etc.), allowing for optimization of outage duration. A snapshot in Primavera of what actually happened in outage 1999, lessons learned and a new work template is the scope of the next year outage.(author)

Mis saab eesti gümnaasiumist? / Igor Garšnek, Linnar Priimägi, Tiiu Purdelo ; vestluse pani kirja Raivo Juurak

Index Scriptorium Estoniae

Garšnek, Igor, 1958-

2008-01-01

Riigikirjandi drillimise asemel on vaja hakata gümnaasiumis süvendatult õppima valikaineid, leiavad TLÜ õppejõud Linnar Priimägi, Eesti Kunstiakadeemia õppejõud Igor Garšnek ja SA Õiguskolledži asutaja Tiiu Purdelo

Impact of the measurement data on the CORD-2 nuclear design calculations of the NPP Krsko

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

2004-01-01

The CORD-2 package was developed at Jozef Stefan Institute and has been validated for the nuclear design calculations of PWR cores. It has been used for the independent verification of the NPP Krsko nuclear design for the last 6 cycles of operation. The accuracy of the package is very good fulfilling all criteria usually imposed on the design prediction of the reactor nuclear parameters. To obtain as robust package as possible and to eliminate potential systematic errors of the package, it was decided to rely on measured core power distributions. In core power measurements, which are performed each month of reactor operation, are used to obtain fuel assemblies burnup histories. Consequently, burnup distributions obtained from the power measurements of all previous cycles are taken as a starting point at the beginning of the considered cycle. Since a lot of experience has been gained with the package, it was decided to evaluate the impact of measurement data on the accuracy of the calculations. Burnup calculations of all 19 cycles of the NPP Krsko are repeated, building simultaneously the calculated library of burnup histories for all fuel assemblies. The basic reactor parameters such as HZP critical boron concentration, isothermal temperature coefficient, control rod worth and cycle length are compared to the results obtained with CORD-2 standard sequence of calculation and direct measurements.(author)

Decommissioning and Waste Disposal Programme of NPP Krsko - How to Proceed in the Future

International Nuclear Information System (INIS)

Mele, I.; Zeleznik, N.; Levanat, I.; Lokner, V.

2006-01-01

By the agreement between Slovenia and Croatia on the ownership and exploitation of the NPP Krsko, which is effective since March 2003, the decommissioning and the disposal of spent fuel and low and intermediate level waste from NPP Krsko is the responsibility of both countries. In article 10 the agreement requires that within a year after putting it into force both parties jointly prepare a decommissioning and waste disposal programme with more detailed elaboration of these issues. According to these requirements such a programme was prepared by the waste management organisations from both countries - APO from Croatia and ARAO from Slovenia - and in March 2004 submitted to the Intergovernmental Commission for adoption. Later in 2004 the document was accepted also by both Governments and in Croatia also by the Parliament. By the agreement it is also anticipated that the decommissioning and waste disposal programmes be revised at least every 5 years. Such an approach is quite common and practiced in many countries, and some countries prepare revisions even more frequently. The purpose of these new revisions is two folded: on one hand to improve the technical solutions for the decommissioning as well as for waste disposal by including new or better known data and new technological developments and experience, and on the other hand to update the cost calculation of these future nuclear liabilities. Having in mind that these cost estimations are made for the rather distant future it is extremely important that regular updating and adjustment of estimates be performed in order to meet the future needs. Although the Decommissioning and Waste Disposal Programme has just recently passed the adoption procedure and its implementation has not yet been fully achieved, the time of the next revision is approaching fast. To make good progress in the next revision serious preparations including some strategic decisions should start immediately. The programme from 2004 was prepared

RELAP5/MOD 3.3 analysis of Reactor Coolant Pump Trip event at NPP Krsko

International Nuclear Information System (INIS)

Bencik, V.; Debrecin, N.; Foretic, D.

2003-01-01

In the paper the results of the RELAP5/MOD 3.3 analysis of the Reactor Coolant Pump (RCP) Trip event at NPP Krsko are presented. The event was initiated by an operator action aimed to prevent the RCP 2 bearing damage. The action consisted of a power reduction, that lasted for 50 minutes, followed by a reactor and a subsequent RCP 2 trip when the reactor power was reduced to 28 %. Two minutes after reactor trip, the Main Steam Isolation Valves (MSIV) were isolated and the steam dump flow was closed. On the secondary side the Steam Generator (SG) pressure rose until SG 1 Safety Valve (SV) 1 opened. The realistic RELAP5/MOD 3.3 analysis has been performed in order to model the particular plant behavior caused by operator actions. The comparison of the RELAP5/MOD 3.3 results with the measurement for the power reduction transient has shown small differences for the major parameters (nuclear power, average temperature, secondary pressure). The main trends and physical phenomena following the RCP Trip event were well reproduced in the analysis. The parameters that have the major influence on transient results have been identified. In the paper the influence of SG 1 relief and SV valves on transient results was investigated more closely. (author)

Nuclear safety activities in SR Slovenia in 1985

International Nuclear Information System (INIS)

1986-09-01

Currently Yugoslavia has one 632 MWe nuclear power plant of PWR design, located at Krsko in the Socialist Republic of Slovenia. NPP Krsko, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in SR Slovenia are mostly related to upgrading the safety of our NPP Krsko and to develop capabilities to be used for the future units. This report presents safety related organizations in SR Slovenia and their activities performed in 1985. (author)

Nuclear safety activities in SR Slovenia in 1985

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-09-15

Currently Yugoslavia has one 632 MWe nuclear power plant of PWR design, located at Krsko in the Socialist Republic of Slovenia. NPP Krsko, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in SR Slovenia are mostly related to upgrading the safety of our NPP Krsko and to develop capabilities to be used for the future units. This report presents safety related organizations in SR Slovenia and their activities performed in 1985. (author)

Some aspects of configuration management at Nuclear Power Plant Krsko

International Nuclear Information System (INIS)

Heruc, Z.; Podhraski, M.

2000-01-01

Configuration Management (CM) objectives at Neck are to ensure consistency between Design Requirements, Physical Plant Configuration and Configuration Information. Software applications, supporting Design Change, Work Control and Document Control Processes, are integrated in one module-oriented Management Information System (MIS). From configuration management perspective, Master Equipment Component List (MECL) database is the central MIS module. Through a combination of a centralized database and process migrated activities (modifications, plant operation, maintenance, document control etc.), it is encored that the CM principles and requirements (accurate, current design dana matching plant's physical configuration while complying to applicable requirements), are followed and fulfilled. (author)

Some aspects of digital I and C and digital human-system interface upgrades in nuclear power plants

International Nuclear Information System (INIS)

Mandic, D.

2005-01-01

Digital I and C technology introduces some new terms and new processes like software life cycle, process computer configuration control, digital human-system interface (HSI), software V and V (Verification and Validation), software common mode failure potential, software documentation, etc. Based on the experience from NEK, and other NPPs and published reports from other organizations, this paper sheds light on challenging tasks related to some aspects of the digital I and C upgrades and especially the NPP MCR/MCB HSI (Nuclear Power Plant Main Control Room / Main Control Board Human-System Interface) upgrade. The Ref. [1], EPRI Report TR-1008122 was used as a guidance to analyze original NEK MCR/MCB HSI design (1970s), to describe migration from the original MCR/MCB HSI design to the 2005 AS-BUILT status and to propose the authors vision for the key planning aspects for I and C upgrades and MCR modernization. This paper submits the justified proposal for the endpoint vision and the migration path applicable to NEK MCR/MCB HSI modernization, as well as some of the possible risks and lessons learned. (author)

Vulnerability of the nuclear power plant in war conditions

International Nuclear Information System (INIS)

Stritar, A.; Mavko, B.

1992-01-01

In the summer 1991 the Nuclear Power Plant Krsko in Slovenia found itself in the area of military operations. This way probably the first commercial nuclear power plant, to which it was threatened with the air jet attack. A number of never before asked questions had to be answered by the operating staff and supporting organizations. In this paper some aspects of the nuclear power plant safety in war condition are described: the selection of the best plant operating state before the attack and the determination of plant system vulnerability. It was concluded, that the best operating mode, into which the plant should be brought before the attack, is the cold shutdown mode. The problem of Nuclear Power Plant safety in war conditions should be addressed in more detail in the future. (author) [sl

Dose trend analysis of the PWR nuclear power plants

International Nuclear Information System (INIS)

Cernilogar Radez, M.; Janzekovic, H.; Krizman, M.

2002-01-01

The analyses of occupational dose trends in Krsko NPP in the period from 1995 to 2001 are given in comparison to the worldwide data. The Central Dose Register of Workers in Nuclear Installations at the Slovenian Nuclear Safety Administration enables the comprehensive dose trend analysis of the occupational doses in Krsko NPP. The time dose trend of the collective annual effective dose at the Krsko NPP shows somehow different trend than the trends of the ISOE data [1]. The performance indicators describing dose data distributions related to the radiation protection standards [2, 3] are discussed.(author)

Corrective action program at the Krsko NPP. Trending and analysis of minor events

International Nuclear Information System (INIS)

Bach, B.; Kavsek, D.

2007-01-01

understand the factors that might be responsible for such trend and to take corrective actions prior to the escalation to a significant event. Reviewed and analyzed data based on codes trending identified common problems, potential trends and common contributors, promote a good trending program. For the effective trending program, positive adverse trends identification and corrective actions that are addressed the weaknesses that have been identified, should be specified and implemented through the corrective action program. For that purpose the appropriate coding system incorporated into Corrective Action and Operating Experience Program is established at Krsko NPP. Minor events and near misses are collected and analyzed in order to aggregate detected minor problems. The different groups of codes developed include codes for direct causes and casual factors, processes and organizations, consequences, level of significance etc. For easier trending and further analysis a different code combinations were utilized in a form of graphs. For example: organisation vs. causal factors (allows particular department to trend human performance in their own organisation), direct cause vs. time (allows trending of equipment degradation), processes vs. organisation (allows trending 501.2 of processes degradation in particular organisation) any code in question vs. time (for trend confirmation) etc. The purpose of this article is to present the coding system established at the Krsko Nuclear Power Plant and variety of ways for trending by using the system. The article deals with the codes established, organization of code system, trend codes combinations and benefit for early recognizing adverse trends of lo-level events. (author)

NPP Krsko: LILW Repository or Long Term Storage

International Nuclear Information System (INIS)

Lokner, V.; Subasic, D.; Levanat, I.

2008-01-01

Construction of the facilities for LILW and SF management, as planned in Decommissioning and LILW and SF management program for NPP Krsko, would be a rather expensive and challenging project for such a small nuclear program. In order to accommodate waste arising from a single nuclear power plant, one LILW repository should be constructed before the end of the NPP operation, then one SF dry storage, and finally one geological repository. This requires relatively urgent identification within Slovenian/Croatian territory of three locations that meet the criteria for establishment of such facilities and are acceptable to the local communities. There are very few such potential locations. The siting process for the first of the three facilities is well under way in Slovenia, because the country wants to have its LILW repository in operation by the year 2013. In order to facilitate public acceptance, Slovenian government has introduced financial incentives to local communities for the repository construction and operation. These 'compensations for limited land use' may significantly increase the overall costs of disposal if the repository is in operation for a long period. In the recent years, however, a possibility of long term storage (LTS) is gaining an increased attention in the waste management community, and has already been introduced e.g. in the Netherlands. It is a particularly viable option for limited waste quantities. Disposal remains the final solution, but present technologies have made possible a relatively inexpensive storage up to about hundred years, which can accommodate LILW, HLW and SF from nuclear programs as well as research reactor waste and NORM. Such storage would be a safe and simple temporary solution, encompassing all immediate and near future waste management needs. In addition, it would increase flexibility and reduce financing requirements for the final waste disposal: providing additional time for reduction of radiation emission and heat

Transport of replaced steam generators from Port of Koper to Krsko (Slovenia)

International Nuclear Information System (INIS)

Kovacic, S.

2000-01-01

All activities regarding the transport preparation as well as preparation of the route between the Port of Koper and Krsko Site were completed within the period of 12 month. Transport configuration had been designed as a self supporting structure where two 12 axes trailers presented rolling cars. Total mass of aforesaid configuration was about 666 tons, where pulling and pushing tractors were not included. Major observations were granted to concrete structures that would be crossed during the transport. It is our pleasure to conclude, that respected design directions relevant for concrete structures (SODOC 1.0) enable rather quality bases regarding load capacity and taking over extremely heavy loads such as transport configuration itself. In manner to achieve a required safety factor and protection against permanent deformations on structures, many static analyses had been made by design engineers. (author)

A Genome-wide CRISPR (Clustered Regularly Interspaced Short Palindromic Repeats) Screen Identifies NEK7 as an Essential Component of NLRP3 Inflammasome Activation.

Science.gov (United States)

Schmid-Burgk, Jonathan L; Chauhan, Dhruv; Schmidt, Tobias; Ebert, Thomas S; Reinhardt, Julia; Endl, Elmar; Hornung, Veit

2016-01-01

Inflammasomes are high molecular weight protein complexes that assemble in the cytosol upon pathogen encounter. This results in caspase-1-dependent pro-inflammatory cytokine maturation, as well as a special type of cell death, known as pyroptosis. The Nlrp3 inflammasome plays a pivotal role in pathogen defense, but at the same time, its activity has also been implicated in many common sterile inflammatory conditions. To this effect, several studies have identified Nlrp3 inflammasome engagement in a number of common human diseases such as atherosclerosis, type 2 diabetes, Alzheimer disease, or gout. Although it has been shown that known Nlrp3 stimuli converge on potassium ion efflux upstream of Nlrp3 activation, the exact molecular mechanism of Nlrp3 activation remains elusive. Here, we describe a genome-wide CRISPR/Cas9 screen in immortalized mouse macrophages aiming at the unbiased identification of gene products involved in Nlrp3 inflammasome activation. We employed a FACS-based screen for Nlrp3-dependent cell death, using the ionophoric compound nigericin as a potassium efflux-inducing stimulus. Using a genome-wide guide RNA (gRNA) library, we found that targeting Nek7 rescued macrophages from nigericin-induced lethality. Subsequent studies revealed that murine macrophages deficient in Nek7 displayed a largely blunted Nlrp3 inflammasome response, whereas Aim2-mediated inflammasome activation proved to be fully intact. Although the mechanism of Nek7 functioning upstream of Nlrp3 yet remains elusive, these studies provide a first genetic handle of a component that specifically functions upstream of Nlrp3. © 2016 by The American Society for Biochemistry and Molecular Biology, Inc.

Report on nuclear energy in SR Slovenia

International Nuclear Information System (INIS)

1987-01-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1987.

Nuclear safety activities in the SR of Slovenia in 1986

Energy Technology Data Exchange (ETDEWEB)

Susnik, J [Inst. Jozef Stefan, Ljubljana (Slovenia)

1987-06-15

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1986. (author)

Report on nuclear energy in SR Slovenia; Porocilo o uporabi jedrske energije v SR Sloveniji

Energy Technology Data Exchange (ETDEWEB)

NONE

1987-07-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1987.

Nuclear safety activities in the SR of Slovenia in 1986

International Nuclear Information System (INIS)

Susnik, J.

1987-06-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1986. (author)

Report on nuclear safety on the operation of nuclear facilities in 1989

International Nuclear Information System (INIS)

Gregoric, M.; Levstek, M. F.; Horvat, D.; Kocuvan, M.; Cresnar, N.

1990-01-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1989.

Report on nuclear safety on the operation of nuclear facilities in 1990

International Nuclear Information System (INIS)

Gregoric, M.; Grlicarev, I.; Horvat, D.; Levstek, M.F.; Lukacs, E.; Kocuvan, M.; Skraban, A.

1991-06-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1990.

Report on nuclear safety on the operation of nuclear facilities in 1989; Porocilo o jedrski varnosti pri obratovanju jedrskih objektov v letu 1989

Energy Technology Data Exchange (ETDEWEB)

Gregoric, M; Levstek, M F; Horvat, D; Kocuvan, M; Cresnar, N [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

1990-07-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1989.

Finanční analýza firmy JELÍNEK - výroba nábytku s. r. o.

OpenAIRE

Kovařík, Matěj

2016-01-01

Thesis evaluates the financial situation of furniture company JELÍNEK - výroba nábytku s. r. o. during the reference period 2010-2014. The first part discusses the theoretical bases of financial analysis. In the second part is elaborated the financial analysis. Horizontal and vertical analysis of financial statements and analysis of differential and financial ratios were excuted. Fundamental characteristics of time series are applied on selected fundamental characteristics. The economic situa...

Analýza nestrukturovaných dat z bankovních stránek na sociální síti Facebook

Directory of Open Access Journals (Sweden)

Lucie Šperková

2014-12-01

Full Text Available Sociální sítě jako novodobý kanál pro sdílení online Word of Mouth představuje pro bankovní společnosti příležitost, jak analyzovat komunikaci a názory svých zákazníků, které zde veřejně sdílejí. Článek ukazuje proces a výsledky pokročilé kontextové analýzy těchto nestrukturovaných dat vybraných veřejných bankovních stránek na sociální síti Facebook. Analýza zákaznických názorů, problémů a přání může hrát významnou roli pro pozici těchto společností na trhu a jejich orientaci na zákazníky. Využity byly metody shlukování a sentiment analýz, výsledky odrážejí stav chování zákazníků a bank na této síti. Článek zdůrazňuje důležitost problematiky Word of Mouth a jeho analýz informačními technologiemi. Zároveň diskutuje, jak analýza kontextu může přenést marketing na další úroveň identifikace zákazníkova chování a jeho vztahu ke společnosti.

Retrofitting a spent fuel pool spray system for alternative cooling as a strategy for beyond design basis events

Energy Technology Data Exchange (ETDEWEB)

Hartmann, Christoph; Vujic, Zoran [Westinghouse Electric Germany GmbH, Mannheim (Germany)

2017-06-15

Due to requirements for nuclear power plants to withstand beyond design basis accidents, including events such as happened in 2011 in the Fukushima Daiichi Nuclear Power Plant in Japan, alternative cooling of spent fuel is needed. Alternative spent fuel cooling can be provided by a retrofitted spent fuel pool spray system based on the AP1000 plant design. As part of Krsko Nuclear Power Plant's Safety Upgrade Program, Krsko Nuclear Power Plant decided on, and Westinghouse successfully designed a retrofit of the AP1000 {sup registered} plant spent fuel pool spray system to provide alternative spent fuel cooling.

Application of computer code ALMOD 3W2 in nonsymmetric transient analysis in the primary loop of nuclear power plant; Primjena programa ALMOD 3W2 u analizi nesimetricnih prijelaznih pojava u primarnom krugu nuklearne elektrane

Energy Technology Data Exchange (ETDEWEB)

Bencik, V [Elektrotehnicki institut ' rade Koncar' , Zagreb (Yugoslavia); Debrecin, N; Feretic, D; Kozaric, M [Elektrotehnicki fakultet, Zagreb (Yugoslavia)

1988-07-01

In this paper the method to calculate the nonsymetric transients in the nuclear power plant is presented. ALMOD 3W2 computer code with steam generator model GEVAP is applied to analyze partial loss of forced reactor coolant flow for NPP Krsko. (author)

Ideal scaling of BETHSY 9.1.B test results to NPP

International Nuclear Information System (INIS)

Petelin, S.; Guntel, I.

1995-01-01

The transient scenario standard problem 27 (ISP-27) was implemented in the RELAP5 analysis of small break loss of coolant accident for Krsko nuclear power plant (Krsko NPP). The objective was to evaluate the effectiveness of ISP-27 proposed accident management procedure for real NPP and to compare the physical phenomena known from experimental background with the phenomena predicted by RELAP5 simulation of real plant transient. The analyses showed that, if relevant break, power scaling criteria, primary and secondary pressure are fulfilled the RELAP5 model of Krsko NPP cannot completely ensure the simulation of typical thermal-hydraulic phenomena observed in BETHSY facility during ISP-27. Much better satisfaction is observed on ideal scaled up model. (author)

Role of Nuclear Energy in the Energy Strategy of Slovenia

International Nuclear Information System (INIS)

Novak, I.

1998-01-01

Krsko nuclear power plant is jointly owned by Croatia and Slovenia and is one of the pillars of Slovenian power system. The utility supplies more than 20% of Slovenian electricity demand. In 16 years of its operation, Krsko NPP showed very high standards of safety and operational availability. It operates under auspices of Slovenian Nuclear Safety Authority and fully complies to national legal frame and international standards, and requirements. In 2000 the nuclear power plant will undergo a major refurbishment, replacement of steam generators and additionally the utility will be equipped with a new full scope simulator. Slovenia set up a fund to collect money for decommissioning of the Krsko NPP. (author)

Procedure for following external nuclear power plant operating experience

International Nuclear Information System (INIS)

Kostadinov, V.

2003-01-01

Slovenian Nuclear Safety Administration (SNSA) has developed computer database and the procedure for following-up and investigating external nuclear operating experience and administrative requirements. The SNSA's primary goal is to investigate safety significant events in due time, to analyze them from the regulatory point of view and to ensure that meaningful lessons be learned and used for improvement of the safe operation of Slovenian Nuclear Power Plant Krsko. Moreover, we intend to make uniform format and method for reporting broader spectrum of events analyzed including low level event reporting. (author)

Some aspects of nuclear power plant safety under war conditions

International Nuclear Information System (INIS)

Stritar, A.; Mavko, B.; Susnik, J.; Sarler, B.

1993-01-01

In the summer of 1991, the Krsko nuclear power plant in Slovenia found itself in an area of military operations. This was probably the first commercial nuclear power plant to have been threatened by an attack by fighter jets. A number of never-before-asked questions had to be answered by the operating staff and supporting organizations. Some aspects of nuclear power plant safety under war conditions are described, such as the selection of the best plant operating state before the attack and the determination of plant system vulnerability and dose releases from the potentially damaged spent fuel in the spent-fuel pit. The best operating mode to which the plant should be brought before the attack is cold shutdown, and radiological consequences to the environment after the spent fuel is damaged and the water in the pit is lost are not very high. The problem of nuclear power plant safety under war conditions should be addressed in more detail in the future

Influence of the CVCS Modelling on Results of the Loss of Offsite Power (LOOP) Safety Analysis for NPP Krsko

International Nuclear Information System (INIS)

Bencik, V.; Bajs, T.; Debrecin, N.

2006-01-01

A Loss of Offsite Power (LOOP) transient scenario is based on a complete loss of non-emergency AC power that results in the loss of all power to the plant auxiliaries, i.e., the Reactor Coolant Pumps (RCPs), condensate pumps, etc. An actual LOOP event would cause a loss of all feedwater, a loss of forced Reactor Coolant System (RCS) flow and a reactor trip within less than 2 seconds as a result of either loss of power to the rod cluster assembly gripper coils or any RCS flow trips. For safety analysis purposes the LOOP event is conservatively modelled as a Loss of Normal Feedwater (LONF) transient with a subsequent loss of offsite power as a result of a reactor trip. The reactor trip followed by RCP trip are delayed until a low-low Steam Generator (SG) level signal is reached. This is a more conservative scenario than the LOOP event because the least amount of SG secondary side water mass available for heat removal and the increased amount of the stored energy in the primary circuit at the time of the loss of RCS flow result. The standard LOOP safety analysis is aimed to demonstrate the natural circulation capability of the RCS to remove residual and decay heat from the core aided by Auxiliary Feedwater in the secondary system. In addition to this goal the presented work is aimed to resolve the potential safety issue resulting from the influence of the Chemical and Volume Control System (CVCS) operation during LOOP event for NPP Krsko. The potential safety concern for the LOOP analysis is that the loss of instrument air system may occur thus leading to the CVCS charging and letdown flow imbalance. A net RCS inventory addition may result with water solid pressurizer condition. Water discharge through the pressurizer relief and safety valves could lead to overpressurization of the Pressurizer Relief Tank (PRT) and rupture of the PRT rupture disks. Additional concern is that pressurizer relief and safety valves may fail to properly reseat when exposed to water relief

Public awareness - calendar with information about emergency preparedness

International Nuclear Information System (INIS)

Podhraski Benkovic, S.; Novosel, N.

2009-01-01

State Office for Nuclear Safety in co-operation with the Ministry of Science, Education and Sport, Nuclear Power Plant Krsko (in Slovenia) and Agency for Education during the years 2002 till now realized the project of preparing the calendar for families living in the circle 25 km from the Nuclear Power Plant Krsko (Slovenia) and in the circle of 100 km from Nuclear Power Plant Paks (Hungary). The calendars are containing primary school pupils' paintings about energy, environment, nuclear technology and additional information about preparedness in the Republic of Croatia in the case of nuclear accident and recommendation for acting. Collecting of paintings is carried out each year between pupils from second to eight grades in the schools near Nuclear Power Plant Krsko and Nuclear Power Plant Paks. Expert commission chose twelve best paintings for the following year. This kind of project is only one way of public relations and awareness which helps in expanding knowledge about successful living close to nuclear and other energy technologies. In this poster presentation more about this project will be presented.(author)

Public awareness - calendar with information about emergency preparedness

Energy Technology Data Exchange (ETDEWEB)

Podhraski Benkovic, S; Novosel, N [State Office for Nuclear Safety, Zagreb (Croatia)

2009-07-01

State Office for Nuclear Safety in co-operation with the Ministry of Science, Education and Sport, Nuclear Power Plant Krsko (in Slovenia) and Agency for Education during the years 2002 till now realized the project of preparing the calendar for families living in the circle 25 km from the Nuclear Power Plant Krsko (Slovenia) and in the circle of 100 km from Nuclear Power Plant Paks (Hungary). The calendars are containing primary school pupils' paintings about energy, environment, nuclear technology and additional information about preparedness in the Republic of Croatia in the case of nuclear accident and recommendation for acting. Collecting of paintings is carried out each year between pupils from second to eight grades in the schools near Nuclear Power Plant Krsko and Nuclear Power Plant Paks. Expert commission chose twelve best paintings for the following year. This kind of project is only one way of public relations and awareness which helps in expanding knowledge about successful living close to nuclear and other energy technologies. In this poster presentation more about this project will be presented.(author)

Public Awareness - Calendar with Information about Emergency Preparedness

International Nuclear Information System (INIS)

Podhraski Benkovic, S.; Novosel, N.

2008-01-01

State Office for Nuclear Safety in co-operation with the Ministry of Science, Education and Sport, Nuclear Power Plant Krsko (in Slovenia) and Agency for Education during the years 2002 till now realized the project of preparing the calendar for families living in the circle 25 km from the Nuclear Power Plant Krsko (Slovenia) and in the circle of 100 km from Nuclear Power Plant Paks (Hungary). The calendars are containing primary school pupils' paintings about energy, environment, nuclear technology and additional information about preparedness in the Republic of Croatia in the case of nuclear accident and recommendation for acting. Collecting of paintings is carried out each year between pupils from second to eight grades in the schools near Nuclear Power Plant Krsko and Nuclear Power Plant Paks. Expert commission chose twelve best paintings for the following year. This kind of project is only one way of public relations and awareness which helps in expanding knowledge about successful living close to nuclear and other energy technologies. In this poster presentation more about this project will be presented.(author)

Social responsible communication of nuclear power plant with external stakeholders

Energy Technology Data Exchange (ETDEWEB)

Simoncic, Milan [Nuclear Power Plant Krsko (Slovenia); Zurga, Gordana [Faculty of Organisation Studies in Novo Mesto (Slovenia)

2016-11-15

Implications that nuclear technology brings to common physical and social environment, are on daily lists of questions that stakeholders address to owners and operators of nuclear power plants. In this respect, stakeholders expect and demand narrow and explicit answers to concrete questions set. We claim that the acceptability of the NPP in the society can be achieved and maintained also through active communication and trust building between NPP and its stakeholders. A research in this respect was conducted on case of the Krsko NPP, Slovenia. Some institutional and international implications are presented, as well as possible areas for further investigation and research.

NPA applications development in the nuclear safety authority framework

International Nuclear Information System (INIS)

Maselj, A.; Vojnovic, D.; Gregonc, M.

1999-01-01

Due to the present tasks of the SNSA (Slovenian Nuclear Safety Administration) there was a need to gain a tool for analysing the transients of the Krsko Nuclear Power Plant at the SNSA. Combining the RELAP5 code with graphical interface NPA (Nuclear Plant Analyzer), the SNSA management saw an opportunity to have a powerful instrument for analyses and assessments on a user friendly basis and without high costs. The Krsko NPP Analyzer is a joint project of the SNSA and the operator, the Krsko NPP. The RELAP5/Mod2.5 input deck was constructed by the Krsko NPP's experts and their subcontractors. In 1996 the work started with translation of input model from RELAP5/Mod2.5 version to Mod3.2. This was done by Tractebel which combined NPA masks with translated input deck and constructed new dynamic function and interactive commands between graphical MMI (Man Machine Interface) and simulation code. Since Tractebel performed similar activities for the Belgian plants, their experience was used through a transfer of knowledge to the SNSA. After this phase of the project, a user of the NPP Analyzer can run accidents as SBLOCA, Main Steam Line Break, Feed Water Break, SGTR, and many other transients activating and combining interactive commands, starting from a full power operation. This project has not been finished yet. Improvements of the input deck should be done. The Critical Safety Function window will be created. The analyzer will be a helpful tool during the training program for Accident Assessment Group, which will give to the experts basic knowledge of plant operation, its systems, and physical phenomena during a steady state and transients or accidents. Also a new dimension is added to the existing safety evaluations at the SNSA to confirm the requested level of nuclear safety at the Krsko NPP. (author)

Analysis of Public Opinion Survey ''Nuclear Energy - the Present and the Future'' (2000-2012)

International Nuclear Information System (INIS)

Jakic, Irena; Filipin, Renato

2014-01-01

Technical Museum Zagreb, in co-operation with Hrvatska elektroprivreda, has been organizing high-school students' visits to the nuclear power plant Krsko since 1989. From schools that have visited the nuclear power plant so far, Zagreb high schools and technical schools are the most represented ones. They filled in the copies of questionnaire after watching film about nuclear energy and before visiting nuclear power plant Krsko. The copies of the public opinion survey (questionnaire) have been filled since 2000 and results of analysis of data until 2012 are in this paper. Questions were the same and that makes possible comparison of the results. (authors)

Analysis of steam generator behaviour in nuclear power plant with computer program RELAP5; Analiza delovanja uparjalnika jedrske elektrarne s programom RELAP5

Energy Technology Data Exchange (ETDEWEB)

Zeljko, M; Gregoric, M; Peterlin, G [Institut ' Jozef Stefan' , Ljubljana (Yugoslavia)

1983-07-01

Analyses of nuclear power plant behaviour are made with large computer programs. We used RELAP5/MOD1/CYCLE001, which was developed in Idaho National Engineering laboratory. Input model was prepared to analyze transients in steam generator of NPP Krsko. We found out that this version had a lot of faults so we intend to implement a new cycle. First experience shows the whole complexity of such analysis from technical and economical viewpoints. (author)

Programme of Preparatory Activities on Launching First Nuclear Power Plant in Croatia

International Nuclear Information System (INIS)

Jakic, I.; Lebegner, J.; Perovic, N.

2010-01-01

New Croatian energy policy recognizes nuclear energy as solution for rising needs for energy and, thus, opens the possibility to construct first nuclear power plant in Croatia. Within this frame, the Croatian government is developing an implementation programme according to this policy and preparing basis for making decision about construction of nuclear power plant. Croatian parliament is responsible for this decision which is expected by the end of 2012. During this period, stake holders in this project (government, regulatory body and future operator of the plant) have to complete activities of preparatory phase of Croatian Nuclear Energy Programme (CRONEP) project according to methodology recommended by IAEA (International Atomic Energy Agency). This paper defines these activities and estimate the costs of first, preparatory phase based on previous experience of other countries which finished the phase successfully. Also, it describes the potential role of Croatian utility as stake holder due to its experience as co-owner of Nuclear power plant Krsko.(author).

RELAP5/MOD 3.2 Analysis of the Loss of RHR System Experiment Scaled to NPP Krsko

International Nuclear Information System (INIS)

Bencik, V.; Bajs, T.; Prah, M.

1998-01-01

In the paper the RELAP5/MOD 3.2 analysis of the loss of Residual Heat Removal (RHR) system during midloop operation experiment performed at the Rig of Safety Assessment (ROSA)-IV/Large Scale Test Facility (LSTF) together with the analysis of the same test scenario scaled to NPP Krsko are presented. The experiment consisted in a loss of the RHR system at cold shutdown conditions along with a 5% cold leg break in the loop without pressurizer. The Safety Injection (SI) system was disable in the calculation. The aims of the work were to study the physical phenomena encountered under low power and low system pressure conditions while the upper part of the Reactor Coolant System (RCS) is filled with noncondensable. The impact of the bypass flow between upper plenum and downcomer inlet on transient responses was investigated. The transient was simulated for 6000 s. (author)

The shift of the public opinion to the favour of nuclear energy in Slovenia

International Nuclear Information System (INIS)

Lengar, I.; Nemec, T.

2001-01-01

In late August and early September of 1999, nuclear energy topics occupied a central place in the Slovenian media because of the transport of two new steam generators to the Krsko nuclear power plant, and also due to the protest action of an Austrian Greenpeace group. Before these events, the public opinion in Slovenia was not in favour or nuclear energy and Greenpeace had a good reputation. In September it has lost much credibility because of their clumsy action of protest, and in just one month this caused a shift of public opinion in Slovenia towards support of Slovenia's only nuclear power plant. The Greenpeace protest action occurred during the transport of the two new steam generators to Krsko. By replacement of the old steam generators the operation of the Krsko NPP will be extended until 2023. The transport envoy travelled during the first half of September '99 across a considerable part of Slovene territory, passing by the capital of Ljubljana. (authors)

Public Opinion shifts to the favour of nuclear energy due to steam generator transport

International Nuclear Information System (INIS)

Lengar, I.; Nemec, T.

2000-01-01

In late August and early September of 1999, nuclear energy topics occupied a central place in the Slovenian media because of the transport of two new steam generators to the Krsko nuclear power plant, and also due to the protest action of an Austrian Green peace group. Before these events, the public opinion in Slovenia was not in favour or nuclear energy ;and Green peace had a good reputation. In September it has lost much credibility because of their clumsy :action of protest, and in just one month this caused a shift of public opinion in Slovenia towards support of Slovenian's only nuclear power plant. The Green peace protest action occurred during the transport of the two new steam generators to Krsko. By replacement of the old steam generators the operation of the Krsko NPP will be extended until 2023. The transport envoy travelled during the first half of September '99 across a considerable part of Slovene territory, passing by the capital of Ljubljana. (authors)

Thermohydraulic analysis of nuclear power plant accidents by computer codes

International Nuclear Information System (INIS)

Petelin, S.; Stritar, A.; Istenic, R.; Gregoric, M.; Jerele, A.; Mavko, B.

1982-01-01

RELAP4/MOD6, BRUCH-D-06, CONTEMPT-LT-28, RELAP5/MOD1 and COBRA-4-1 codes were successful y implemented at the CYBER 172 computer in Ljubljana. Input models of NPP Krsko for the first three codes were prepared. Because of the high computer cost only one analysis of double ended guillotine break of the cold leg of NPP Krsko by RELAP4 code has been done. BRUCH code is easier and cheaper for use. Several analysis have been done. Sensitivity study was performed with CONTEMPT-LT-28 for double ended pump suction break. These codes are intended to be used as a basis for independent safety analyses. (author)

Radiological monitoring of nuclear facilities

International Nuclear Information System (INIS)

Mihailovic, M.; Najzer, M.; Kobal, I.; Udovc, W.; Zovrtanik, D.

1977-01-01

We have continued to measure gross beta activity of the river Sava water samples near Krsko, and Sentjakob and water samples of springs and wells near NEK, as well as quantitative and qualitative gamma spectroscopic isotopic analysis of agricultural products and river Sava water samples. We have found that the average gross beta activity of river Sava water samples near Krsko is lower about fifteen percent that the average activity of the previous years, while it stayed the same in Sentjakob (discounting one result in august, which was 12,8 pCi/1). In quantitative isotopic analysis we had problems due to low resolution of the NaI(T1) crystal, so we were able to measure only K-40 with required accuracy. Improvement of equipment for gama spectrometry would be essential for continuation the quantitative isotopic analysis program. In the second part of the project we have processed four-year data from measurements of natural radioactivity of the environment. The conclusion was that the collected data give a good account of the following: a) fluctuations in natural beta activity of the river Sava, b) the conti-bution of soluble and insoluble natural or artificial radionuclides, c) gross α activity of the river Sava water samples, d) specific activity of the ash in the riVer water samples, e) aross beta activity of seston, sediments, bentos on various sampling locations, f) influence of the local sewage on the concentration of the various elements in the samples of water, and water organisms, g) level of natural gross beta radioactivity in water springs and wells, h) gross beta activity of agricultural products

Nuclear power plant safety under military threats

International Nuclear Information System (INIS)

Stritar, A.; Mavko, B.

1993-01-01

The Krsko nuclear power plant in Slovenia was probably the first in the world that found itself in the middle of a war region. A number of preventive measures performed during and immediately after the war in summer 1991 by the plant personnel as well as some of related activities of the Reactor Engineering Division of the 'Jozef Stefan' Institute are described. All efforts were aimed at the minimization of the possible public radiological consequences during a military attack. The critical safety functions in such conditions were checked. Concern was further devoted to maintenance of the core cooling in the core and to integrity of the spent fuel pit. The cold shutdown mode was found to be the most appropriate option. After selecting the cold shutdown mode as a most suitable operational state of the plant, further studies of the vulnerability were done. In addition to possible direct damage to structures, that would cause release of radioactivity, two important subjects were considered: AC and DC power supply and the ultimate heat sink. A quick analysis during the crisis has shown that the consequences of a military attack against the plant by jet fighters could be serious, but with the proper preventive measures and preparedness the environmental consequences could be minimized. (Z.S.) 1 fig., 1 ref

Minimum success criteria at SGTR combined with loss of secondary heat sink

International Nuclear Information System (INIS)

Parzer, I.; Petelin, S.

1993-01-01

A parametric analysis has been performed investigating minimum success criteria for the hypothetical Steam Generator Tube Rupture (SGTR) accident in a Pressurized Water Reactor (PWR) Nuclear Power Plant, combined with the total loss of secondary heat sink. The analyses have been performed by RELAP5/MOD2 and MOD3 computer codes using Krsko NPP input deck. The Krsko NPP is a 2-loop Westinghouse PWR, 640 MWe, located in Slovenia and operating from 1981. Two break sizes have been chosen for the SGTR event: 2 and 5 double-ended broken tubes have been assumed. Total loss of secondary heat sink has been assumed from the beginning of the calculation. The ways of cooling down the plant after the postulated accident have been investigated, including Bleed ampersand Feed through the primary system. The NPP Krsko Emergency Operating Procedures (EOP) have been verified for this case. Some suggestions have been made, how to improve FR-H.1 procedure (Loss of Secondary Heat Sink), to include some steps, which take into account also SGTR when it is combined with loss of secondary heat sink. Possible misinterpretations of E-0 procedure (Reactor Trip or Safety Injection) have been studied

Three steam generator replacement projects in 1995: Consortium Siemens Framatome is well prepared to contribute its experience to the SGR at the Krsko NPP

International Nuclear Information System (INIS)

Holz, R.; Clavier, G.

1996-01-01

Since the companies Siemens AG and Framatome S.A. joined their experience and efforts in the field of steam generators replacements and formed a consortium in 1991, the following projects were performed in 1995: Ringhals 3, Tihange 3 and Asco 2. Further projects will follow in 1996, i.e., Doel 4 and Asco 2. Currently, this European consortium is bidding for the contract to replace the steam generators at the Krsko NPP and hopes to be awarded in 1996. An overview of the way the Consortium Siemens and Framatome approaches SG replacement projects is given based on the projects performed in 1995. Various aspects of project planning, management, licensing, personnel qualification and techniques used on site will be discussed. (author)

Asynchronous Two-Level Checkpointing Scheme for Large-Scale Adjoints in the Spectral-Element Solver Nek5000

Energy Technology Data Exchange (ETDEWEB)

Schanen, Michel; Marin, Oana; Zhang, Hong; Anitescu, Mihai

2016-01-01

Adjoints are an important computational tool for large-scale sensitivity evaluation, uncertainty quantification, and derivative-based optimization. An essential component of their performance is the storage/recomputation balance in which efficient checkpointing methods play a key role. We introduce a novel asynchronous two-level adjoint checkpointing scheme for multistep numerical time discretizations targeted at large-scale numerical simulations. The checkpointing scheme combines bandwidth-limited disk checkpointing and binomial memory checkpointing. Based on assumptions about the target petascale systems, which we later demonstrate to be realistic on the IBM Blue Gene/Q system Mira, we create a model of the expected performance of our checkpointing approach and validate it using the highly scalable Navier-Stokes spectralelement solver Nek5000 on small to moderate subsystems of the Mira supercomputer. In turn, this allows us to predict optimal algorithmic choices when using all of Mira. We also demonstrate that two-level checkpointing is significantly superior to single-level checkpointing when adjoining a large number of time integration steps. To our knowledge, this is the first time two-level checkpointing had been designed, implemented, tuned, and demonstrated on fluid dynamics codes at large scale of 50k+ cores.

Compensations to Local Communities in the Krsko NPP Decommissioning Program

International Nuclear Information System (INIS)

Levanat, I.; Knapp, A.; Lokner, V.

2010-01-01

In Slovenia, direct financial compensations (for 'limited land use') to local communities hosting nuclear facilities were initially specified by a government Decree from 2003. In Croatia, a possibility of direct financial compensations had been indicated in the land use plan in conjunction with the prospective RW repository siting about a decade earlier, but the topic was subsequently abandoned together with the repository project. In 2004, the joint Slovenian-Croatian Decommissioning and LILW and SF management program for NPP Krsko from 2004 (the 1st revision of the joint Program) conservatively included the compensation amounts from the Slovenian Decree into the cost estimates of LILW and SF repositories, although their location was entirely unspecified ('in Slovenia or in Croatia'). Shortly before the 2nd revision of the joint Program started in the fall of 2008, the Slovenian government had amended its Decree, practically doubling the amounts of the repository compensations. Assuming that some (or possibly all) nuclear facilities and waste, dealt with in the Program, may be located in Slovenia, the revision has adopted a conservative approach to include all compensations to local communities that may be required by the Slovenian regulations into the Program costs. This paper discusses the Slovenian government Decree, its impact on the joint Program costs, and its implications on RW and SF management in the region. The Decree suffers from the lack of self-consistency, clarity, and consistency with the more general legal provisions on which it should have been based, but it may have an important supporting role in the process of RW and SF management facilities siting. The Decree introduced significant additional costs into the joint Program, which have grown from about one hundred million eur in the 1st revision to about half a billion in this revision (depending on the Program scenario). Besides, application of the Decree in the joint Program has set a precedent

Využití dodacích podmínek INCOTERMS v činnosti zasílatelské firmy v námořní přepravě

OpenAIRE

Staroba, Jaromír

2007-01-01

Práce je zaměřená na využívání dodacích podmínek INCOTERMS českými exportéry v rámci zasílatelské firmy. V teoretické části lze nalézt přehledný popis problematik námořní přepravy, kupní smlouvy, zasílatelství a INCOTERMS. Praktická část obsahuje výzkum využití INCOTERMS exportéry v rámci zasílatelské firmy Gebruder Weiss.

Nuclear Power Plants and Sustainable Development on a Liberalized Market

International Nuclear Information System (INIS)

Androcec, I.; Stanic, Z.; Tomsic, Z.

2002-01-01

Finding a way to generate electricity so as to satisfy the terms of sustainable development of the entire society is the only way which will secure safe energy future. If we talk about energy in the context of sustainable development, one of the most important element is environmental protection. Since CO 2 emissions stemming from electricity generation have predominant impact on climate change, one of the options for reducing emissions is the use of fuels without carbon, such as e.g. nuclear fuel. The future of nuclear power plants was considered in view of: nuclear fuel supply; potential impact of fuel cycle on environment, power plant operation, decommissioning and secondary products from electricity generation; and the entire nuclear power plant economy. Nuclear power plants were also examined in the context of the Kyoto Protocol stipulating reduction of greenhouse gases emissions. Nuclear power plants can not reduce CO 2 emissions in a short-term because they already operate with maximum output, but in a long-run they can play a significant role. This paper is aiming to analyse the role of nuclear power plants in long term environmental sustainability in electricity sector reform (liberalisation, deregulation, privatisation) in small or medium sized power supply systems. Nuclear power plants are associated with certain environmental aspects which will be taken into account. A comparison will be made through externalities with other energy resources, especially fossil fuels, which are prevailing energy resources, considering possible use of nuclear power plants in the countries with small and medium-size grids. It will be given an example of the role of NPP Krsko on air emissions reduction in Croatia. (author)

Severe accident analysis in a two-loop PWR nuclear power plant with the ASTEC code

International Nuclear Information System (INIS)

Sadek, Sinisa; Amizic, Milan; Grgic, Davor

2013-01-01

The ASTEC/V2.0 computer code was used to simulate a hypothetical severe accident sequence in the nuclear power plant Krsko, a 2-loop pressurized water reactor (PWR) plant. ASTEC is an integral code jointly developed by Institut de Radioprotection et de Surete Nucleaire (IRSN, France) and Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS, Germany) to assess nuclear power plant behaviour during a severe accident. The analysis was conducted in 2 steps. First, the steady state calculation was performed in order to confirm the applicability of the plant model and to obtain correct initial conditions for the accident analysis. The second step was the calculation of the station blackout accident with a leakage of the primary coolant through degraded reactor coolant pump seals, which was a small LOCA without makeup capability. Two scenarios were analyzed: one with and one without the auxiliary feedwater (AFW). The latter scenario, without the AFW, resulted in earlier core damage. In both cases, the accident ended with a core melt and a reactor pressure vessel failure with significant release of hydrogen. In addition, results of the ASTEC calculation were compared with results of the RELAP5/SCDAPSIM calculation for the same transient scenario. The results comparison showed a good agreement between predictions of those 2 codes. (orig.)

Excessive heat removal due to feedwater system malfunction

International Nuclear Information System (INIS)

Beader, D.; Peterlin, G.

1986-01-01

Excessive heat removal transient of the Krsko Nuclear Power Plant, caused by steam generators feedwater system malfunctions was simulated by RELAP5/MOD1 computer code. The results are increase of power and reactor scram caused by high-high steam generator level. (author)

Equipment Reliability Program in NPP Krsko

International Nuclear Information System (INIS)

Skaler, F.; Djetelic, N.

2006-01-01

Operation that is safe, reliable, effective and acceptable to public is the common message in a mission statement of commercial nuclear power plants (NPPs). To fulfill these goals, nuclear industry, among other areas, has to focus on: 1 Human Performance (HU) and 2 Equipment Reliability (EQ). The performance objective of HU is as follows: The behaviors of all personnel result in safe and reliable station operation. While unwanted human behaviors in operations mostly result directly in the event, the behavior flaws either in the area of maintenance or engineering usually cause decreased equipment reliability. Unsatisfied Human performance leads even the best designed power plants into significant operating events, which can be found as well-known examples in nuclear industry. Equipment reliability is today recognized as the key to success. While the human performance at most NPPs has been improving since the start of WANO / INPO / IAEA evaluations, the open energy market has forced the nuclear plants to reduce production costs and operate more reliably and effectively. The balance between these two (opposite) goals has made equipment reliability even more important for safe, reliable and efficient production. Insisting on on-line operation by ignoring some principles of safety could nowadays in a well-developed safety culture and human performance environment exceed the cost of electricity losses. In last decade the leading USA nuclear companies put a lot of effort to improve equipment reliability primarily based on INPO Equipment Reliability Program AP-913 at their NPP stations. The Equipment Reliability Program is the key program not only for safe and reliable operation, but also for the Life Cycle Management and Aging Management on the way to the nuclear power plant life extension. The purpose of Equipment Reliability process is to identify, organize, integrate and coordinate equipment reliability activities (preventive and predictive maintenance, maintenance

Revision 2 of the NPP Krsko Decommissioning Program Is Stalled

International Nuclear Information System (INIS)

Levanat, I.; Lokner, V.; Rapic, A.; Zeleznik, N.; Kralj, M.

2012-01-01

Revision 2 of the joint Slovenian-Croatian Program of NPP Krsko Decommissioning and SF andLILW Disposal was scheduled to be finished and formally approved by the end of 2009, in accordance with the bilateral Agreement on the NPP. Slightly behind the schedule, the Project team completed the entire document during spring of 2010, and in June 2010 drafted a proposal for a peer review of the Program by a dedicated IAEA expert mission. This procedure was agreed upon at the last session (May 2010) of the Intergovernmental Commission for implementation of the Agreement, when the Commission was acquainted with the five scenarios of the Revision 2 and with the estimates of their costs/financing. It was expected that the peer review would be performed soon, and that formal adoption of the Revision 2 would follow. Although in this process of approval some decisions remained to be made by the stakeholders, the Project team did select and recommend one scenario to be used for costing purposes, in order to ensure that most necessary corrections in Program financing would be timely adopted. However, the planned IAEA review was cancelled by the Advisory board, the body nominated by the Commission ''to supervise the activities and resolve the issues raised by the Project team''. By this cancellation, the process of Program revision was effectively stalled, because the Advisory board could not clearly define further course of action: differing views between the Slovenian and the Croatian part of the Advisory board appeared, in particular regarding the set of Program scenarios and regarding the appropriateness of the Revision 2 document for the IAEA review; nonetheless, the Advisory board sent to the Project team a compilation of requests to modify Revision 2 document. The Project team determined that some minor requests were easy to fulfill, but other modifications could only be carried out after changes in the boundary conditions (approved by the Commission), or changes in national

Overexpression of NIMA-related kinase 2 is associated with poor prognoses in malignant glioma.

Science.gov (United States)

Liu, Huajie; Liu, Bin; Hou, Xianzeng; Pang, Bo; Guo, Pengbo; Jiang, Wanli; Ding, Qian; Zhang, Rui; Xin, Tao; Guo, Hua; Xu, Shangchen; Pang, Qi

2017-05-01

Eleated expression of NIMA-related kinase 2 (NEK2) was frequently observed in a variety of malignant cancers, and it appears to be involved in the initiation, maintenance, progression, metastasis of cancer and is positively associated with poor prognosis. We sought to investigate NEK2 expression and its predictive roles in malignant gliomas, and study the correlation of NEK2 protein expression with proliferation, clinical parameters, overall survival and some other parameters. We investigate NEK2 protein expression in 99 samples of malignant gliomas, including 35 WHO grade II, 22 grade III, and 42 grade IV gliomas, by immunohistochemistry and western blot (n = 50). We then made correlative analysis of protein overexpression using the Kaplan-Meier method, Log rank test, and Cox proportional-hazards model analysis. NEK2 protein was overexpressed in malignant gliomas, but not in normal brain tissues. Overexpression of NEK2 correlated with malignancy, proliferation and adverse overall survival in gliomas. Moreover, chemotherapy, resection extent and WHO grade also correlate with overall survival in gliomas. However, within WHO grade II glioma subgroup, NEK2 overexpression showed no impact on overall survival. The present study firstly reveals that NEK2 protein is widely overexpressed in gliomas. NEK2 overexpression correlates significantly with malignancy (WHO grades), proliferation (Ki-67) and prognosis in malignant gliomas. NEK2 is a potential gene therapy target and prognostic indicator.

The pre-operational monitoring - how useful are recommendations of international organizations and various national programs

International Nuclear Information System (INIS)

Mihailovic, M.

1980-01-01

National legislation and the preoperational monitoring program around Nuclear Power Plant Krsko are described. The usefulness of international recommendations and various national preoperational monitoring programs is examined. Modifications are described which were introduced with the aim of identifying the site specific critical exposure pathways. The role of qualified and experienced experts is discussed. (H.K.)

Report on operation of nuclear facilities in Slovenia in 1991

International Nuclear Information System (INIS)

1992-11-01

Slovenian Nuclear Safety Administration (SNSA) is responsible for: nuclear safety, transport of nuclear and radioactive materials, safeguarding nuclear materials, and conducting regulatory process related to liability for nuclear damage, qualification and training of operators at nuclear facilities, quality assurance and inspection of nuclear facilities. The major nuclear facility supervised by SNSA is the Nuclear Power Plant in Krsko with a pressurized water reactor of 632 MW electric power. Beside the nuclear power plant, TRIGA Mark 11 Research Reactor of 250 kW thermal power operates within the Reactor Center of Jozef Stefan Institute. There is an interim storage of low and medium radioactive waste at the Reactor Center. Also the Uranium mine Zirovski Vrh was supervised by SNSA. All the nuclear power facilities in Republic of Slovenia were operating safely in 1991. There were no significant events that could be evaluated as a safety problem or a breach of technical specifications. A great part of activities of SNSA was focused on the next visit of the IAEA OSART team (Operational Safety Assessment Review Team) in Krsko Nuclear Power Plant and on the visit of the INSARR mission (Integrated Safety Assessment of Research Reactors) for the TRIGA Mark 11 Research Reactor. (author)

Steam generator replacement from ALARA aspects

International Nuclear Information System (INIS)

Terry, I.; Breznik, B.

2003-01-01

This paper is going to consider radiological related parameters important for steam generator replacement (SGR) implementation. These parameters are identified as ALARA related parameters, owner-contractor relationship, planning, health physics with logistic services, and time required for the replacement. ALARA related parameters such as source or initial dose rate and plant system configuration define the initial conditions for the planning. There is room to optimise work planning. managerial procedures and also the staff during the implementation phase. The overview of these general considerations is based on the following background: using internationally available data and the experience of one of the vendors, i.e. Siemens-Framatome, and management experience of SG replacement which took place at Krsko NPP in the spring of 2000. Generally plant decisions on maintenance or repair procedures under radiation conditions take into account ALARA considerations. But in the main it is difficult to adjudge the results of an ALARA study, usually in the form of a collective dose estimate, because a comparison standard is missing. That is, very often the planned work is of a one-off nature so comparisons are not possible or the scopes are not the same. In such a case the collective doses for other types of work are looked at and a qualitative evaluation is made. In the case of steam generator replacement this is not the case. Over years of steam generator replacements world-wide a standard has been developed gradually. The first part of the following displays an overview of SGR and sets the Krsko SGR in perspective by applying dose analysis. The second part concentrates on the Krsko SGR itself and its ALARA aspects. (authors)

Mathematical model of the reactor coolant pump

International Nuclear Information System (INIS)

Kozuh, M.

1989-01-01

The mathematical model of reactor coolant pump is described in this paper. It is based on correlations for centrifugal reactor coolant pumps. This code is one of the elements needed for the simulation of the whole NPP primary system. In subroutine developed according to this model we tried in every possible detail to incorporate plant specific data for Krsko NPP. (author)

License renewal process

International Nuclear Information System (INIS)

Fable, D.; Prah, M.; Vrankic, K.; Lebegner, J.

2004-01-01

The purpose of this paper is to provide information about license renewal process, as defined by Nuclear Regulatory Commission (NRC). The Atomic Energy Act and NRC regulations limit commercial power reactor licenses to an initial 40 years but also permit such licenses to be renewed. This original 40-year term for reactor licenses was based on economic and antitrust considerations not on limitations of nuclear technology. Due to this selected time period; however, some structures and components may have been engineered on the basis of an expected 40-year service life. The NRC has established a timely license renewal process and clear requirements codified in 10 CFR Part 51 and 10 CFR Part 54, that are needed to assure safe plant operation for extended plant life. The timely renewal of licenses for an additional 20 years, where appropriate to renew them, may be important to ensuring an adequate energy supply during the first half of the 21st Century. License renewal rests on the determination that currently operating plants continue to maintain adequate levels of safety, and over the plant's life, this level has been enhanced through maintenance of the licensing bases, with appropriate adjustments to address new information from industry operating experience. Additionally, NRC activities have provided ongoing assurance that the licensing bases will continue to provide an acceptable level of safety. This paper provides additional discussion of license renewal costs, as one of key elements in evaluation of license renewal justifiability. Including structure of costs, approximately value and two different approaches, conservative and typical. Current status and position of Nuclear Power Plant Krsko, related to license renewal process, will be briefly presented in this paper. NPP Krsko is designed based on NRC Regulations, so requirements from 10 CFR 51, and 10 CFR 54, are applicable to NPP Krsko, as well. Finally, this paper will give an overview of current status of

Croatian radioactive waste management program: Current status

International Nuclear Information System (INIS)

Matanic, R.; Lebegner, J.

2001-01-01

Croatia has a responsibility to develop a radioactive waste management program partly due to co-ownership of Krsko nuclear power plant (Slovenia) and partly because of its own medical and industrial radioactive waste. The total amount of generated radioactive waste in Croatia is stored in temporary storages located at two national research institutes, while radioactive waste from Krsko remains in temporary storage on site. National power utility Hrvatska Elektroprivreda (HEP) and Hazardous Waste Management Agency (APO) coordinate the work regarding decommissioning, spent fuel management and low and intermediate level radioactive waste (LILRW) management in Croatia. Since the majority of work has been done in developing the LILRW management program, the paper focuses on this part of radioactive waste management. Issues of site selection, repository design, safety assessment and public acceptance are being discussed. A short description of the national radioactive waste management infrastructure has also been presented. (author)

Recent improvements in program packages SHUFFLE and FAR

International Nuclear Information System (INIS)

Slavic, S.; Kromar, M.; Zefran, B.

1996-01-01

Program packages SHUFFLE and FAR were developed at 'Jozef Stefan' Institute to monitor all changes of fuel assemblies during a nuclear power plant operation. Both packages were written in the Clipper language which is suitable for data base applications and allows straightforward communications with other available data bases. Packages currently run on PC machines under DOS operating system. Both packages are in routine use at a nuclear power plant Krsko, but they can be applied to any PWR power plant without significant modification. Experiences obtained from the utility in past few years triggered several improvements and new features. (author)

16 x 16 Vantage+ Fuel Assembly Flow Vibrational Testing

International Nuclear Information System (INIS)

Chambers, Martin; Kurincic, Bojan

2014-01-01

Nuklearna Elektrarna Krsko (NEK) has experienced leaking fuel after increasing the cycle duration to 18 months. The leaking fuel mechanism has predominantly been consistent over multiple cycles and is typically observed in highly irradiated Fuel Assemblies (FA) after around 4 years of continuous operation that were located at the core periphery (baffle). The cause of the leaking fuel is due to Grid-To-Rod-Fretting (GRTF) and occasional debris fretting. NEK utilises a 16x16 Vantage+ FA design with all Inconel structural mixing vane grids (8 in total), Zirlo thimbles, Integral Fuel Burnable Absorber (IFBA) rods with enriched ZrB2, enriched Annular Blanket, Debris Filter Bottom Nozzle (DFBN), Removable Top Nozzle (RTN) and Zirlo fuel cladding material with a high burnup capability of 60 GWD/MTU. Numerous design and operational changes are thought to have reduced the original 16x16 FA design margin to fretting resistance of either vibration or its wear work rate, such as significant power uprate (spring force loss, rod creep down...), operational cycle duration increase from 12 to 18 months (increasing residence time as well as lead FA and fuel rod burnup values), Reactor Coolant System flow increase (increased vibration), removal of Thimble Plugs (increased bypass flow, increased vibration) and Zirc-4 to Zirlo cladding change (decreasing wear work rate). The fuel rod to grid spring as well as dimple contact areas are relatively smaller than other FA designs that exhibit good in-reactor fretting performance. A FA design change project to address the small rod to dimple / spring contact area and utilise fuel cladding oxide coating is currently being pursued with the fuel supplier. The FA vibrational properties are very important to the in-reactor FA performance and reliability. The 16x16 Vantage+ vibrational testing was performed with a full size FA in the Fuel Assembly Compatibility Testing (FACTS) loop that is able to provide full flow rates at elevated temperature

Emergency preparedness in Slovenia

International Nuclear Information System (INIS)

Martincic, R.; Korun, M.; Pucelj, B.; Usenicnik, B.

1996-01-01

Slovenia has a two-loop PWR, 632 MW electric power at Krsko and a research reactor (TRIGA, 250 kW) near Ljubljana. Construction at the Krsko site began in early 1975 and the plant was synchronized to the national grid in October 1981. In Slovenia we had also an uranium mine at Zirovski which is at present in the decommissioning stage. There are more than 400 radiation sources with activities between 100 MBq and 10 GBq and a few between 1 and 10 TBq in use in Slovenia. Changes that occurred in Slovenia as a result of independence required a new assessment of the situation in the field of disaster protection, as well as the coordination of policies and goals. Slovenia is at present in the process of reconstructing its system of protection against natural and other disasters. In this general context nuclear or radiological accidents fall under industrial accidents which in turn are treated as 'other disasters'

Management of safety culture

International Nuclear Information System (INIS)

Kavsek, D.

2004-01-01

The strengthening of safety culture in an organization has become an increasingly important issue for nuclear industry. A high level of safety performance is essential for business success in intensely competitive global environment. This presentation offers a discussion of some principles and activities used in enhancing safety performance and appropriate safety behaviour at the Krsko NPP. Over the years a number of events have occurred in nuclear industry that have involved problems in human performance. A review of these and other significant events has identified recurring weaknesses in plant safety culture and policy. Focusing attention on the strengthening of relevant processes can help plants avoid similar undesirable events. The policy of the Krsko NPP is that all employees concerned shall constantly be alert to opportunities to reduce risks to the lowest practicable level and to achieve excellence in plant safety. The most important objective is to protect individuals, society and the environment by establishing and maintaining an effective defense against radiological hazard in the nuclear power plant. It is achieved through the use of reliable structures, components, systems, and procedures, as well as plant personnel committed to a strong safety culture. The elements of safety culture include both organizational and individual aspects. Elements commonly included at the organizational level are senior management commitment to safety, organizational effectiveness, effective communication, organizational learning, and a culture that encourages identification and resolution of safety issues. Elements identified at the individual level include personal accountability, a questioning attitude, communication, procedural adherence, etc.(author)

Scenario development and evaluation for the NPP Krsko revised decommissioning program

International Nuclear Information System (INIS)

Levanat, I.; Lokner, V.; Subasic, D.

2004-01-01

In this first revision, several integrated scenarios of the NPP Krsko dismantling and waste management were developed and analyzed in order to estimate the decommissioning program (DP) costs and to propose an appropriate funding plan. Most dismantling technologies and cost estimates were derived from the original decommissioning plan adopted in 1996. The LILW disposal cost estimates, however, rely on the tunnel type facility design which was developed in Slovenia a few years ago, whereas the SF repository design for this DP was adapted from the Swedish deep disposal concept. The starting assumptions for this DP were that the LILW repository would be licensed by 2013, the NPP would be permanently shut down in 2023, and the SF repository would become available in 2030. The boundary conditions also specified that DP should first re-evaluate the SID strategy from the original plan (Strategy Immediate Dismantling with immediate SF disposal, but also with a long period of on-site decay storage for the activated components, so that it actually terminates only after 96 years), and then modify it to achieve truly prompt decommissioning in which all planned activities should be completed within about 15 years after the NPP shut-down. In addition, the option of SF export to a third country should be introduced in all DP scenarios, as a realistic alternative to SF disposal into the local repository (in Slovenia or in Croatia). And finally, dry storage of SF for some 30 years before disposal or export, in an independent installation on unspecified location, should be evaluated within the DP sensitivity analysis. After a thorough analysis of the original SID strategy, it became clear that substantial modifications would be necessary in order to meet the boundary conditions while complying with the specified design and technologies of the assumed LILW and SF disposal facilities. Therefore, a systematic procedure for development and financial evaluation of feasible scenarios was

Belene nuclear power plant contracting approach

International Nuclear Information System (INIS)

Tankosic, D.; Mignone, O.

2004-01-01

Historically, three main types of project execution and contractual approaches have been applied to energy and industrial projects, including nuclear projects. These approaches are grouped into three broad categories: 1) Turnkey Approach; 2) Split Package (Island) Approach; and 3)Multiple Package Approach. Based on a preliminary screening done by an ongoing feasibility study work for NPP Belene (NEK contract to Parsons E and C), the recommended approach is going to follow that general trend i.e., with some variation between the Split Package and the Turnkey approach. Before deciding on an execution approach or at least before issuing bid specifications for the nuclear power plant, it is prudent, even for a country with existing nuclear power program (like Bulgaria), to re-check/verify capabilities of the interested bidders to handle contracts of this size and nature. During the last decades, nuclear energy went through a substantial restructuring and most of the capabilities (human and financial) that existed before are not any more available. This re-checking should mainly cover the experience of the bidders as regards the design, construction and operation of the stations where they were involved, but also include items such as local experience, capability to bring favorable financing, liability coverage, general background, potential and organizational structures. The advantages and disadvantages for the Owner of the three contracting approaches can be briefly summarized as follows: Turnkey Approach - main advantages: all responsibilities rest in a Contractor or Consortium. Main disadvantages - limited project control by Owner and restricted local participation. For Split Package Contract Approach main advantage are more favorable financing conditions and increased local participation. Main disadvantage is the increased interface problems. For Multiple package Contract Approach main advantages are the opportunity to tailor the plant and maximum increase of local

Public opinion about nuclear energy 2001poll

International Nuclear Information System (INIS)

Stritar, A.; Istenic, R.

2001-01-01

In the Nuclear Training Centre in Ljubljana we are polling our visitors on a yearly basis. The visitors, mainly elementary and high school students, are polled before they listen to the lecture and visit the permanent exhibition. The attitude towards nuclear power remains favorable: 83,3% of polled population agrees with NPP Krsko operation until the end of its life cycle and 9,8% accept construction of another nuclear power plant in Slovenia.(author)

Public opinion about nuclear energy - 1998 poll

International Nuclear Information System (INIS)

Stritar, A.; Istenic, R.

1998-01-01

In the Nuclear Training center in Ljubljana we are polling our visitors on a yearly basis. The visitors are elementary and high school students. They are polled before they listen to the lecture and visit the permanent exhibition. This year we can observe some improved attitude towards nuclear energy. This could be influence of the absence of open attacks against the nuclear power plant Krsko in the media in last two years.(author)

Secondary School Youth Opinion Survey on Energetics within the Programme Nuclear Physics Use - the Past, Present and Future

International Nuclear Information System (INIS)

Skulj, B.; Filipin, R.

2002-01-01

METHOD OF SURVEY: As a part of the years-long educative programme Nuclear physics use: the past, present and future all parttakers fill in a survey questionaire of 11 topical questions, mostly related to the issues of nuclear energy. The questionaire is filled in before visiting the nuclear power plant Krsko. TARGET GROUP: Technical Musem, in cooperation with Hrvatska elektroprivreda, has been organizing high-school students' visits to the nuclear power plant Krsko since 1989. From all schools that have so far visited the nuclear power plant, Zagreb high schools and technical schools are the most represented ones. The respondents are aged between 16 and 20. The copies of the survey that have been filled in during 2000/2001 are to be analyzed, and the expected number of the respondents is about 600. QUESTIONS: Survey questions reflected several different fields, all in some sort of connection to nuclear energetics. Among them are: -present and future energy resources acceptability of different types of power plants environmental protection and global warming radioactivity radioactive waste issues nuclear power plants types of information resources. Such a wide range of different subjects included in the survey has been chosen so that, after its analysis, further efforts can be taken in quality informing of insufficiently known issues. Also, this kind of public poll will provide the Museum and Hrvatska elektroprivreda with relevant findings about the climate of opinion and the thinking of young generations towards energetics issues and the cause of its future development. The analyzed results of the survey present only a fragment of the material, later to be published in a separate publication. (author)

NPP life management program - status report for Slovenia

International Nuclear Information System (INIS)

Glumac, B.

1998-01-01

Status report on NPP life management in Slovenia is dealing with possible life extension of NPP Krsko which comprises: replacement of steam generator; power upgrade; exchange of plant process computer; snubber reduction program, additional forced ventilation cooling system. Fuel improvements are predicted as well as the problems of storing spent fuel, low and intermediate waste if the plant is to operate through 2023 and possibly beyond that date. Related research activities are concerned with radiation damage, modelling of reactor core parameters by Monte Carlo calculations and PSA and severe accidents studies. Most of the activities are performed in cooperation with foreign organisations

Building trust with the schoolchildren in the nuclear training centre

International Nuclear Information System (INIS)

Stritar, Andrej; Istenie, Radko

1995-01-01

Although Krsko Nuclear Power Plant has been in operation for more than ten years, comparatively little has been done in the field of systematic education and public information. Deficiencies in this field are causing serious misunderstandings about the role of nuclear power and is having a negative impact on its public acceptance. At The Nuclear Training Centre Milan Copic (NTC) in Ljubljana we have prepared a presentation on nuclear energy encompassing a short description of a PWR nuclear power plant, importance of nuclear power in the world and in Slovenia, basic ideas of nuclear safety and radioactive waste disposal

Radiological emergency assessment of local decision support system

International Nuclear Information System (INIS)

Breznik, B.; Kusar, A.; Boznar, M.Z.; Mlakar, P.

2003-01-01

Local decision support system has been developed based on the needs of Krsko Nuclear Power Plant for quick dose projection and it is one of important features required for proposal of intervention before actual release may occur. Radiological emergency assessment in the case of nuclear accident is based on plant status analysis, radiation monitoring data and on prediction of release of radioactive sources to the environment. There are possibilities to use automatic features to predict release source term and manual options for selection of release parameters. Advanced environmental modelling is used for assessment of atmospheric dispersion of radioactive contamination in the environment. (author)

Component Cooling Heat Exchanger Heat Transfer Capability Operability Monitoring

International Nuclear Information System (INIS)

Mihalina, M.; Djetelic, N.

2010-01-01

The ultimate heat sink (UHS) is of highest importance for nuclear power plant safe and reliable operation. The most important component in line from safety-related heat sources to the ultimate heat sink water body is a component cooling heat exchanger (CC Heat Exchanger). The Component Cooling Heat Exchanger has a safety-related function to transfer the heat from the Component Cooling (CC) water system to the Service Water (SW) system. SW systems throughout the world have been the root of many plant problems because the water source, usually river, lake, sea or cooling pond, are conductive to corrosion, erosion, biofouling, debris intrusion, silt, sediment deposits, etc. At Krsko NPP, these problems usually cumulate in the summer period from July to August, with higher Sava River (service water system) temperatures. Therefore it was necessary to continuously evaluate the CC Heat Exchanger operation and confirm that the system would perform its intended function in accordance with the plant's design basis, given as a minimum heat transfer rate in the heat exchanger design specification sheet. The Essential Service Water system at Krsko NPP is an open cycle cooling system which transfers heat from safety and non-safety-related systems and components to the ultimate heat sink the Sava River. The system is continuously in operation in all modes of plant operation, including plant shutdown and refueling. However, due to the Sava River impurities and our limited abilities of the water treatment, the system is subject to fouling, sedimentation buildup, corrosion and scale formation, which could negatively impact its performance being unable to satisfy its safety related post accident heat removal function. Low temperature difference and high fluid flows make it difficult to evaluate the CC Heat Exchanger due to its specific design. The important effects noted are measurement uncertainties, nonspecific construction, high heat transfer capacity, and operational specifics (e

Steam generator replacement project in 2000

International Nuclear Information System (INIS)

Cerjak, J.; Holz, R.; Haus, J.; Gloaguen, C.

1999-01-01

NE Krsko has awarded the contract for the Steam Generator Replacement Project, which is one of the modernization projects in Krsko, to the Consortium of Siemens / Framatome in February 1998. This paper deals with the various aspects of the project: scope planning, engineering, preparation of modification packages for licensing, management, major techniques used, etc., showing also the status of the activities for the project which are scheduled to be performed in April through June 2000. The project is being performed on a turnkey basis, that means the Consortium is performing all engineering, preparation of the modification packages and site activities; NE Krsko is dealing with the licensing of the project.(author)

Medicinal plants used in Lesotho for treatment of reproductive and post reproductive problems.

Science.gov (United States)

Moteetee, A; Seleteng Kose, L

2016-12-24

Reproductive healthcare has been highlighted as a major challenge in Lesotho mainly due to the high prevalence of HIV/AIDS and sexually transmitted infections. As a result other reproductive ailments have not received much attention, particularly because healthcare facilities are already limited and many of them are inaccessible. For these reasons, medicinal plants play a major role in primary healthcare system in the country, in addition the plants are easily accessible, more affordable, and their use forms part of the cultural heritage. However, documentation of medicinal plants used for reproductive ailments is scattered, more importantly the biological and pharmacological properties, as well as toxicity of many of these plants are not yet known. To document the plants used by both male and female Basotho (residing in Lesotho) for the treatment of reproductive ailments, to explore their recorded biological and pharmacological effects as well as their toxicity, and to establish if these plants are used for similar purposes in other southern African cultures. The results stem from published findings of recent interviews of traditional medicinal practitioners in the Maseru District of Lesotho, first author's own experiences and observations from the Qacha's Nek District as well as comprehensive literature survey including numerous books and unpublished data. Electronic databases such as Google, Google Scholar, PubMed, and ScienceDirect were also used to search for the chemical compounds, pharmacological activity, and toxicity of the plants. A total of 87 plant species are reported to be used for the treatment of several reproductive problems such as infertility, complications associated with pregnancy (twelve plants are used to treat conditions such as colic, heartburn, nausea, and constipation), cleansing and/ or toning of the uterus (with a purpose either to induce pregnancy or to get rid of the placenta, for example Withania somnifera and Zantedeschia

Public opinion about nuclear energy, year 2002 poll

International Nuclear Information System (INIS)

Stritar, A.; Istenic, R.

2002-01-01

In the Nuclear Training Centre in Ljubljana we are polling our visitors on a yearly basis. The visitors, mainly elementary and high school students, are polled before they listen to the lecture and visit the permanent exhibition. In the year 2002 the attitude towards nuclear power remains favorable: 84,7% of polled population agrees with NPP Krsko operation until the end of its life cycle and 9,1% accept construction of another nuclear power plant in Slovenia.(author)

Determining of leakage rate of radionuclides Co-60 and Cs-137 in real conditioning; Odredjivanje brzine procurivanja radionuklida Co-60 i Cs-137 u realnim uslovima

Energy Technology Data Exchange (ETDEWEB)

Plecas, I; Peric, A; Kostadinovic, A [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

1989-07-01

In this paper, results of examination of LEAKAGE rate of radionuclides Co-60 and Cs-137 in real condition are given. Radionuclides Co-60 and Cs-137 were immobilized by cement process and conditioned in concrete containers trying to make similar scenario for repository of radioactive waste materials as in engineering trench systems. Experiments were realized with evaporator bottom concentrate (EB) from Nuclear Power Plant Krsko in which the main radionuclides are Co-60 and Cs-137. (author)

Genetic epidemiology of motor neuron disease-associated variants in the Scottish population.

Science.gov (United States)

Black, Holly A; Leighton, Danielle J; Cleary, Elaine M; Rose, Elaine; Stephenson, Laura; Colville, Shuna; Ross, David; Warner, Jon; Porteous, Mary; Gorrie, George H; Swingler, Robert; Goldstein, David; Harms, Matthew B; Connick, Peter; Pal, Suvankar; Aitman, Timothy J; Chandran, Siddharthan

2017-03-01

Genetic understanding of motor neuron disease (MND) has evolved greatly in the past 10 years, including the recent identification of association between MND and variants in TBK1 and NEK1. Our aim was to determine the frequency of pathogenic variants in known MND genes and to assess whether variants in TBK1 and NEK1 contribute to the burden of MND in the Scottish population. SOD1, TARDBP, OPTN, TBK1, and NEK1 were sequenced in 441 cases and 400 controls. In addition to 44 cases known to carry a C9orf72 hexanucleotide repeat expansion, we identified 31 cases and 2 controls that carried a loss-of-function or pathogenic variant. Loss-of-function variants were found in TBK1 in 3 cases and no controls and, separately, in NEK1 in 3 cases and no controls. This study provides an accurate description of the genetic epidemiology of MND in Scotland and provides support for the contribution of both TBK1 and NEK1 to MND susceptibility in the Scottish population. Copyright © 2017 The Authors. Published by Elsevier Inc. All rights reserved.

Citlivostní analýza jako nástroj pro verifikaci CFD modelu a optimalizaci konkrétního prvku

NARCIS (Netherlands)

Hojer, O.; Basta, J.; Hensen, J.L.M.

2006-01-01

Clánek zduraznuje význam volby vhodných okrajových podmínek pro správnost energetických simulacních výpoctu. Okrajové podmínky musí být vázány na úcel, pro který se simulacní výpocty provádí. Je predložen teoretický rozbor, metodologie a výsledky výpoctu ruzných okrajových podmínek stanovených z

Future needs in radiation protection training for NPP workers of Slovenia

International Nuclear Information System (INIS)

Kozelj, M.; Bogovic, T.

1999-01-01

Short review of history of radiation protection training for NPP workers in Slovenia and legal requirements regarding this field are presented. Courses developed in co-operation between Milan Copic Nuclear Training Centre and Krsko Nuclear Power Plant are briefly described and their implementation presented. Using available data we have predicted probable number of courses and participants in forthcoming years. Some results from inquiry on courses for regularly exposed workers are presented, enabling us to modify courses according to participants' needs.(author)

Evaluation of implementation 18-month cycle in NPP Krsko

International Nuclear Information System (INIS)

Novsak, M.; Bilic Zabric, T.

2003-01-01

The feasibility study, which evaluates the impacts of the transition to the 18-month cycle on plant design bases, operational and maintenance requirements, long-term economics of the operation, is performed. Activities, which have to be implemented for adopting 18- month cycle, are presented. The study shows that implementation of 18-month cycle is possible with some investments through transition 15-month cycle. (author)

The progress in development and use of nuclear energy for the power in Yugoslavia

International Nuclear Information System (INIS)

Vrhovac, S.; Bojic, K.; Fabijancic, A.; Medvedec, I.; Vujovic, D.

1984-01-01

Nuclear power plant Krsko from 1982, produces the power which is very useful for the electric power system of the country. At the same time, the investors of the nuclear power plants from republics and autonomous provinces of Yugoslavia have organized the construction of series of nuclear power plants up to 2000. The purpose of this report is to explain those activities which have initiated the process of development and the use of energy for the power in Yugoslavia, and to continue the attempts to place the near future to the progress of this process. The base of these efforts has to be solving the very problem of decision making regarding the best solution of nuclear fuel cycle, the type of nuclear power plants in Yugoslavia and their construction. (author)

The perspectives of nuclear option for Croatia

International Nuclear Information System (INIS)

Feretic, D.

2004-01-01

In order to satisfy the expected level of electricity consumption in Croatia it will be necessary, as a minimum, until the year 2020 to install about 2000 MW in new power plants. Gas and coal fired plants presently are main competitors to nuclear power plants. In near future it my be different due to expected problems with gas availability and cost increase and also in adverse environmental impact (particularly due to CO 2 emissions) of coal fired plants. Nuclear power plants have advantage not only in economics of produced energy but also in impact to the environment. Preservation of knowledge obtained during construction of NPP Krsko is also an important reason to maintain nuclear option. Pre construction and construction period for new plants (particularly for coal fired and nuclear plants) could be long so that timely start of preparatory activities is indispensable to meet the required schedule.(author)

Nuclear licensing in Slovenia

International Nuclear Information System (INIS)

Prah, M.; Spiler, J.; Vojnovic, D.; Pristavec, M.

1998-01-01

The article presents the approach to nuclear licensing in Slovenia. The paper describes, the initialization, internal authorization and review process in the Krsko NPP. The overall process includes preparation, internal independent evaluation, the Krsko Operating Committee and the Krsko Safety Committee review and internal approval. In addition, the continuation of the licensing process is discussed which includes independent evaluation by an authorized institution and a regulatory body approval process. This regulatory body approval process includes official hearing of the licensee, communication with the licensee, and final issuance of a license amendment. The internal evaluation, which follows the methodology of US NRC (defined in 10 CFR 50.59 and NUMARC 125) is described. This concept is partially implemented in domestic legislation.(author)

RODOS system in Slovenia

International Nuclear Information System (INIS)

Peteh, D.; Cindro, M.; Vokal Nemec, B.

2006-01-01

The RODOS (Real-time On-line DecisiOn Support) system was installed in Slovenia in the year 2004. Soon after installation it was concluded that the system is too complex and difficult to run as the support tool in case of an accident in the Krsko NPP. At present the SNSA (Slovenian Nuclear Safety Administration) is able to handle accidents at the Krsko nuclear power plant with RODOS modules that provide results for 1x1 km grid but only as additional post-accident analytical tool. However, RODOS is being used as the on-line tool for the analysis of the consequences of accidents in other European nuclear power plants. Those are processed with coarser tools (20x20 km grid). It is also possible to handle various radiological accidents, like source melt in iron mills or terrorist attacks, irrespective of the location of the accident. Monthly exercises are conducted at the SNSA for various accident scenarios. The aim of the exercises is to assess the possibility of RODOS incorporation in the SNSA emergency procedures. RODOS users around Europe form a tightly knit community, with the aim of prompt data and result exchange. For that purpose, new modules are being developed that will facilitate this process. The RODOS development team, prompted by the user feedback, is currently working on new versions that will be more user-friendly and easier to work with. (author)

Public Acceptance, a Key Issue of Nuclear Energy

International Nuclear Information System (INIS)

Stritar, A.

1996-01-01

A brief history of public acceptance of nuclear energy in Slovenia is given. While in former Yugoslavia a problem of public acceptance virtually did not exist because of undemocratic social system, it grew larger and larger with the process of democratization in late eighties. The first democratic government in Slovenia had to abandon its original idea for an early closure of the nuclear power plant Krsko. In 1995 and 1996 there were two attempts to organize the national referendum about the future of the plant. The lessons learned from the public debates in recent years could help other countries entering the nuclear program to prepare and implement efficient public information strategy. (author)

The Role of Occupational Health and Safety in Complex Outage Services to NPPs

International Nuclear Information System (INIS)

Rozman, A.; Androjna, A.

2010-01-01

Meeting outage schedules in NPPs which are increasingly demanding, apart from all other aspects, introduces a new perspective on occupational health and safety (OHS). Not only is the OHS a constituent part of a plant's overall outage management, it above all dictates paramount objectives to outage service providers. The paper reviews the impacts of reductions of outage durations on OHS and presents related experience of the leading Slovenian outage services provider, NUMIP d.o.o. over the last ten years. The company is now getting prepared for its 12th outage at Krsko NPP in 2010, and has not have recorded a major injury so far, even though these projects engaged over 450 people at a time on-site. To achieve such results, a lot of emphasis is being put onto OHS management prior to and during outages. A certified OHSAS 18001 system has been established and implemented to further support preparation and execution of NUMIP's outage activities at Krsko NPP, and also for other projects. An effective continuous improvement system is built into the project, providing for implementation of lessons learned from domestic and foreign plants. To illustrate the topic in more detail, a case on a Seismic protection of polar crane project is presented. It took place in the 2009 Outage and has certainly been one of the most demanding projects from the OHS point of view for NUMIP so far. The paper aims at contributing to a better understanding of the role of effective management of OHS on the side of a service provider, and, consequently, in the overall outage success of a plant.(author).

Time for Competent Decisions on Radioactive Waste Management in Croatia

International Nuclear Information System (INIS)

Knapp, A.; Levanat, I.; Saponja-Milutinovic, D.; Lokner, V.

2013-01-01

After a couple of decades of hesitant and indecisive consultations between Slovenia and Croatia on the management options for the Krsko nuclear power plant (KNPP) waste, time for decision making has approached. Council Directive 2011/70/Euratom requires that both countries adopt specific national programs for radioactive waste and spent fuel management before August 23, 2015. In the nineties, Croatia undertook a campaign aimed at constructing a low and intermediate level waste (LILW) repository. The region of Trgovska gora was designated as the potential repository site, and a preliminary safety assessment indicated that it was suitable for a near surface vault-type disposal facility - but then the campaign was stopped. Soon after, Slovenia intensified preparations for a LILW repository on its territory, and Krsko (near the NPP) was selected for disposal site. An exotic and expensive silo-type disposal concept was adopted, disposal units immersed into the groundwater flowing towards the nearby Sava river. The project continues. Presently, however, Croatia does not know whether it will be allowed to dispose of its share of LILW from the KNPP into the Slovenian repository, nor under what conditions. Croatia does not know whether it will have to build its own repository, nor whether such solution would be financially preferable - although Croatia may have to begin transferring its half of the KNPP waste to its territory in less than ten years. It is therefore high time for Croatia to resume intensive preparations for the establishment of a LILW repository on Trgovska gora - regardless of whether or not it would actually be constructed. Without such preparations, and the insights gained, Croatia will not be capable of making competent decisions about its national interests regarding the KNPP waste management, nor will it be prepared for competent and convincing negotiations with Slovenia about the options for sharing the Krsko facility.(author)

Balance and forms of zinc in soil and its uptake by plants

Directory of Open Access Journals (Sweden)

Šárka Poláková

2006-01-01

Full Text Available In this paper, zinc flows in arable soils of the Czech Republic and zinc fractions in arable soils are studied. Furthermore, a zinc uptake by agricultural plants is focused. Based on a database of the programme The basal soil monitoring system (BSMS a static zinc balance for arable soils on the national level was assessed. This programme is carried out by The Central Institute for Supervising and Testing in Agriculture (CISTA in Brno. As a representative for the zinc balance calculation, 121 monitoring plots were chosen. The Czech Republic net zinc fluxes ranged from –1250 g.ha– 1.y– 1 to +5595 g.ha– 1.y– 1, median +453 g.ha– 1.y– 1. The maximum zinc fluxes are typical of plots with manure applications. An atmospheric deposition is the most important input of zinc into arable soils. It makes 96,6% of the whole inputs. Leaching and run-off are neglected in this zinc balance by reason of missing credible data. The project Examination of zinc availability in dependence on its form in soil was established to provide more information about behavior of zinc in soil. The first step was starting a greenhouse pot experiment, which was focused on comparison of several extraction agents (AR, 2M HNO3, 0.43M HNO3, Mehlich III, DTPA, CAT, 1M NH4NO3, 0.01M CaCl2. Four soils with increasing zinc content were picked out for this experiment (Domanínek, Chrlice, Kutná Hora, Hlízov. Total zinc contents in these selected soils ranged from 156.8 to 583.7 ppm in dry matter (Aqua regia extraction. Contents in plants were in wide range from 20.7 to 273 ppm in dry matter according to the plant variety and used soil. Strong correlations between 0.43M HNO3, Mehlich III, DTPA and CAT were proved. Using of weaker extraction agents enabled to distinguish geogenic and anthropogenic origin of the contamination.

Ageing Management Program Database

International Nuclear Information System (INIS)

Basic, I.; Vrbanic, I.; Zabric, I.; Savli, S.

2008-01-01

The aspects of plant ageing management (AM) gained increasing attention over the last ten years. Numerous technical studies have been performed to study the impact of ageing mechanisms on the safe and reliable operation of nuclear power plants. National research activities have been initiated or are in progress to provide the technical basis for decision making processes. The long-term operation of nuclear power plants is influenced by economic considerations, the socio-economic environment including public acceptance, developments in research and the regulatory framework, the availability of technical infrastructure to maintain and service the systems, structures and components as well as qualified personnel. Besides national activities there are a number of international activities in particular under the umbrella of the IAEA, the OECD and the EU. The paper discusses the process, procedure and database developed for Slovenian Nuclear Safety Administration (SNSA) surveillance of ageing process of Nuclear power Plant Krsko.(author)

Experience with high percent step load decrease from full power in NPP Krsko

International Nuclear Information System (INIS)

Vukovic, V.

2000-01-01

The control system of NPP Kriko, is designed to automatically control the reactor in the power range between 15 and 100 percent of rated power for the following designed transients; - 10 percent step change in load; 5 percent per minute loading and unloading; step full load decrease with the aid of automatically initiated and controlled steam dump. Because station operation below 15 percent of rated power is designed for a period of time during startup or standby conditions, automatic control below 15 percent is not provided. The steam dump accomplishes the following functional tasks: it permits the nuclear plants to accept a sudden 95 percent loss of load without incurring reactor trip; it removes stored energy and residual heat following a reactor trip and brings the plant to equilibrium no-load conditions without actuation of the steam generator safety valves; it permits control of the steam generator pressure at no-load conditions and permits a manually controlled cooldown of the plant. The first two functional tasks are controlled by Tavg. The third is controlled by steam pressure. Interlocks minimise any possibility of an inadvertent actuation of steam dump system. This paper discusses relationships between designed (described) characteristics of plant and the data which are obtained during startup and/or first ten years of operation. (author)

Small Molecule TH-39 Potentially Targets Hec1/Nek2 Interaction and Exhibits Antitumor Efficacy in K562 Cells via G0/G1 Cell Cycle Arrest and Apoptosis Induction.

Science.gov (United States)

Zhu, Yongxia; Wei, Wei; Ye, Tinghong; Liu, Zhihao; Liu, Li; Luo, Yong; Zhang, Lidan; Gao, Chao; Wang, Ningyu; Yu, Luoting

2016-01-01

Cancer is still a major public health issue worldwide, and new therapeutics with anti-tumor activity are still urgently needed. The anti-tumor activity of TH-39, which shows potent anti-proliferative activity against K562 cells with an IC50 of 0.78 µM, was investigated using immunoblot, co-immunoprecipitation, the MTT assay, and flow cytometry. Mechanistically, TH-39 may disrupt the interaction between Hec1 and Nek2 in K562 cells. Moreover, TH-39 inhibited cell proliferation in a concentration- and time-dependent manner by influencing the morphology of K562 cells and inducing G0/G1 phase arrest. G0/G1 phase arrest was associated with down-regulation of CDK2-cyclin E complex and CDK4/6-cyclin D complex activities. Furthermore, TH-39 also induced cell apoptosis, which was associated with activation of caspase-3, down-regulation of Bcl-2 expression and up-regulation of Bax. TH-39 could also decrease mitochondrial membrane potential (Δψm) and increase reactive oxygen species (ROS) accumulation in K562 cells. The results indicated that TH-39 might induce apoptosis via the ROS-mitochondrial apoptotic pathway. This study highlights the potential therapeutic efficacy of the anti-cancer compound TH-39 in treatment-resistant chronic myeloid leukemia. © 2016 The Author(s) Published by S. Karger AG, Basel.

What is new in the Act on Nuclear Safety

International Nuclear Information System (INIS)

Novosel, N.

2005-01-01

The Act on Nuclear Safety was passed by the Croatian Parliament on 15 October 2003, and published in Narodne novine (official journal) No. 173/03. This Act regulates safety measures for using nuclear materials and equipment, regulates nuclear activities, and establishes the National Office for Nuclear Safety. The new act supersedes the Act on Protective Measures Against Ionising Radiation and Safety in the Use of Nuclear Facilities and Installations (Narodne novine No. 18/81) and the Act on Protection against Ionising Radiation and Special Safety Measures in Using Nuclear Energy (Narodne novine No. 53/91). Regulations based on the latter Act shall apply until they are replaced by new regulations based on the Act on Nuclear Safety. Provisions of this Act apply for nuclear activities, nuclear materials and specified equipment. Croatia does not have nuclear facilities on its territory, but a Croatian power utility company owns 50% of the Nuclear Power Plant Krsko on the territory of Slovenia. In that respect, Croatia has assumed responsibilities defined by the Agreement between the Government of the Republic of Slovenia and the Government of the Republic of Croatia on the Regulation of the Status and Other Legal Relationships, Connected with Investments in the Krsko Nuclear Power Plant, its Exploitation and Decommissioning (Narodne novine No. 9/02, International Agreements). Having accessioned international conventions and agreements, Croatia has also assumed the responsibility to implement their provisions. In the process of European and international integrations, Croatia has to harmonize with the European and international standards in nuclear safety.(author)

Development of local partnership for siting of LILW repository in Slovenia

International Nuclear Information System (INIS)

Kralj, Metka; Zeleznik, Nadja

2007-01-01

Available in abstract form only. Full text of publication follows: Slovenia has only temporary storage facilities for radioactive waste. According to the legislation, a permanent LILW repository site should be authorized by 2008, and the repository has to acquire the operating licence by 2013. In 2006, ARAO, the general public and three municipalities established local partnerships in order to increase public acceptability of the LILW repository. Civil initiative groups opposed to the siting appeared in all three local communities. In one case they forced the municipality to withdraw, in one case they changed the siting location, and in one case they were integrated to local partnership. In the municipality of Krsko, the program of local partnership was publicly discussed. There is an NPP in Krsko, so the local partnership also demanded to discuss the power plant issues. Thematic committees were established that worked separately. They also discussed the issues of the spatial plan for the repository. In the municipality of Brezice, a steering committee was established to promote local partnership activities and organization of thematic committees. There was only one active thematic committee, but many activities for the general public were organised. In the municipality of Sevnica, the local partnership was soon cancelled. (authors)

Fanconi anemia complementation group A (FANCA) localizes to centrosomes and functions in the maintenance of centrosome integrity.

Science.gov (United States)

Kim, Sunshin; Hwang, Soo Kyung; Lee, Mihee; Kwak, Heejin; Son, Kook; Yang, Jiha; Kim, Sung Hak; Lee, Chang-Hun

2013-09-01

Fanconi anemia (FA) proteins are known to play roles in the cellular response to DNA interstrand cross-linking lesions; however, several reports have suggested that FA proteins play additional roles. To elucidate novel functions of FA proteins, we used yeast two-hybrid screening to identify binding partners of the Fanconi anemia complementation group A (FANCA) protein. The candidate proteins included never-in-mitosis-gene A (NIMA)-related kinase 2 (Nek2), which functions in the maintenance of centrosome integrity. The interaction of FANCA and Nek2 was confirmed in human embryonic kidney (HEK) 293T cells. Furthermore, FANCA interacted with γ-tubulin and localized to centrosomes, most notably during the mitotic phase, confirming that FANCA is a centrosomal protein. Knockdown of FANCA increased the frequency of centrosomal abnormalities and enhanced the sensitivity of U2OS osteosarcoma cells to nocodazole, a microtubule-interfering agent. In vitro kinase assays indicated that Nek2 can phosphorylate FANCA at threonine-351 (T351), and analysis with a phospho-specific antibody confirmed that this phosphorylation occurred in response to nocodazole treatment. Furthermore, U2OS cells overexpressing the phosphorylation-defective T351A FANCA mutant showed numerical centrosomal abnormalities, aberrant mitotic arrest, and enhanced nocodazole sensitivity, implying that the Nek2-mediated T351 phosphorylation of FANCA is important for the maintenance of centrosomal integrity. Taken together, this study revealed that FANCA localizes to centrosomes and is required for the maintenance of centrosome integrity, possibly through its phosphorylation at T351 by Nek2. Copyright © 2013 Elsevier Ltd. All rights reserved.

Radionuclide migration through porous cement-waste composition in semi-real conditions

International Nuclear Information System (INIS)

Plecas, I.; Peric, A.; Kostadinovic, A.

1989-01-01

In this paper, result of examination of Leakage rate or radionuclides Co-60 and Cs-137 in semi-real conditions are given. Radionuclides Co-60 and Cs-137 were immobilized by cement process and conditioned in concrete containers trying to make similar scenario for storing radioactive waste materials as in engineering trench system, repository. Experiments were realized with two waste water, evaporator bottom and reactor cooling system, (EB) and (RCS), from Nuclear Power Plants Krsko, in which the main radionuclides are Co-60 and Cs-137. These results will be used for future Yugoslav radioactive waste storing center (author)

Fast thermal transients on valve

International Nuclear Information System (INIS)

Ferjancic, M.; Stok, B.; Halilovic, M.; Koc, P.; Mole, N.; Otrin, Z.; Kotar, A.

2007-01-01

One of the regulatory body methods to supervise nuclear safety of a nuclear power plant is a review of plant modifications and evaluation of their impact on plant operating experience. The Slovenian Nuclear Safety Administration (SNSA) licensed in April 2003 the use of leak-before-break (LBB) methodology in the Krsko NPP for the primary loop including surge line and connecting pipelines with minimal diameter of 6 inch. The SNSA decision based also on fracture mechanics analyses that include direct pipe failure mechanisms such as water hammer, creep damage, erosion and corrosion, fatigue and environmental conditions over the entire life of the plant. The evaluation of the operating transients pointed out, that presumed loadings, used for the LBB analysis, did not incorporate all the fast thermal transients data. For that purpose the SNSA requested Faculty of Mechanical Engineering (FS) in Ljubljana to perform additional analyses. The results of the analysis shall confirm the validity of the LBB analysis. (author)

Determining the boron concentration during long-term cooling of the reactor core after large loss of coolant accident; Dolocenje koncentracij bora pri dolgotrajnoem hladjenju sredice po veliki izlivni nezgodi

Energy Technology Data Exchange (ETDEWEB)

Mavko, B; Ravnki, M [Institut Jozef Stefan, Ljubljana (Yugoslavia)

1988-07-01

Critical boron concentration before and after postulated loss of coolant accident with long-term cooling recirculation was calculated for cycle 6 of Krsko NPP. The limiting boron concentration curve of containment sump was calculated for equilibrium conditions. The results were analysed and showed that the boron concentration in refueling water storage tank and in safety injection accumulators should be increased from 2000 to 2100 ppm in 6th cycle. In the consequence corresponding chapters of the NPP Krsko technical Specifications were changed as well. (author)

Emplacement of inflated Pāhoehoe flows in the Naude's Nek Pass, Lesotho remnant, Karoo continental flood basalt province: use of flow-lobe tumuli in understanding flood basalt emplacement

Science.gov (United States)

Jay, Anne E.; Marsh, Julian S.; Fluteau, Frédéric; Courtillot, Vincent

2018-02-01

Physical volcanological features are presented for a 710-m-thick section, of the Naude's Nek Pass, within the lower part of the Lesotho remnant of the Karoo Large Igneous Province. The section consists of inflated pāhoehoe lava with thin, impersistent sedimentary interbeds towards the base. There are seven discreet packages of compound and hummocky pāhoehoe lobes containing flow-lobe tumuli, making up approximately 50% of the section. Approximately 45% of the sequence consists of 14 sheet lobes, between 10 and 52-m-thick. The majority of the sheet lobes are in two packages indicating prolonged periods of lava supply capable of producing thick sheet lobes. The other sheet lobes are as individual lobes or pairs, within compound flows, suggesting brief increases in lava supply rate. We suggest, contrary to current belief, that there is no evidence that compound flows are proximal to source and sheet lobes (simple flows) are distal to source and we propose that the presence of flow-lobe tumuli in compound flows could be an indicator that a flow is distal to source. We use detailed, previously published, studies of the Thakurvadi Formation (Deccan Traps) as an example. We show that the length of a lobe and therefore the sections that are `medial or distal to source' are specific to each individual lobe and are dependent on the lava supply of each eruptive event, and as such flow lobe tumuli can be used as an indicator of relative distance from source.

FUMACS-G, a Graphical User Interface for FUMACS Code Package

International Nuclear Information System (INIS)

Trontl, K.; Gergeta, K.; Smuc, T.

2002-01-01

The FUMACS (FUel MAnagement Code System) code package has been developed at Rudjer Boskovic Institute in year 1991 with the aim to enable in-core fuel management analysis of the NPP Krsko core for nominal conditions. Due to modernization and uprating of the NPP Krsko core in year 2000 and the original 1991 FUMACS inadequacy in simulating NPP Krsko core in these uprated conditions, in the year 2001 a new version of FUMACS code package has been developed - FUMACS/FEEC 2001. The code package upgrading procedure consisted of two main aspects: modifications of master files, libraries and codes necessary for proper modeling of the uprated NPP Krsko core and development of the code package structure suitable for Windows-32 environment. The latter included upgrading the source of the code from FORTRAN F77 to F90 level and development of a graphical, user-friendly interface with fully integrated electronic help system. Since the original FUMACS code package has been developed as a DOS based application, running of the code package on a Windows operating system proved to be rather inefficient and lacking in advantages of a standard Windows application. Therefore, FUMACS-G has been developed as a user friendly environment for handling off all project input and output files, as well as for easier overall project management. The design of FUMACS-G shell has been based on Microsoft application design guidelines. (author)

Cyber Security in Nuclear Power Plants - U.S. NRC Regulatory Guide 5.71

International Nuclear Information System (INIS)

Pogacic, Goran

2014-01-01

We have already made a big step into new millennia and with it there is no more dilemma about presence of computers and internet in our lives. Almost all modern facilities struggle with this new dimension of information flow and how to use it to their best interest. But there is also the other side of the coin- the security threat. For nuclear power plants this threat poses even greater risk. In addition to protecting their trade secrets, personal data or other common targets of cyber attacks, nuclear power plants need to protect their digital computers, communication systems and networks up to and including the design basis threat (DBT). As stated in U.S. Nuclear Regulatory Commission (NRC) Regulatory Commission Regulations, Title 10, Code of Federal Regulations (CFR), section 73.1, 'Purpose and Scope' this includes protection against acts of radiological sabotage and prevention of the theft or diversion of special nuclear material. The main purpose of this paper is to explore the NRC Regulatory Guide (RG) 5.71 and its guidance in implementing cyber security requirements stated in NRC 10 CFR, section 73.54, 'Protection of Digital Computer and Communication Systems and Networks'. In particular, this section requires protection of digital computers, communication systems and networks associated with the following categories of functions: · safety-related and important-to-safety functions, · security functions, · emergency preparedness functions, including offsite communication, and · support systems and equipment which, if compromised, would adversely impact safety, security, or emergency preparedness functions. This section requires protection of such systems and networks from those cyber attacks that would act to modify, destroy, or compromise the integrity or confidentiality of data or software; deny access to systems, services or data; and impact the operation of systems, networks, and equipment. This paper will also present some of

Development of a General Conceptual-numerical Model to Simulate the Fate and Subsurface Transport of Explosives, and the Moisture and Temperature Signatures Around Land Mines

Science.gov (United States)

2008-12-01

Chen, J. Gan, J. Šimůnek, A. C. Chang, and L. Wu, Leaching risk of N-nitrosodimethylamine ( NDMA ) in soil receiving reclaimed wastewater, Highlighted...Abstracts, published on a CD-ROM as abstract 5043, ASA, Madison, 2005. Haruta, S., J. Gan, and J. Šimunek, Numerical Analyses of NDMA Leaching Risk in...Gan, J. Šimůnek, A. C. Chang, and L. Wu, Leaching risk of N- nitrosodimethylamine ( NDMA ) in soil receiving reclaimed wastewater, Highlighted article

NPP Prevlaka - Preparation of construction

International Nuclear Information System (INIS)

Bojic, K.

1984-01-01

On the basis of study 'Optimal electricity generation structure till the year 2000' production of 3 x 500 MWe in nuclear power plants has been anticipated. Second Croatian-Slovenian NPP project will be based on the same principles the first one (NPP Krsko) was based on. Preconstruction investigation studies are performed at site Prevlaka on river Sava downstream of Zagreb. Licensing procedure has started with republic Urban countryside planning activities. Preconstruction activities are planned to be finished by the end of 1986. while the construction is expected to start during 1987. Parallel to investigation studies for NPP Prevlaka, evaluation of nuclear technology and reactor type is planned to be made. (author)

Some Major Issues Influencing Nuclear Energy Prospective

International Nuclear Information System (INIS)

Feretic, D.

2012-01-01

The presentation analyses some issues which are of particular importance for future nuclear power application. These include duration of uranium reserves and high level radioactive waste decay period in function of uranium reserves (determined, assumed and speculative) and type of fuel cycle used. Public acceptance during essential historical milestones of nuclear power use, influence of safety and compatibility evaluations, quantified risk, externalities and nuclear accidents. Short review of major accidents, causes, consequences, impact of LNT and hormesis hypothesis. Particular problem for future of nuclear power is potential shortage of experienced personnel due to long period without plants construction. To address some of problems which may face future investors a brief review of specific events experienced during construction of NPP Krsko is presented. Such events could be of interest to countries planning to construct nuclear power plant.(author).

Startup program after SGR and power increase

International Nuclear Information System (INIS)

Krajnc, B.; Dudas, M.; Spiler, J.; Novsak, M.

2000-01-01

NPP Krsko replaced steam generators during the outage 2000. Parallel with the steam generator replacement all required systems modifications to accommodate new steam generators into the existing plant (upper feed,..) and support plant power increase of 6.3%, have been implemented. During the years 1997 - 2000 all the required licensing, technical analyses and systems verifications to support such plant changes have been completed. One of the activities within this effort was also the preparation of a detailed Plant Startup Program, which was subject of licensing review and approval process. An integrated plant startup program was then developed based on the plant startup test program, performed regularly during plant startup after refueling and above-mentioned Plant Startup Program. These additional tests defined by the Startup Test Program have been required due to new steam generators, steam generator replacement and related modifications, and power increase from previous 1882 MWt to 2000 MWt. During the preparation period, a startup team was established and procedures were written. All procedures sensitive to the operation were validated on the plant specific simulator. This paper presents more about the Startup Test Program, analysis of its implementation, the results of some key tests as well as the lessons learned. (author)

Managing human performance

International Nuclear Information System (INIS)

Strucic, M.; Kavsek, D.

2004-01-01

Human performance remains a significant factor for management attention not only from a reactor safety perspective, but also from a financial one. Recent significant events analysis shows that human errors are still dominant causes and contributors to them. An analysis of significant events in nuclear industry occurred through 15-years period revealed that three of four significant events were triggered by human error, although the number of events have dropped by more than a factor of four. A number of human performance breakdowns occurred in the application of errorprevention techniques. These included a lack of pre-job briefs, inadequate turnover of tasks, ineffective use of peer checking, inadequate procedure adherence, and failure to apply a questioning attitude when unexpected changes were encountered in the task. Attempts by the industry to improve human performance have traditionally focused at the worker level. However, human error occurs within the context of the organization, which can either foster or resist human error. The greatest room for improvement lies not only in the continued improvement of front-line worker performance but more so in the identification and elimination of weaknesses in the organizational and managerial domains that contributes to worker performance at the job site. Based on mentioned analysis, other industrial sources and own operating experience, NPP Krsko is paying more attention to improve human performance among own as well as contractor workers. Through series of programs and activities, such as Reactivity Management Program, Safety Culture Program, Self-assessment Program, Corrective Action Program, Plant Performance Monitoring Program, developed in last few years, and through new procedures, written guides and publications, training and management efforts, number of human errors is going to be reduced. Involvement of higher levels of NPP Krsko organization in promotion and use of Human Performance techniques is

Assessing ‘New’ Greek cinema of the 1960s and the role of Theodoros Angelopoulos in Hellenic cinematography

Directory of Open Access Journals (Sweden)

Angelo Nicolaides

2012-01-01

Full Text Available In this review of Greek Cinema in in the 1960s special consideration is given to the issue of what constitutes ‘quality’ cinema with a Greek flavour. By examining the period in question as the locus of inquiry, namely the 1960s, the study identifies a number of factors which influenced the Greek filmmaking industry’s functional flexibility and seeks to answer a number of important questions. Specifically, the study investigated what constituted ‘New’ Greek cinema (NEK? How did it differ from ‘Old’ Greek cinema (PEK and what did the Hellenic state do to promote the cultural standing of cinema in its policies? What made films produced in Greece have a distinct Hellenic flavour whilst simultaneously appearing to be authentic? What was the role of Theodoros Angelopoulos inter alia in promoting Hellenic cinema and where does it stand today? The film identity of NEK and cinametic culture merge as interpretative meta-concepts evoked within the sociopolitical context of the 1960s.This concept-analytical type article was thus undertaken with a view to have a better grip on the attributes of NEK. With this as the main focus, the study, also sought to highlight the Greek film industry role during a period of rigid Military Junta control in Greece (1967-1974. This article will hopefully contribute towards both a better understanding of NEK, and a realisation that the film industry is more influential in moulding society than is sometimes believed.

Contribution of Nuclear Training Centre in Ljubljana to Training and Information in the Area of Nuclear Technology

International Nuclear Information System (INIS)

Stritar, A.

1998-01-01

Nuclear Training Centre in Ljubljana ia a part of the Jozef Stefan Institute. The paper presents its main activities, which consist of training for NPP Krsko staff, training in the area of radiation protection, organization of international training courses and public information. NPP Krsko personnel obtains initial technical training at our training centre. We are also offering training courses and licensing for people working with radioactive substances in medicine, industry and science. We are internationally recognized training centre for organization of regional and interregional courses and meeting. Our fourth activity is public information. We are visited by around 7000 students per year and answer to every question about nuclear energy. (author)

Public opinion about nuclear energy. Year 2006 poll

International Nuclear Information System (INIS)

Istenic, R.; Jencic, I.; Tkavc, M.

2006-01-01

Public information, one of the important activities of the Nuclear Training Centre Milan Copic at the Jozef Stefan Institute in Ljubljana, is focused on youngsters. Almost one half of every generation of schoolchildren in Slovenia is informed on nuclear energy by live lectures, exhibition, publications and laboratory demonstrations. To measure the opinion of youngsters about nuclear power and get a feed-back for our activities about 1000 youngsters are polled every year since 1993 using the same basic set of questions. Continued operation of the NPP Krsko is supported by 76% of youngsters in Slovenia (slightly positive trend from the last year's 71%). Opposition to NPP Krsko operation remains low. (author)

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

Use of GOTHIC Code for Assessment of Equipment Environmental Qualification

International Nuclear Information System (INIS)

Cavlina, N.; Feretic, D.; Grgic, D.; Spalj, S.; Spiler, J.

1996-01-01

Environmental qualification (EQ) of equipment important to safety in nuclear power plants ensures its capability to perform designated safety function on demand under postulated service conditions, including harsh accident environment (e. g. LOCA, HELB). The computer code GOTHIC was used to calculate pressure and temperature profiles inside NPP Krsko containment during limiting LOCA and MSLB accidents. The results of the new best-estimate containment code are compared to the older CONTEMPT code using the same input data and assumptions. The predictions obtained by both codes are very similar. As a result of the calculation the envelopes of the LOCA and MSLB pressures and temperatures, as used in FSAR/USAR Chapter 6, can be used in EQ project. (author)

Expert software for accident identification

International Nuclear Information System (INIS)

Dobnikar, M.; Nemec, T.; Muehleisen, A.

2003-01-01

Each type of an accident in a Nuclear Power Plant (NPP) causes immediately after the start of the accident variations of physical parameters that are typical for that type of the accident thus enabling its identification. Examples of these parameter are: decrease of reactor coolant system pressure, increase of radiation level in the containment, increase of pressure in the containment. An expert software enabling a fast preliminary identification of the type of the accident in Krsko NPP has been developed. As input data selected typical parameters from Emergency Response Data System (ERDS) of the Krsko NPP are used. Based on these parameters the expert software identifies the type of the accident and also provides the user with appropriate references (past analyses and other documentation of such an accident). The expert software is to be used as a support tool by an expert team that forms in case of an emergency at Slovenian Nuclear Safety Administration (SNSA) with the task to determine the cause of the accident, its most probable scenario and the source term. The expert software should provide initial identification of the event, while the final one is still to be made after appropriate assessment of the event by the expert group considering possibility of non-typical events, multiple causes, initial conditions, influences of operators' actions etc. The expert software can be also used as an educational/training tool and even as a simple database of available accident analyses. (author)

Simulations and field tests of a reactor coolant pump emergency start-up by means of remote gas units

International Nuclear Information System (INIS)

Omahen, P.; Gubina, F.

1992-01-01

The problem of the reactor coolant pump start-up in case of emergency by means of remote gas power plant units was analyzed. In this paper a simulation model is developed which enabled a detailed simulation of the transient process occurring at the start-up. The start-up of the RCP motor set was simulated in case of available one and two gas units. The field tests were performed and the measured variable values complied well with the simulation results. Two gas units have been determined as a safe start-up scheme of the RCP motor set considering for safety reasons accepted busbars and motor protection settings. A derived model for deep rotor bars was experimentally confirmed as effective means for the RCP motor set start-up transient simulation. Start-up procedures have been designed and adopted to the safety procedures of the Nuclear Power Plant Krsko

Example of severe accident management guidelines validation and verification using full scope simulator

International Nuclear Information System (INIS)

Krajnc, B.; Basic, I.; Spiler, J.

2001-01-01

The purpose of Severe Accident Management Guidelines (SAMG) is to provide guidelines to mitigate and control beyond design bases accidents. These guidelines are to be used by the technical support center that is established at the plant within one hour after the beginning of the accident as a technical support for the main control room operators. Since some of the accidents can progress very fast there are also two guidelines provided for the main control room operators. The first one is to be used if the core damage occurs and the TSC is not established yet and the second one after technical support center become operational. After SG replacement and power uprate in year 2000, NPP Krsko developed Rev.1 of these procedures, which have been validated and verified during one-week effort. Plant specific simulator capable of simulating severe accidents was extensively used.(author)

DTK C/Fortran Interface Development for NEAMS FSI Simulations

Energy Technology Data Exchange (ETDEWEB)

Slattery, Stuart R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lebrun-Grandie, Damien T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-09-19

This report documents the development of DataTransferKit (DTK) C and Fortran interfaces for fluid-structure-interaction (FSI) simulations in NEAMS. In these simulations, the codes Nek5000 and Diablo are being coupled within the SHARP framework to study flow-induced vibration (FIV) in reactor steam generators. We will review the current Nek5000/Diablo coupling algorithm in SHARP and the current state of the solution transfer scheme used in this implementation. We will then present existing DTK algorithms which may be used instead to provide an improvement in both flexibility and scalability of the current SHARP implementation. We will show how these can be used within the current FSI scheme using a new set of interfaces to the algorithms developed by this work. These new interfaces currently expose the mesh-free solution transfer algorithms in DTK, a C++ library, and are written in C and Fortran to enable coupling of both Nek5000 and Diablo in their native Fortran language. They have been compiled and tested on Cooley, the test-bed machine for Mira at ALCF.

Matematikaoktatás a bolognai típusú gazdasági képzésekben (Maths instruction in Bologna-type economics tuition)

OpenAIRE

Kánnai, Zoltán; Pintér, Miklós; Tasnádi, Attila

2010-01-01

A gazdálkodási és közgazdasági alap- és mesterszakok tanterveiben számos matematikai tárgy szerepel. A kétciklusú bolognai képzésre történő áttérés Európa-szerte igényelte a matematikaoktatás szerkezetének, mennyiségének és mélységének újragondolását a gazdálkodási és közgazdasági képzési területeken. Mivel az átállás országonként és intézményenként párhuzamosan és jelentős mértékben egymástól függetlenül ment végbe, egyetemenként számos eltérő megoldással találkozhatunk. Az egyetemek operatí...

Radioactive Waste Repositories and Incentives to Local Communities

International Nuclear Information System (INIS)

Knapp, A.; Medakovic, S.

2008-01-01

Public acceptance of radioactive waste (RW) repository depends on various and often community-specific factors. Although radiological risk from a properly constructed low and intermediate level waste (LILW) repository is practically negligible, routine safety considerations will favor low populated areas and therefore probably underdeveloped communities. Repository acceptance in such communities is more likely to be facilitated by prospective benefits to local economy, such as infrastructure development and increased employment, as well as by dedicated financial incentives to the community. Direct financial compensation to the local community for acceptance of the repository has been considered in some documents in countries experienced in RW management, but it has not become a widely accepted practice. In Croatia, a possibility for such compensation is mentioned in the land use plan in conjunction with the prospective RW repository site. In Slovenia, the government has already specified the annual amount of 2.33 million euro as a compensation for 'limited land use' to be shared by local communities in the vicinity of the planned LILW repository during its operation. Applicability of the Slovenian compensations to the prospective joint Slovenian-Croatian repository is not yet clear, at least in the aspect of joint funding. The joint Slovenian-Croatian Decommissioning and LILW and SF management program for NPP Krsko from 2004 did conservatively include the compensations into the repository cost estimates, but that might not be retained in subsequent revisions of the Program. According to the agreement between governments of Slovenia and Croatia on the Nuclear power plant Krsko, Croatian side has no obligations to participate in 'public expenditures' introduced after the agreement, as would be the case of community compensations for LILW repository in Slovenia. Before further decisions on joint NPP Krsko waste management are made, including the issue of LILW

Science Information Centre and Nuclear Library of 'Jozef Stefan' Institute, Ljubljana, Slovenia

International Nuclear Information System (INIS)

Stante, A.; Smuc, S.

2006-01-01

The 'Jozef Stefan' Institute Science Information Centre is the central Slovene physics library and one of the largest special libraries in Slovenia. Our collection covers the fields of physics, chemistry, biochemistry, electronics, information science, artificial intelligence, energy management, environmental science, material science, robotics etc. The Nuclear Library at the Reactor Centre Podgorica is a part of the Science Information Centre. It collects and keeps literature from the field of reactor and nuclear energy and provides information to scientists employed at the Reactor Centre and users from the Nuclear Power Plant Krsko as well as other experts dealing with nuclear science and similar fields. The orders subscribed are sent by the Science Information Centre to other libraries included in inter-library lending in Slovenia and abroad. (author)

Hydrogen behaviour in PWR containment evaluated with MAAP4.0.5

International Nuclear Information System (INIS)

Bilic-Zabric, T.; Basic, I.; Spiler, J.

2004-01-01

The possible impacts of the non-uniform hydrogen distribution and the consequent fast burning should be assessed in the light of newer research information on hydrogen management. The review should include the hydrogen source term, both for the in-vessel and ex-vessel period, and investigate the potential effects on the hydrogen management strategy. NPP Krsko will repeat MAAP 4.0.5 calculation for the most important Rx vessel failure sequences taken from Individual Plant Examination Project (with molten core-concrete interaction (MCCI) and with no MCCI) including wet cavity strategy. Mass and energy gases releases of analyzed sequences will be used to assess the non-uniform hydrogen distribution and the consequent fast burning by GOTHIC 7.1 (3-D).(author)

Use of sensitivity, uncertainty and data adjustment analysis to improve nuclear data

Energy Technology Data Exchange (ETDEWEB)

Kodeli, I [CEA-Centre d' Etudes de Saclay, SERMA/LEPP, Gif sur Yvette (France); Sartori, E [OECD/ NEA Data Bank, Issy-les-Moulineaux (France); Remec, I [Inst. Jozef Stefan, Ljubljana (Slovenia)

1992-07-01

Sensitivity and adjustment analysis provide some valuable information about the radiation transport calculations. Together they give us a clear insight into the importance of different calculational parameters and tell us how much we can trust our result. Without this information the calculation cannot be considered as comprehensive. On the other hand the adjustment permits the improvement of our data base and thus reduces the uncertainty of our target quantities for a range of specific applications. With the objective to validate the methodology used in the reactor shielding analysis, these techniques were applied to PWR power plants, manufactured by EDF (52 capsules analysed in France) and Westinghouse (capsule and cavity dosimetry for the Krsko NPP in Slovenia), as well as to the ASPIS benchmark experiment. (author)

Deterministic analysis of mid scale outdoor fire

International Nuclear Information System (INIS)

Vidmar, P.; Petelin, S.

2003-01-01

The idea behind the article is how to define fire behaviour. The work is based on an analytical study of fire origin, its development and spread. Mathematical fire model called FDS (Fire Dynamic Simulator) is used in the presented work. A CFD (Computational Fluid Dynamic) model using LES (Large Eddie Simulation) is used to calculate fire development and spread of combustion products in the environment. The fire source is located in the vicinity of the hazardous plant, power, chemical etc. The article presents the brief background of the FDS computer program and the initial and boundary conditions used in the mathematical model. Results discuss output data and check the validity of results. The work also presents some corrections of the physical model used, which influence the quality of results. The obtained results were discussed and compared with the Fire Safety Analysis report included in the Probabilistic Safety Assessment of Krsko nuclear power plant. (author)

Does Dual Ownership of Waste Imply a Regional Disposal Approach?

International Nuclear Information System (INIS)

Mele, I.

2006-01-01

The construction of the Nuclear Power Plant Krsko, being located in Slovenia near the Slovenian-Croatian border, was a joint investment by Slovenia and Croatia, two republics of the former Yugoslavia. The plant was completed in 1981 and the commercial operation started early in 1983. The obligations and rights of both investors during the construction and operation were specified in two bilateral contracts signed in 1974 and 1982. These contracts were fairly detailed on construction, operation and exploitation of the nuclear power plant (NPP), but they said very little about future nuclear liabilities. The electricity production was equally shared between the two countries and both parties participated in management of the NPP. In 1991, after Slovenia and Croatia became two independent countries, the agreement on the ownership and exploitation of the NPP Krsko was re-negotiated and a new contract signed in 2003. By the new contract the decommissioning and the disposal of spent fuel (SF) as well as low and intermediate level waste (LILW) is the responsibility of both parties, and the financial resources for covering these liabilities should be equally provided. Regardless of shared ownership of waste, the agreement opts for a single disposal solution for LILW as well as for SF, but the details are left open. More clear elaboration of these responsibilities is given in the programme of the decommissioning and disposal of radioactive waste from the NPP which was jointly prepared by the Slovenian and Croatian waste management organisations in 2004. The programme is clearly opting for only one repository for LILW and one repository for spent fuel, which can be located either in Slovenia or Croatia. Irrespective of the country where such a repository will be sited, dual ownership of waste opens up another dimension of such a solution: will such a repository be regarded as a national facility or as a regional or multinational facility? Both options-national and regional

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

International Nuclear Information System (INIS)

1999-01-01

operation of the units. 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 definition, developed by IAEA and presented in INSAG-8 ' was used for analysis performance. Based on this analysis a set of activities was developed, to ensures further plant operation with the necessary safety level. The measures were combined in a program called Complex program for modernization of units 1-4. The implementation of the program is foreseen for a period of four next fuel cycles and started at the beginning of 1998. In respond to the requirements for the content of this paper a detailed description of the current status of resolving of the safety issues, classified by IAEA in TECDOC 640 is presented. The whole process of safety evaluation, short and long term safety improvements presents in a systematical manner the efforts of the Government of Bulgaria, NEK Ltd and KNPP to operate these units with due respect of their nuclear safety responsibility according to Nuclear Safety Convention signed at Vienna in 1994 and ratified by Bulgarian Parliament in 1995

Tritium Measurements in Slovenia - Chronology Till 2004

International Nuclear Information System (INIS)

Logar, Jasmina Kozar; Vaupotic, Janja; Kobal, Ivan

2005-01-01

Almost all the analyses of tritium in Slovenia have been performed by the tritium laboratory at the Jozef Stefan Institute. Nearly 90 % of its measurements have been covered by two national programs, both approved by the Slovenian Nuclear Safety Administration: the radioactive monitoring program in the environs of Krsko Nuclear Power Plant (KNPP) and the program of global radioactive contamination monitoring in the environment. These programs include samples of groundwaters, surface waters, precipitation and drinking waters, as well as liquid and gaseous effluents from KNPP. Tritium was determined in some research projects and in hydrological studies of thermal waters, groundwater and coalmine waters. Tritium in the Karst region was mapped as well as the springs of entire territory of Slovenia. Around 5500 samples have been analyzed up to 2004

Developement of multimedial web portal for PLD course tutorials

OpenAIRE

Fíla, Lukáš

2009-01-01

Tato práce popisuje principy tvorby statických webových stránek a nejpoužívanější metody používané při tvorbě stránek dynamických. Seznámíte se s jazyky HTML, CSS, PHP, JavaScript a databázemi MySQL. Dále jsou zpracovány základní informace o problematice programovatelných logických obvodů PLD a FPGA. This paper describes the principles of the creation of static Web pages and the most common methods used in creating dynamic pages. Acquainted with the languages of HTML, CSS, PHP, JavaScript ...

High acceptance of nuclear power by youngsters in Slovenia

International Nuclear Information System (INIS)

Stritar, Andrej; Istenic, Radko

2001-01-01

(question about disadvantages of nuclear power and last question). Obviously on-going modernisation of the Nuclear power plant Krsko (steam generator replacement), which was quite substantially publicised, did not have any negative influence to public opinion. Public information remains to be important to keep the favourable public attitude and should be intensified in the radioactive waste area

Changing perception about nuclear power in Slovenia in the changing political climate

International Nuclear Information System (INIS)

Stritar, Andrej; Istenff, Radko

1998-01-01

Public opinion about nuclear energy and in particular about the Nuclear Power Plant Krsko has experienced some fluctuations during last years. There were periods when attacks in media by the opponents were very heavy, which resulted also in a more negative public opinion about this kind of energy production. In the year 1995 and 1996 there was a very strong anti nuclear motion initiated by opponents. They wanted to organize a national referendum for the premature closure of the NPP Krsko. The motion was quite a big disaster, since they have managed to collect only about 6 of needed 40.000 signatures for the support of the referendum. After that there were very few open attacks against nuclear energy present in media. At the Nuclear Training Centre in Ljubljana we are continuing our long-term program of public education about nuclear energy. Elementary and High schools have a permanent invitation to visit us. We receive about 7000 students per year together with about 300 teachers. They all have opportunity to listen to the lecture about nuclear energy or about radioactive waste and to visit our permanent exhibition. In June 1997 we have repeated the pool among visitors, which was conducted already in years 1990, 91, 92, 93 and 1995. In the paper we will compare the results and try to draw some conclusions. Nuclear power is not the largest headline in Slovenia anymore. The influence of that can be seen also on public perception. Our poll of young people shows their better and more favorable perception of this way of energy production than in the past

Nuclear energy as a part of national energy strategy of Slovenia

International Nuclear Information System (INIS)

Stritar, A.

2002-01-01

Slovenian National Committee of the World Energy Council has prepared the draft of the National Energy Strategy of Slovenia for next 20 years. Following are the main conclusions of the nuclear part of proposed National Energy Strategy of Slovenia: NPP Krsko should operate until the end of its lifetime; possibilities for the extension of the operating lifetime of NPP Krsko should be investigated; possible new nuclear units of smaller size should be seriously considered after 2010; advantage should be taken of established knowledge basis and infrastructure and the option for construction of additional nuclear unit for production for European electricity market should be kept open; the site for the low and intermediate waste repository should be found as soon as possible, while the spent nuclear fuel should be stored temporarily until some regional solutions are available.(author)

Influence of reactor vessel nodalization in the coupled code analysis of Asymmetric Main Feedwater Isolation

International Nuclear Information System (INIS)

Bencik, V.; Feretic, D.; Grgic, D.

2001-01-01

Asymmetric Main Feedwater Isolation (AMFWI) transient in one Steam Generator (SG) for NPP Krsko using RELAP5 standalone code and coupled code RELAP5- QUABOX/CUBBOX (R5QC) was analyzed. In the RELAP5 standalone calculation, a point kinetics model was used, while in the coupled code a three-dimensional (3D) neutronics model of QUABOX with different RELAP5 nodalization schemes of reactor vessel was used. Both code versions use best-estimate thermal-hydraulic system code for all components in the plant and include realistic description of plant protection and control systems. Two different types of calculations were performed: with and without automatic control rod system available. The AMFWI transient causes the great asymmetry of the transferred heat in the SGs and subsequently the asymmetry of the power produced across the core due to different reactivity feedback resulting from the thermal-hydraulic channels assigned to different loops. The work presented in the paper is a part of validation of the 3D coupled code R5QC in the analysis of asymmetric transients.(author)

Krsko NPP ecological information system

International Nuclear Information System (INIS)

Kovac, A.; Breznik, B.

1996-01-01

The Ecological Information System was developed and is used for continuous data collecting from different measuring points as well as for dose calculation in case of emergency. The system collects all the data which are continuously measured in the environment or might have influence to the environment or are necessary for evaluation of impact to the environment. (author)

NPP Krsko secondary side analysis

International Nuclear Information System (INIS)

Fabijan, Lj.

1987-01-01

The purpose of this work is to analyze secondary side thermohydraulics response on steam generator tube plugging in order to ensure nominal NPP power. We had established that the additional opening of the governing valve No. 3 and 4 can compensate pressure drop caused by steam generator tube plugging. Two main steam flows with four governing valves were simulated. Steam expansion in turbine and feed water system was modeled separately. All important process point and steam moisture changes impact on nominal NPP power were analysed. (author)

Report of the technical committee meeting 1997 annual workshop on ASSET experience and feedback

International Nuclear Information System (INIS)

1997-01-01

Papers and presentations were made by all participating countries and provided a wide range of perspectives on the use of the ASSET methodology. Generally, the views expressed were positive, however, there were comments on areas were the service could be improved or enhanced. The workshop was divided into three task groups to analyze the self-assessments conducted at Krsko NPP, Slovenia; Dukovany NPP, Czech Republic; and Balakovo NPP, Russian Federation. In addition, they were asked to comment on the recommendations on the ASSET service made by the Consultants' Meeting of 26-30 August 1996 on ''Performance of the IAEA programme on Operational Safety Services''. A presentation was made by Mr. B. Thomas to remind delegates of the ASSET methodologies, and Mr. V. Sivokon demonstrated the latest developments of computer software available for assisting in the plant Self-Assessment process. Refs, figs, tabs

Report of the technical committee meeting 1997 annual workshop on ASSET experience and feedback

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

Papers and presentations were made by all participating countries and provided a wide range of perspectives on the use of the ASSET methodology. Generally, the views expressed were positive, however, there were comments on areas were the service could be improved or enhanced. The workshop was divided into three task groups to analyze the self-assessments conducted at Krsko NPP, Slovenia; Dukovany NPP, Czech Republic; and Balakovo NPP, Russian Federation. In addition, they were asked to comment on the recommendations on the ASSET service made by the Consultants` Meeting of 26-30 August 1996 on ``Performance of the IAEA programme on Operational Safety Services``. A presentation was made by Mr. B. Thomas to remind delegates of the ASSET methodologies, and Mr. V. Sivokon demonstrated the latest developments of computer software available for assisting in the plant Self-Assessment process. Refs, figs, tabs.

Reactor core design calculations and fuel management in PWR; Izracun projekta sredice in upravljanja z forivom tlacnovodnega reaktorja

Energy Technology Data Exchange (ETDEWEB)

Ravnik, M [Institut Jozef Stefan, Ljubljana (Yugoslavia)

1987-07-01

Computer programs and methods developed at J. Stefan Institute for nuclear core design of Krsko NPP are treated. development, scope, verification and organisation of core design procedure are presented. The core design procedure is applicable to any NPP of PWR type. (author)

Conceptions of Landscape-Ecological Relevance Emerged in the Czech Botany during the Second Half of Twentieth Century

Directory of Open Access Journals (Sweden)

Kovář Pavel

2015-12-01

Full Text Available This paper summarizes those substantial theoretical concepts or methods for applications within interdisciplinary or practical uses published by Czech autors (geobotanists = ecological botanists, plant ecologists and ecophysiologists during the second half of the 20th century, that were internationally cited. All selected thematical clusters are of landscape-ecological relevance through various contexts. Examples include the concepts of (potential reconstructed vegetation in maps (R. Neuhäusl, Z. Neuhäuslová, linear vegetation features (corridors in landscape and deductive classification of vegetation (K. Kopecký, analysis of soil seed bank (Z. Kropáč, dependency of macrophyte plant stands on ecodynamics (S. Hejný, dynamic periodicity in segetal vegetation (Z. Kropáč, E. Hadač, S. Hejný, anemo-orographic system explaining species richness in mountain regions (J. Jeník, productivity in grassland ecosystems (M. Rychnovská, J. Květ, elementary landscape units based on homogenity and potential vegetation (E. Hadač, landscape dispensation phenomena (V. Ložek, afforestation of coastal sandy dunes – the Netherlands, and polluted areas - the Czech Republic (J. Fanta, invasive plants and invasions into landscapes (M. Rejmánek.

Assessment of SFR Wire Wrap Simulation Uncertainties

Energy Technology Data Exchange (ETDEWEB)

Delchini, Marc-Olivier G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Popov, Emilian L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Pointer, William David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Swiler, Laura P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-09-30

Predictive modeling and simulation of nuclear reactor performance and fuel are challenging due to the large number of coupled physical phenomena that must be addressed. Models that will be used for design or operational decisions must be analyzed for uncertainty to ascertain impacts to safety or performance. Rigorous, structured uncertainty analyses are performed by characterizing the model’s input uncertainties and then propagating the uncertainties through the model to estimate output uncertainty. This project is part of the ongoing effort to assess modeling uncertainty in Nek5000 simulations of flow configurations relevant to the advanced reactor applications of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. Three geometries are under investigation in these preliminary assessments: a 3-D pipe, a 3-D 7-pin bundle, and a single pin from the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility. Initial efforts have focused on gaining an understanding of Nek5000 modeling options and integrating Nek5000 with Dakota. These tasks are being accomplished by demonstrating the use of Dakota to assess parametric uncertainties in a simple pipe flow problem. This problem is used to optimize performance of the uncertainty quantification strategy and to estimate computational requirements for assessments of complex geometries. A sensitivity analysis to three turbulent models was conducted for a turbulent flow in a single wire wrapped pin (THOR) geometry. Section 2 briefly describes the software tools used in this study and provides appropriate references. Section 3 presents the coupling interface between Dakota and a computational fluid dynamic (CFD) code (Nek5000 or STARCCM+), with details on the workflow, the scripts used for setting up the run, and the scripts used for post-processing the output files. In Section 4, the meshing methods used to generate the THORS and 7-pin bundle meshes are explained. Sections 5, 6 and 7 present numerical results

Assessment of Safety Culture

International Nuclear Information System (INIS)

Bilic Zabric, T.; Kavsek, D.

2006-01-01

A strong safety culture leads to more effective conduct of work and a sense of accountability among managers and employees, who should be given the opportunity to expand skills by training. The resources expended would thus result in tangible improvements in working practices and skills, which encourage further improvement of safety culture. In promoting an improved safety culture, NEK has emphasized both national and organizational culture with an appropriate balance of behavioural sciences and quality management systems approaches. In recent years there has been particular emphasis put on an increasing awareness of the contribution that human behavioural sciences can make to develop good safety practices. The purpose of an assessment of safety culture is to increase the awareness of the present culture, to serve as a basis for improvement and to keep track of the effects of change or improvement over a longer period of time. There is, however, no single approach that is suitable for all purposes and which can measure, simultaneously, all the intangible aspects of safety culture, i.e. the norms, values, beliefs, attitudes or the behaviours reflecting the culture. Various methods have their strengths and weaknesses. To prevent significant performance problems, self-assessment is used. Self-assessment is the process of identifying opportunities for improvement actively or, in some cases, weaknesses that could cause more serious errors or events. Self-assessments are an important input to the corrective action programme. NEK has developed questionnaires for safety culture self-assessment to obtain information that is representative of the whole organization. Questionnaires ensure a greater degree of anonymity, and create a less stressful situation for the respondent. Answers to questions represent the more apparent and conscious values and attitudes of the respondent. NEK proactively co-operates with WANO, INPO, IAEA in the areas of Safety Culture and Human

Governance of electrotechnical standardisation in Europe

NARCIS (Netherlands)

H.J. de Vries (Henk)

2015-01-01

markdownabstract__Abstract__ This report provides recommendations about the governance of electrotechnical standardisation in Europe to seven independent National Committees: DKE (Germany), Electrosuisse (Switzerland), OVE (Austria), NEC (the Netherlands), NEK (Norway), SEK (Sweden), and SESKO

Daňový systém Francouzské republiky s akcentem na přímé daně

OpenAIRE

Chocholáč, Jan; Průša, Petr

2016-01-01

Článek se zabývá daňovým systémem Francouzské republiky s důrazem na přímé daně, které se skládají z daně z příjmu a daně z nemovitostí. Tento článek podrobně popisuje daň příjmu fyzických osob, daň z příjmu právnických osob, daň z nemovitosti, daň dědickou a daň darovací. Article deals with the tax system of the French Republic with emphasis on direct taxes which consists of income taxes and property taxes. The article described in detail the tax on personal income tax, corporate income t...

Kuidas Sander Saarmets kosmosest maailma vallutama kipub / Moon Meier

Index Scriptorium Estoniae

Meier, Moon

2007-01-01

Eesti Muusika- ja Teatriakadeemias elektronmuusika erialal õppivast Sander Saarmetsast kui noorest heliloojast, kes on siiani oma nime teinud ulmemuusika ringkondades. Kommenteerivad sõber, muusik, ulmeplaatide boss Aivar Tõnso ja Muschraumi kitarrist Kaur Garšnek

Nuclear energy between science and public

Energy Technology Data Exchange (ETDEWEB)

Bobnar, B [Inst. Jozef Stefan, Ljubljana (Slovenia)

1992-07-01

The objective of the presented research was to establish the presence and the structure of nuclear energy as a theme in Slovenian mass media and at the same time to answer the question what chances an active Slovenian reader had in the year 1991 to either strengthen or change his opinion on nuclear power. Measurement and analysis of chosen relevant variables in 252 contributions in six Slovenian mass media publications in the year 1991 showed that the most frequent nuclear theme was decommissioning and closing down of a nuclear power plant. Other themes followed in the order of the frequency of appearance: nuclear energy as an economic issue, waste disposal, NPP Krsko operation, influence on health, information about events, seismic questions. The scientific theme - nuclear energy, was intensely represented in chosen Slovenian mass media publications in 1991. Common to all nuclear themes is that they were being presented from the political point of view. (author) [Slovenian] Prispevek s strani komunikoloskih raziskav osvetljuje nekatere dileme ob vstopanju stroke v svet mnozicnih medijev. Cilj raziskave je bil: ugotoviti prisotnost in strukturo jedrske energije kot teme v javnih pisnih medijih v letu 1991 ter oceniti, ali je imel povprecni bralec vsaj enega dnevnega casopisa moznost, da okrepi ali spremeni svoje mnenje o jedrski energiji. Merjenje in analiza relevantnih izbranih spremenljivk v 252 prispevkih v sestih slovenskih pisnih medijih sta pokazala, da je bila najpogostejsa jedrska tema zapiranje in razgradnja jedrskih elektrarn, sledili so ekonomski vidiki jedrske energije, vprasanja, povezana s skladiscenjem in odlagaliscem radioaktivnih odpadkov, delovanje NE Krsko, vpliv jedrske energije na zdravje, informacije o nezgodah, seizmoloska vprasanja. Strokovna tema - jedrska energija, je bila intenzivno predstavljena v slovenskih pisnih medijih v letu 1991, vendar prevladujoce s politicnega zornega kota. (author)

Fotbal na malířském plátně v počátcích moderního umění

Czech Academy of Sciences Publication Activity Database

Winter, Tomáš

2014-01-01

Roč. 36, č. 5 (2014), s. 21-24 ISSN 0418-5129 Institutional support: RVO:68378033 Keywords : Jiránek, Miloš * Naske, František Xaver * Preisler, Jan Subject RIV: AL - Art, Architecture, Cultural Heritage

Evaluation of consequences and risks in Slovenia

International Nuclear Information System (INIS)

Susnik, J.

1996-01-01

The paper describes the evaluation of nuclear power plant accident consequences and risks using probabilistic safety codes during the last 12 years at the J. Stefan Institute. They cover classic individual and population risk studies due to assumed potential severe accident scenarios, prediction and estimation of Chernobyl accident consequences, the optimization of emergency countermeasures at the Krsko site, where the 632 MWe Westinghouse PWR NPP went into commercial operation on January 1983, and the ranking of population risk within the public debate in connection with the civil initiative to close the NPP Krsko. We report on the initial use of the CRAC2 code in 1984 and later, when it was first applied for the study of population risk in the area of the second planned Slovenian-Croatian NPP for the Prevlaka site. The study was completed a few weeks before the Chernobyl accident in April 1986. Risk evaluation was also included in the analysis of nuclear safety at the NPP Krsko during the war for Slovenia's independence in 1991. We report on the (CRAC2) analyses of the Chernobyl accident: on initial estimation of the maximal potentially expected consequences in Slovenia, on the effect of the radioactive cloud rise on the consequences relatively close to the NPP; on the further research after the detailed information on the radioactivity release and on the air masses movement were published; then the cloud activity which moved towards Slovenia was assessed and the expected consequences along its path were calculated. As the calculated integral individual exposure to the I 131 inhalation and the ground Cs 137 contamination matched with the measurements in Ljubljana and with the UNSCEAR 1988 data, our reliance on the CRAC2 code and on its ancestors is high. We report on the analyses, performed by the CRAC2 code and since 1993 also by the PC COSYMA code, related to the countermeasure effects. The consequences studied were extended to late health effects. We analyzed

Group constants calculation for fuel assemblies containing burnable absorbers; Prorachun grupnih konstanti gorivnih elemenata koji sadrzhe sagorive apsorbere

Energy Technology Data Exchange (ETDEWEB)

Petrovic, B [Institut Rudjer Boskovic, Zagreb (Yugoslavia); Pevec, D [Elektrotehnicki Fakultet, Zagreb Univ. (Yugoslavia); Urli, N; Shmuc, T [Institut Rudjer Boskovic, Zagreb (Yugoslavia)

1988-07-01

The upgrading of the computer code package PSU-LEOPARD/MCRAC is described. The upgraded package enables modelling of fuel assemblies containing burnable absorbers in the form of borosilicate glass rodlets, or, integral fuel burnable absorbers. The package is tested using the NPP Krsko core data. (author)

Nuclear and radiation safety in Slovenia. Annual report 2001

International Nuclear Information System (INIS)

Janzekovic, H.

2002-01-01

The Slovenian Nuclear Safety Administration (SNSA) has prepared a Report on Nuclear and Radiation Safety in Slovenia for 2001 as a regular form of reporting to the citizens of the Republic of Slovenia on the activities related to the nuclear fuel cycle and the use of the ionising sources. The report has been prepared in collaboration with the Health Inspectorate of the Republic of Slovenia (HIRS), the Administration for Civil Protection and Disaster Relief (ACPDR), the Pool for Assurance and Reinsurance of Liability for Nuclear Damage and the Pool for Decommissioning of the NPP Krsko and for the Radwaste Disposal from the NPP Krsko. The reports of the Agency for Radioactive Waste Management (ARAO), the Institute of Oncology, the Department of Nuclear Medicine of the Medical Centre Ljubljana and the technical support organisations are also included. The SNSA made no crucial modifications to the reports of the above mentioned institutions. The modifications were made just facilitate a reading of the reports. (author)

Report on nuclear and radiation safety in Slovenia in 2001

International Nuclear Information System (INIS)

Janzekovic, H.

2002-01-01

The Slovenian Nuclear Safety Administration (SNSA) has prepared a Report on Nuclear and Radiation Safety in Slovenia for 2001 as a regular form of reporting to the citizens of the Republic of Slovenia on the activities related to the nuclear fuel cycle and the use of the ionising sources. The report has been prepared in collaboration with the Health Inspectorate of the Republic of Slovenia (HIRS), the Administration for Civil Protection and Disaster Relief (ACPDR), the Pool for Assurance and Reinsurance of Liability for Nuclear Damage and the Pool for Decommissioning of the NPP Krsko and for the Radwaste Disposal from the NPP Krsko. The reports of the Agency for Radioactive Waste Management (ARAO), the Institute of Oncology, the Department of Nuclear Medicine of the Medical Centre Ljubljana and the technical support organisations are also included. The SNSA made no crucial modifications to the reports of the above mentioned institutions. The modifications were made just facilitate a reading of the reports.

The effect of feeding wheat varieties with different grain pigmentation on growth performance, texture, colour and meat sensory traits of broiler chickens

Directory of Open Access Journals (Sweden)

Ondřej Šťastník

2017-01-01

Full Text Available The feeding effect of of three spring wheat genotypes (Vánek, Konini and UC66049 with different grain colour on growth performance, body composition and meat quality parameters of broiler chickens was tested. Ninety chickens were divided into three groups (control, Konini and UC with 30 chickens in each. The tested genotypes were compares with standard variety Vánek (control with common (red grain colour. The two experimental groups received feed mixtures containing 38.2% of wheats with different grain colour: groups Konini (n = 30 and UC (n = 30 with. The third group (n = 30 had 38.2% of common wheat Vánek cultivar (Control group. The live weight of chickens between the experimental groups and control group was not significant different, as well as body composition and chemical analysis of breast and thigh meat of chickens. The feeding of wheat with different grain colour had no effect on performance parameters of broiler chickens. Breast meat tenderness according to the Razor Blade Shear Force was higher in control group against experimental groups. The colour change was not significantly different in all coordinates. pH values (measured after 1-hour post mortem were found significantly higher in the group fattening with Konini wheat than control and UC groups. Chickens meat from the experimental group was characterised by steady overall quality. The effect of various feeding had no effect on meat quality in terms of relevance to consumers.

Co-operation between Slovenia and Croatia in the low- and intermediate level radioactive waste repository project

International Nuclear Information System (INIS)

Schaller, A.; Lokner, V.; Subasic, D.; Zeleznik, N.; Mele, I.; Tomse, P.

2001-01-01

The paper describes the LILW repository project development in Slovenia and Croatia from the viewpoint of co-operation of national agencies for radioactive waste management - ARAO in Slovenia and APO in Croatia. The project performance, as well as the co-operation itself, are based on the fact that NPP Krsko, sited in Slovenia, is the joint venture facility of both countries, which are consequently obliged to find a proper solution for final disposal of operational and decommissioning radioactive waste generated by the plant. The main aspects of the project development in both countries, such as LILW repository site selection and characterisation, development of repository conceptual design, performance assessment/safety analysis procedures and public participation, are presented in the paper. Based on separate descriptions of the project development in Slovenia and Croatia respectively, the main aspects of co-operation between ARAO and APO are elaborated.(author)

Plaadid / Immo Mihkelson

Index Scriptorium Estoniae

Mihkelson, Immo, 1959-

2002-01-01

Uutest plaatidest Fairport Covention "House Full", Haven "Between the Senses", Orbital "Work 1989-2002", A "Hi-Fi Serious", Montell Jordan "Montell Jordan", bela Fleck & Flecktones "Live At The Quick", Angelique Kidjo "Black Ivory Soul", Nek "Le Cose Da Diffendere"

"Hingelindude" lend / Igor Garšnek

Index Scriptorium Estoniae

Garšnek, Igor, 1958-

2010-01-01

Tallinna Filharmoonia kontserdisarjas "Viva oratorio!" 2. novembril Tallinna Jaani kirikus toimunud Rein Rannapi koori-orkestriteose "Hingelinnud I" (tekst Indrek Hirv) esiettekandest. Esitasid ETV mudilaskoor, lastekoor ja vilislased ning Tallinna Kammerorkester Toomas Vavilovi dirigeerimisel, solistid Bonzo ja Kaisa Padur

Kõlarist Kõlarini / Igor Garšnek

Index Scriptorium Estoniae

Garšnek, Igor, 1958-

2011-01-01

6. oktoobril Mustpeade majas toimunud Margo Kõlari juubelikontserdist "Väikese Vankri vennaskond", kus esinesid Tallinna Kammerorkester Tõnu Kaljuste dirigeerimisel, ansamblid PaukenfEst, Heinavanker, Resonabilis, Vox Clamantis ja solistid

Erakust muusiku maja Jaapanis

Index Scriptorium Estoniae

1999-01-01

Väikesel kunstlikul neemel asuva maja eksterjöör koosneb lihtsatest valgetest pindadest, maja läänekülg avaneb Vaikse ookeani lahele. Interjöör on rikkaliku koloriidiga. Kavandas mehhiko arhitekt Ricardo Legorreta koos kolleegidega Kajiama Designist

Comparison of public exposures from different sources of radioactive contamination in recent years in Slovenia

International Nuclear Information System (INIS)

Vokal, B.; Krizman, M.

2003-01-01

In spite of that Slovenia is a small country it contains a considerable variety of radioactive sources, which cause radioactive contamination of the environment. These sources mostly belong to nuclear fuel cycle, as the Krsko Nuclear Power Plant, the Zirovski vrh Uranium Mine (in the decommissioning), the TRIGA Research Reactor and Central low and intermediate level radioactive waste storage. Some other technological enhanced natural radiation sources, for example, the Sostanj Thermal Power Plant have also an impact to the environment. The comparison of the public exposure due to various sources of radioactive releases to the exposure of a members of the public in Slovenia shows that the critical group in the vicinity of the Zirovski Vrh uranium mine is the most exposed one in Slovenia. The global contamination due to the Chernobyl accident and the past nuclear tests was estimated to be around 10 μSv in Slovenia while the estimated annual dose for all other radioactive facilities are in the order of magnitude of one μSv. In this review the releases from the hospitals are not reported but some studies showed that it is not negligible. (authors)

Plant host finding by parasitic plants: a new perspective on plant to plant communication.

Science.gov (United States)

Mescher, Mark C; Runyon, Justin B; De Moraes, Consuelo M

2006-11-01

Plants release airborne chemicals that can convey ecologically relevant information to other organisms. These plant volatiles are known to mediate a large array of, often complex, interactions between plants and insects. It has been suggested that plant volatiles may have similar importance in mediating interactions among plant species, but there are few well-documented examples of plant-to-plant communication via volatiles, and the ecological significance of such interactions has been much debated. To date, nearly all studies of volatile-mediated interactions among plant species have focused on the reception of herbivore-induced volatiles by neighboring plants. We recently documented volatile effects in another system, demonstrating that the parasitic plant Cuscuta pentagona uses volatile cues to locate its hosts. This finding may broaden the discussion regarding plant-to-plant communication, and suggests that new classes of volatile-meditated interactions among plant species await discovery.

Plant Host Finding by Parasitic Plants: A New Perspective on Plant to Plant Communication

OpenAIRE

Mescher, Mark C; Runyon, Justin B; De Moraes, Consuelo M

2006-01-01

Plants release airborne chemicals that can convey ecologically relevant information to other organisms. These plant volatiles are known to mediate a large array of, often complex, interactions between plants and insects. It has been suggested that plant volatiles may have similar importance in mediating interactions among plant species, but there are few well-documented examples of plant-to-plant communication via volatiles, and the ecological significance of such interactions has been much d...

National debate (Slovenia)

International Nuclear Information System (INIS)

Pecnik, Maks; Veselic, Miran

2003-01-01

The Governmental policies in the area of the safety of spent fuel management and of the safety of radioactive waste management are set in comprehensive nuclear legislation comprising of international agreements, domestic laws and regulations. In addition the government prepared several documents pertinent to the policy in the area of radioactive waste management. The most important are: a Strategy of Energy Use and Supply of Slovenia, adopted by the Slovene Parliament in 1996; a Decommissioning Plan for the Krsko NPP, produced and approved by the Government in September 1996; a Strategy for Long-term Spent Fuel Management,adopted by the Slovenian Government in 1996. The Strategy on Low and Intermediate Level Waste Management has been prepared by the Agency for Radioactive Waste Management. The document has been submitted to the Government for approval. According to the new Act on Ionising Radiation Protection and Nuclear Safety (2002) the National programme for radioactive waste and spent fuel management shall be adopted by the Parliament as a part of the national programme for the protection of the environment pursuant to the regulations on environmental protection. This National programme will substitute The Strategy for Long-term Spent Fuel Management and The Strategy on Low and Intermediate Level Waste Management. The technical groundwork for the National programme for radioactive waste and spent fuel management, together with a detailed description of the measures relating to the reduction of the occurrence of radioactive waste, to the treatment thereof prior to disposal and to its disposal, and the measures relating to the treatment and disposal of spent fuel, shall be carried out and communicated to the ministry competent for the environment by the ARAO Agency. The operative programmes within the national programme of the radioactive waste and spent fuel management shall be drawn up by the ARAO Agency adopted by the Government. The operative programmes shall

Nuclear energy between science and public

International Nuclear Information System (INIS)

Bobnar, B.

1992-01-01

The objective of the presented research was to establish the presence and the structure of nuclear energy as a theme in Slovenian mass media and at the same time to answer the question what chances an active Slovenian reader had in the year 1991 to either strengthen or change his opinion on nuclear power. Measurement and analysis of chosen relevant variables in 252 contributions in six Slovenian mass media publications in the year 1991 showed that the most frequent nuclear theme was decommissioning and closing down of a nuclear power plant. Other themes followed in the order of the frequency of appearance: nuclear energy as an economic issue, waste disposal, NPP Krsko operation, influence on health, information about events, seismic questions. The scientific theme - nuclear energy, was intensely represented in chosen Slovenian mass media publications in 1991. Common to all nuclear themes is that they were being presented from the political point of view. (author) [sl

Kolm tähelepanuväärset bibliograafiat / Tiina Ritson

Index Scriptorium Estoniae

Ritson, Tiina, 1955-

2011-01-01

Arvustus: Uku Masing 100 : bibliograafia 1923-2009 / koost. Anneli Sepp. Tartu : Ilmamaa, 2010. Voldemar Panso bibliograafia / koost. Katre Riisalu, Eha Garšnek, Mari Sibul. Tallinn : Eesti Draamateater, 2010. Pilv, Aare. Juhan Viidingu ja Jüri Üdi bibliograafia // Juhan Viiding, eesti luuletaja. Tartu, 2010.

Koeien met een glimlach op SMILE-bedrijven

NARCIS (Netherlands)

Smolders, E.A.A.

2006-01-01

Informatie over het SMILE-project (Sustainable Milk Initiative Launch in Europe), waarbij melkveehouders kijken op elkaars bedrijf en daarmee gestimuleerd worden om stalaanpassingen op het eigen bedrijf door te voeren, waarmee het aantal beschadigingen aan huid, hakken, knieën en nek bij hun koeien

Origin of brackish groundwater in a sandstone aquifer on Bornholm, Denmark

DEFF Research Database (Denmark)

Jørgensen, Niels Oluf; Heinemeier, Jan

2008-01-01

A multi-isotope approach in combination with hydrochemical data and borehole logging is applied to identify the source of brackish groundwater in a borehole in the well field of Neksø Municipal Waterworks in Bornholm, Denmark. The aquifer lithology consists of fractured Lower Cambrian sandstones...

‘Anders slapen’. Evaluatie van ‘anders slapen’: een pilotonderzoek naar het effect van ‘anders slapen’ bij spanningshoofdpijn op Kwaliteit van Leven en participatie.

NARCIS (Netherlands)

de Vlugt, Liesbeth

2014-01-01

Samenvatting Inleiding- (Spannings)hoofdpijn is een veelvoorkomend probleem dat van invloed is op de Kwaliteit van Leven (KvL) en participatie van mensen in het dagelijks leven. Cervicogene hoofdpijn is een vorm van spanningshoofdpijn, waarbij de oorzaak gelegen is in spanning in de nek. Elkhuizen

Operational experience feedback with precursor analysis

International Nuclear Information System (INIS)

Koncar, M.; Ferjancic, M.; Muehleisen, A.; Vojnovic, D.

2003-01-01

Experience of practical operation is a valuable source of information for improving the safety and reliability of nuclear power plants. Operational experience feedback (Olef) system manages this aspect of NPP operation. The traditional ways of investigating operational events, such as the root cause analysis (RCA), are predominantly qualitative. RCA as a part of the Olef system provides technical guidance and management expectations in the conduct of assessing the root cause to prevent recurrence, covering the following areas: conditions preceding the event, sequence of events, equipment performance and system response, human performance considerations, equipment failures, precursors to the event, plant response and follow-up, radiological considerations, regulatory process considerations and safety significance. The root cause of event is recognized when there is no known answer on question 'why has it happened?' regarding relevant condition that may have affected the event. At that point the Olef is proceeding by actions taken in response to events, utilization, dissemination and exchange of operating experience information and at the end reviewing the effectiveness of the Olef. Analysis of the event and the selection of recommended corrective/preventive actions for implementation and prioritization can be enhanced by taking into account the information and insights derived from Pasa-based analysis. A Pasa based method, called probabilistic precursor event analysis (PPE A) provides a complement to the RCA approach by focusing on how an event might have developed adversely, and implies the mapping of an operational event on a probabilistic risk model of the plant in order to obtain a quantitative assessment of the safety significance of the event PSA based event analysis provides, due to its quantitative nature, appropriate prioritization of corrective actions. PPEA defines requirements for PSA model and code, identifies input requirements and elaborates following

Preparation of the Regulatory Infrastructure for the New Nuclear Build

International Nuclear Information System (INIS)

Cimesa, Sinisa; Persic, Andreja; Vrankar, Leopold; Stritar, Andrej

2011-01-01

Slovenia is seriously considering building a new nuclear power plant. The Slovenian Nuclear Safety Administration (SNSA) is very much aware of the complexity of such a project as well as of the fact that at the moment the SNSA does not have sufficient resources for licensing and overseeing the design, construction and operation of the possible new plant. Likewise, the question arises whether technical support organizations which support SNSA in supervising the existing Krsko nuclear power plant have sufficient capacity. Therefore SNSA established a special project team with the task to prepare the Administration for the possible start of the new nuclear build. In the beginning of 2009, the project team prepared the analysis of licensing process, which is basically an overview of spatial planning, construction and nuclear safety regulation processes. The purpose of the review of the whole process, from spatial planning to the issuance of the operating license, was to identify phases which will require most effort. The next step was to set the strategy for the review process as well as to analyze and establish the basis for resource demands needed for SNSA's and other stakeholders involvements and decision making in the process. This will enable SNSA to establish a qualified and effective infrastructure for a possible new nuclear build. (authors)

Plant host finding by parasitic plants: A new perspective on plant to plant communication

Science.gov (United States)

Mark C. Mescher; Justin B. Runyon; Consuelo M. De Moraes

2006-01-01

Plants release airborne chemicals that can convey ecologically relevant information to other organisms. These plant volatiles are known to mediate a large array of, often complex, interactions between plants and insects. It has been suggested that plant volatiles may have similar importance in mediating interactions among plant species, but there are few well-...

Societal and Political Issues of Site Selection Process Development for the LILW Repository in Slovenia

Energy Technology Data Exchange (ETDEWEB)

Polic, Marko; KoS, Drago [Univ. of Ljubljana (Slovenia); Zeleznik, Nadja [ARAO, Ljubljana (Slovenia)

2006-09-15

The siting of the radioactive waste repository, even the low and intermediate level radioactivity waste (LILW), presents a great problem in almost every country that produces these materials. Attempts to locate a disposal facility in Slovenia have until now proven unsuccessful. After the failure of the first 'technocratic' approach it became evident that the main problem was not a technical one, but socio-psychological, namely the public acceptability of any radioactive waste disposal facility (RWD). In general people strongly oppose to any kind of such a facility in their vicinity and exhibit a 'Not in my Backyard' (NIMBY) attitude even if they are aware of its necessity. However there are slight signs of changes especially in argumentation supporting the public denial of LIL RWD. The main LILW producer in Slovenia is nuclear power plant in Krsko (NEK). The project for the construction of this plant did not include consideration of the LIL RWD while at that time plans for new NPP's in Yugoslavia with a centralized LILW repository were present. The search for possible locations of LILW repository started only after the beginning of its commercial operation in 1983. The general development of radioactive waste management (RWM) issue in Slovenia was similar to the development in other developed countries, while its details and context differ in smaller or greater degree due to different cultural, political, social and economic backgrounds. The RWM process was following the same general course: technological approach neglecting public issues - public reactance - move toward public involvement. All this was accompanied by the relevant public attitudes: neutrality - rejection - eventual conditional public acceptance. The procedure to find a LILW repository is proposed and established, but the processes leading to final solution are going on without being completely foreseen yet. The general underlying view is connected to the fear of

Societal and Political Issues of Site Selection Process Development for the LILW Repository in Slovenia

International Nuclear Information System (INIS)

Polic, Marko; KoS, Drago; Zeleznik, Nadja

2006-01-01

The siting of the radioactive waste repository, even the low and intermediate level radioactivity waste (LILW), presents a great problem in almost every country that produces these materials. Attempts to locate a disposal facility in Slovenia have until now proven unsuccessful. After the failure of the first 'technocratic' approach it became evident that the main problem was not a technical one, but socio-psychological, namely the public acceptability of any radioactive waste disposal facility (RWD). In general people strongly oppose to any kind of such a facility in their vicinity and exhibit a 'Not in my Backyard' (NIMBY) attitude even if they are aware of its necessity. However there are slight signs of changes especially in argumentation supporting the public denial of LIL RWD. The main LILW producer in Slovenia is nuclear power plant in Krsko (NEK). The project for the construction of this plant did not include consideration of the LIL RWD while at that time plans for new NPP's in Yugoslavia with a centralized LILW repository were present. The search for possible locations of LILW repository started only after the beginning of its commercial operation in 1983. The general development of radioactive waste management (RWM) issue in Slovenia was similar to the development in other developed countries, while its details and context differ in smaller or greater degree due to different cultural, political, social and economic backgrounds. The RWM process was following the same general course: technological approach neglecting public issues - public reactance - move toward public involvement. All this was accompanied by the relevant public attitudes: neutrality - rejection - eventual conditional public acceptance. The procedure to find a LILW repository is proposed and established, but the processes leading to final solution are going on without being completely foreseen yet. The general underlying view is connected to the fear of radioactivity and general negative

A Study of Jordanian University Students' Perceptions of Using Email Exchanges with Native English Keypals for Improving Their Writing Competency

Science.gov (United States)

Mahfouz, Safi Mahmoud

2010-01-01

English foreign language learners generally tend to consider email exchanges with native speakers (NSs) as an effective tool for improving their foreign language proficiency. This study investigated Jordanian university students' perceptions of using email exchanges with native English keypals (NEKs) for improving their writing competency. A…

Power feedback effects in the LEM code

International Nuclear Information System (INIS)

Kromar, M.

1999-01-01

The nodal diffusion code LEM has been extended with the power feedback option. Thermohydraulic and neutronic coupling is covered with the Reactivity Coefficient Method. Presented are results of the code testing. Verification is done on the typical non-uprated NPP Krsko reload cycles. Results show that the code fulfill objectives arising in the process of reactor core analysis.(author)

Aktív anyagok szerepe a rozmaring ízesítésű napraforgó olajban = The role of active materials of rosemary in sunflower oil

OpenAIRE

Somogyi, László

2008-01-01

Kutatómunkám célja az immerzióval, azaz a fűszer áztatásával előállított rozmaring ízesítésű napraforgó olaj aromakarakterének és fontosabb kémiai tulajdonságainak elemzése volt. Az elvégzendő feladatokat az alábbi kérdések megválaszolása érdekében jelöltem ki: 1. Hogyan változik az ízesített napraforgó olaj aromája az adagolt rozmaring arányának és az áztatási időnek függvényében? 2. Milyen oxidációs stabilitással rendelkezik az ízesített olaj ? 3. Mennyire képes az ízesített nap...

Plant stress signalling: understanding and exploiting plant-plant interactions.

Science.gov (United States)

Pickett, J A; Rasmussen, H B; Woodcock, C M; Matthes, M; Napier, J A

2003-02-01

When plants are attacked by insects, volatile chemical signals can be released, not only from the damaged parts, but also systemically from other parts of the plant and this continues after cessation of feeding by the insect. These signals are perceived by olfactory sensory mechanisms in both the herbivorous insects and their parasites. Molecular structures involved can be characterized by means of electrophysiological assays, using the insect sensory system linked to chemical analysis. Evidence is mounting that such signals can also affect neighbouring intact plants, which initiate defence by the induction of further signalling systems, such as those that increase parasitoid foraging. Furthermore, insect electrophysiology can be used in the identification of plant compounds having effects on the plants themselves. It has been found recently that certain plants can release stress signals even when undamaged, and that these can cause defence responses in intact plants. These discoveries provide the basis for new crop protection strategies, that are either delivered by genetic modification of plants or by conventionally produced plants to which the signal is externally applied. Delivery can also be made by means of mixed seed strategies in which the provoking and recipient plants are grown together. Related signalling discoveries within the rhizosphere seem set to extend these approaches into new ways of controlling weeds, by exploiting the elusive potential of allelopathy, but through signalling rather than by direct physiological effects.

Prioritization of design changes based on PSA

International Nuclear Information System (INIS)

Krajnc, B.; Mavko, B.

1996-01-01

Effective use of Probabilistic Safety Analyses (PSA) in the day to day plant operation is subject of intensive discussions among plant operators and regulators. There are several possible applications in which the PSA can be used, among those also to use the PSA approach for the quantification of influence of different proposed design changes to nuclear safety - influence on public safety - health. NPP Krsko is one of those plants that successfully completed its PSA project, with Level 1 and Level 2 analyses and effective know-how transfer. It also faces a number of regulatory and internally generated requirements for different design changes, mainly due to the fact that the plant is committed to continuous augmentation of nuclear safety. It is considered that the available tools and knowledge should be used and therefore applicable methodology should be developed for effective prioritization of proposed design changes by performing cost-benefit analyses for all major modifications - focusing on their influence on nuclear safety. Based on the above a new method for prioritization of design changes is proposed. The method uses Level 1 results (in the sense of plant damage states and their frequencies) directly as an input for further processing - first decision step to decide whether the proposed modification has or has no influence on nuclear safety. In Level 2 analyses the combination of probabilistic and deterministic approach was adopted. In fact the results of the deterministic analyses of severe accidents are treated in probabilistic manner due to large uncertainty of results. Finally to be able to perform plant specific cost benefit analyses so called partial Level 3 was defined. The proposed methods was preliminary tested and it gave favorable results. (author)

Plant-soil feedbacks: role of plant functional group and plant traits

NARCIS (Netherlands)

Cortois, R.; Schröder-Georgi, T.; Weigelt, A.; van der Putten, W.H.; De Deyn, G.B.

2016-01-01

Plant-soil feedback (PSF), plant trait and functional group concepts advanced our understanding of plant community dynamics, but how they are interlinked is poorly known. To test how plant functional groups (FGs: graminoids, small herbs, tall herbs, legumes) and plant traits relate to PSF, we grew

Validation of the IAEA-WIMSD library for the LOADF code on operation transients at the Krsko Power Plant

International Nuclear Information System (INIS)

Trkov, A.; Kurincic, B.

2002-01-01

The LOADF package for reactor core operation monitoring has been tested with the new IAEA-WIMSD-69 library. A transient involving power reduction from full to 80% power was analysed. Predicted critical boron concentrations and control rod positions were compared against measured values. The results confirm that transient prediction with the new library is at least as good or better as with the validated old library.(author)

Comparative study of the effect of chemical and physical factors on the variability of almond

International Nuclear Information System (INIS)

Imamaliev, G.N.; Akhund-Zade, I.M.; Brazhnikova, G.B.

1975-01-01

Six vareties of almond: Texas, Krymskij, Nek-ultra, Logindok, Drejk and Myagkoskorlupyj have been studied. It is shown that gamma-irradiation at a dose up to 16 kr induces 16 to 43 % changes in plants. A dose of 32 kr induces 33 to 60 % changes, 40 t0 50 kr - 65 to 90 % changes, but with a less percentage of survived plants. High doses of gamma-radiation induces a broad spectrum of variability, is not observed under the treatment of seeds with chemical mutagens. A dose of 32 to 40 kr has been found to be critical for the varieties studied, a dose of 50 kr - to be lethal. At a dose of 50 kr the seedlings either do not survive to the end of the vegetative period, or only 3 to 5 plants survie. A chemical mutagen, ethylmethanesulphonate (EMS) at a concentration of 0.1 to 0.2 % produc 12 to 13 % morphological changes, the percentage of survived plants being higher as compared with gamma-radiation. The mutagen concentration of 0.4% produces 90 to 93 % changed plants, the plant survival being 50 to 57 %. The 0.4% concentration can be taken as a critical one for the varieties studied. Comparative evaluations of gamma-radiation and chemical mutagens reveale that EMS at concentrations studied produces 3 to 4 times more changes than gamma-rays, the percentage of survived plants being also 3 to 4 times higher. However, EMS produces monotypic changes, while gamma-radiation induces a broad spectrum of variability. Thus, EMS can be used as a factor inducing dwarf varieties of almond and other fruit cultures

A lecture on nuclear physics in primary school

International Nuclear Information System (INIS)

Arh, S.

2004-01-01

I am going to propose the contents of a lecture on nuclear physics and radioactivity in primary school. Contemporary technology, medicine and science exploit intensively the discovered knowledge about processes in atoms and in a nucleus. Mankind has gained huge profit from peaceful applications of nuclear reactions and ionizing radiation. We use the products of nuclear industry every day. But about half of the school population never hears a professional explanation about what is going on in nuclear power plants. Only on some secondary schools students learn about nuclear physics. The lack of knowledge about nuclear processes is the main reason why people show great fear when hearing the words: radiation, radioactivity, nuclear, etc. At last it is now time to give some fundamental lessons on nuclear physics and radioactivity also to pupils in primary school. From my four-year teaching experience in primary school I am suggesting a programme of lectures on nuclear physics and radioactivity. At the end of the lessons we would visit the Krsko Nuclear Power Plant or the Nuclear Training Centre Milan Copic. This could be included in the so called natural science day. Pupils come from the eight class (14 years old) of primary school and have no problems following the explanation. (author)

LNG plant combined with power plant

Energy Technology Data Exchange (ETDEWEB)

Aoki, I; Kikkawa, Y [Chiyoda Chemical Engineering and Construction Co. Ltd., Tokyo (Japan)

1997-06-01

The LNG plant consumers a lot of power of natural gas cooling and liquefaction. In some LNG plant location, a rapid growth of electric power demand is expected due to the modernization of area and/or the country. The electric power demand will have a peak in day time and low consumption in night time, while the power demand of the LNG plant is almost constant due to its nature. Combining the LNG plant with power plant will contribute an improvement the thermal efficiency of the power plant by keeping higher average load of the power plant, which will lead to a reduction of electrical power generation cost. The sweet fuel gas to the power plant can be extracted from the LNG plant, which will be favorable from view point of clean air of the area. (Author). 5 figs.

LNG plant combined with power plant

International Nuclear Information System (INIS)

Aoki, I.; Kikkawa, Y.

1997-01-01

The LNG plant consumers a lot of power of natural gas cooling and liquefaction. In some LNG plant location, a rapid growth of electric power demand is expected due to the modernization of area and/or the country. The electric power demand will have a peak in day time and low consumption in night time, while the power demand of the LNG plant is almost constant due to its nature. Combining the LNG plant with power plant will contribute an improvement the thermal efficiency of the power plant by keeping higher average load of the power plant, which will lead to a reduction of electrical power generation cost. The sweet fuel gas to the power plant can be extracted from the LNG plant, which will be favorable from view point of clean air of the area. (Author). 5 figs

A comprehensive siRNA screen for kinases that suppress macroautophagy in optimal growth conditions

DEFF Research Database (Denmark)

Szyniarowski, Piotr; Corcelle-Termeau, Elisabeth; Farkas, Thomas

2011-01-01

, whereas CSNK1A1, BUB1, PKLR and NEK4 suppressed autophagosome formation downstream or independent of mTORC1. Importantly, all identified kinases except for BUB1 regulated macroautophagy also in immortalized MCF-10A breast epithelial cells. The kinases identified here shed light to the complex regulation...

Distance od jsoucna, poslání ke jsoucnu. K Patočkovu negativnímu platonismu a některým jeho interpretacím

Czech Academy of Sciences Publication Activity Database

Frei, Jan

2017-01-01

Roč. 65, č. 6 (2017), s. 873-886 ISSN 0015-1831 Institutional support: RVO:67985955 Keywords : Jan Patočka * Negative Platonism * contradictory nature of the conception * Petr Rezek * Ladislav Hejdánek * Pavel Kouba Subject RIV: AA - Philosophy ; Religion OBOR OECD: Philosophy, History and Philosophy of science and technology

Goede verlichting beeldscherm-werkplek wettelijk verplicht [Good lighting of the VDU-workplace under legal obligation

NARCIS (Netherlands)

Bergem-Jansen, P.M. van

1993-01-01

ln ons land werken naar schatting meer dan een miljoen mensen met een beeldscherm. Uit ondezoek (Pot e.a., 1986) blijkt dat beeldschermwerk kan leiden tot nek- en schouderklachten, vermoeidheid van de ogen en hoofdpijn; circa 4O% van de beeldschermwerkers vertoont één of beide van de eerstgenoemde

Temperature and stress distribution in pressure vessel by the boundary element method

International Nuclear Information System (INIS)

Alujevic, A.; Apostolovic, D.

1990-01-01

The aim of this paper is to demonstrate the applicability of boundary element method for the solution of temperatures and thermal stresses in the body of reactor pressure vessel of the NPP Krsko . In addition to the theory of boundary elements for thermo-elastic continua (2D, 3D) results are given of a numerically evaluated meridional cross-section. (author)

Kuidas portreteerida legendi / Igor Garšnek

Index Scriptorium Estoniae

Garšnek, Igor, 1958-

2008-01-01

Kahest muusikadokumentaalist "Elvis - Presleyde pilgu läbi" ("Elvis by the Presleys, rež. Rob Klug, 2005) ja "Rääkimata lugu: Freddie Mercury" ("Freddie Mercury, the Untold Stry", rež. Rudi Dolezal ja Hannes Rossacher, 2000)

Mõtlemine algab kujustamisest / Igor Garšnek

Index Scriptorium Estoniae

Garšnek, Igor, 1958-

2010-01-01

2. detsembril toimunud kontserdist "The Music of the Image", kus esinesid Brüsseli Filharmoonikud, Lewis Morison, Gaelle Mechaly, Juanjo Mosalini ja Gabriel Yared Dirk Brosse dirigeerimisel ning 6. detsembril Estonia kontserdisaalis toimunud "Suurest filmimuusika kontserdist", kus esinesid Peterburi sümfooniaorkester Cinema ja Žanna Dombrovskaja Igor Ponomarenko juhatusel

O Karlu Kosíkovi a nejen o něm: rozhovor Terezy Kunešové s PhDr. Josefem Zumrem

Czech Academy of Sciences Publication Activity Database

Kunešová, T.; Zumr, Josef

2015-01-01

Roč. 62, č. 1 (2015), s. 105-124 ISSN 1803-7445 Institutional support: RVO:67985955 Keywords : Karel Kosík * Josef Zumr * Marxism * Czechoslovakia * Communist Party of Czechoslovakia * Dialectics of the Concrete * Arnošt Kolman * Ladislav Hejdánek Subject RIV: AA - Philosophy ; Religion http://hdl.handle.net/11222.digilib/133886

Documentation of high impact visualizations and improvement plans for utilization of VisIt for reactor simulation

Energy Technology Data Exchange (ETDEWEB)

R.Childs, H; Bremer, D J

2008-10-03

The primary goal of this milestone was to enable the visualization and analysis needs of the campaign's simulation codes. This goal was well accomplished. We have extended the VisIt visualization and analysis tool to be suitable for the Nek, UNIC, SAS, and DIABLO code teams. This represented a significant development effort, primarily in terms of tuning the processing of the very large data sets produced by the Nek code. As a result of our development, and of the support we provided, these groups have been able to successfully accomplish their visualization and analysis activities using VisIt. Visualization is an important part of the simulation process. It allows stakeholders to explore simulations and discover phenomena, to confirm assumptions, and to convey findings to a larger audience. Further, visualization software is complex and is an active research area, especially in the area of visualization of very large data sets, such as those produced by the Reactor campaign's Nek code. To meet the campaign's visualization and analysis needs, we chose to leverage the existing software tool, VisIt. VisIt is an open source, parallel visualization and analysis tool for interactively exploring scientific data. The tool represents approximately fifty man-years worth of effort, much of which was dedicated to techniques for processing large data and also to user interfaces. VisIt originated in the DOE's Advanced Simulation and Computing Initiative (ASCI) program, but is also actively developed by the Office of Science's Scientific Discovery through Advanced Computing (SciDAC) program, as well as by the at large open source community, including university partners. Our work for this effort consisted of both customizing VisIt to meet Reactor campaign needs and of providing support for stakeholders in the Reactor campaign to ensure they were successful using the tool.

Maloti Drakensberg Transfrontier Park joint management: Sehlabathebe National Park (Lesotho) and the uKhahlamba Drakensberg Park World Heritage Site (South Africa)

Science.gov (United States)

John M. Crowson

2011-01-01

On 8 April 2005, the first Joint Management Committee meeting was held at Qacha's Nek, Lesotho. This was to ensure co-operative management through joint management. The formation of a Joint Management Committee was part of the Bilateral Maloti Drakensberg Transfrontier Project agreement and consisted of officials from the Ministry of Tourism, Environment and...

The Westinghouse AP600 an advanced nuclear option for small or medium electricity grids

International Nuclear Information System (INIS)

Bruschi, H. J.; Novak, V.

1996-01-01

During the early days of commercial nuclear power, many countries looking to add nuclear power to their energy mix required large plants to meet the energy needs of rapidly growing populations and large industrial complexes. The majority of plants worldwide are in the range of 100 megawatts and beyond. During the 1970s, it became apparent that a smaller nuclear plants would appeal to utilities looking to add additional power capacity to existing grids, or to utilities in smaller countries which were seeking efficient, new nuclear generation capacity for the first time. For instance, the Westinghouse-designed 600 megawatt Krsko plant in Slovenia began operation in 1980, providing electricity to inhabitants of relatively small, yet industrial populations of Slovenia and Croatia. This plant design incorporated the best, proven technology available at that time, based on 20 years of Westinghouse PWR pioneering experience. Beginning in the early 1980s, Westinghouse began to build further upon that experience - in part through the advanced light water reactor programs established by the Electric Power Research institute (EPRI) and the U.S. Department of Energy (DOE) - to design a simplified, advanced nuclear reactor in the 600 megawatt range. Originally, Westinghouse's development of its AP600 (advanced, passive 600-megawatt) plants was geared towards the needs of U.S. utilities which specified smaller, simplified nuclear options for the decades ahead. It soon became evident that the small and medium sized electricity grids of international markets could benefit from this new reactor. From the earliest days of Westinghouse's AP600 development, the corporation invited members of the international nuclear community to take part in the design, development and testing of the AP600 - with the goal of designing a reactor that would meet the diverse needs of an international industry composed of countries with similar, yet different, concerns. (author)

Implications of the Croatian Spent Fuel and Radioactive Waste Strategy

International Nuclear Information System (INIS)

Lokner, V.; Levanat, I.

2012-01-01

Croatian Government approved its national Radioactive waste and Spent Fuel Strategy as a part of the accession process to EU in July 2009 enabling acquisition of adequate administrative capacity by the time of accession to properly implement and enforce the relevant legislation in all areas related to nuclear safety. Strategy was formulated in line with the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. In particular, the strategy was approved to ensure that sufficient qualified staff and adequate financial services are available to support the safety of facilities for spent fuel and radioactive waste management generated by Krsko NPP during their operating lifetime and from decommissioning. Following are statements from the Croatian strategy that are relevant for Croatian position regarding capacity building for storage and disposal of LILW and SF. To be able to fulfill the obligations assumed, Croatia needs to do the following (Strategy Section 3.3): reach an agreement with Slovenia by 2013 at the latest regarding the location of objects for storing LILW; should no such agreement be reached, Croatia is to initiate preparations for assuming its half of operational LILW and for third-country export thereof, or for storing the LILW on Croatian territory, whilst also gradually assuming the part of LILW created from decommissioning; reach an agreement with Slovenia by 2018 at the latest regarding the location of a common SF storage; should no such agreement be reached, initiate preparations for assuming a third-country export of SF, or for storing half of SF on Croatian territory. This paper discusses the Strategy aims in the light of noticeable delay of 2nd revision of the Program of NPP Krsko Decommissioning and SF andLILW Disposal, the status of the planned Slovenian national repository on Vrbina site and the prospects of its use for joint Croatian/Slovenian LILW disposal - all in the context of as yet

Plant-plant competition outcomes are modulated by plant effects on the soil bacterial community.

Science.gov (United States)

Hortal, S; Lozano, Y M; Bastida, F; Armas, C; Moreno, J L; Garcia, C; Pugnaire, F I

2017-12-19

Competition is a key process that determines plant community structure and dynamics, often mediated by nutrients and water availability. However, the role of soil microorganisms on plant competition, and the links between above- and belowground processes, are not well understood. Here we show that the effects of interspecific plant competition on plant performance are mediated by feedbacks between plants and soil bacterial communities. Each plant species selects a singular community of soil microorganisms in its rhizosphere with a specific species composition, abundance and activity. When two plant species interact, the resulting soil bacterial community matches that of the most competitive plant species, suggesting strong competitive interactions between soil bacterial communities as well. We propose a novel mechanism by which changes in belowground bacterial communities promoted by the most competitive plant species influence plant performance and competition outcome. These findings emphasise the strong links between plant and soil communities, paving the way to a better understanding of plant community dynamics and the effects of soil bacterial communities on ecosystem functioning and services.

Apoplastic interactions between plants and plant root intruders

Directory of Open Access Journals (Sweden)

Kanako eMitsumasu

2015-08-01

Full Text Available Numerous pathogenic or parasitic organisms attack plant roots to obtain nutrients, and the apoplast including the plant cell wall is where the plant cell meets such organisms. Root-parasitic angiosperms and nematodes are two distinct types of plant root parasites but share some common features in their strategies for breaking into plant roots. Striga and Orobanche are obligate root parasitic angiosperms that cause devastating agricultural problems worldwide. Parasitic plants form an invasion organ called a haustorium, where plant cell wall degrading enzymes (PCWDEs are highly expressed. Plant-parasitic nematodes are another type of agriculturally important plant root parasite. These nematodes breach the plant cell walls by protruding a sclerotized stylet from which PCWDEs are secreted. Responding to such parasitic invasion, host plants activate their own defense responses against parasites. Endoparasitic nematodes secrete apoplastic effectors to modulate host immune responses and to facilitate the formation of a feeding site. Apoplastic communication between hosts and parasitic plants also contributes to their interaction. Parasitic plant germination stimulants, strigolactones (SLs, are recently identified apoplastic signals that are transmitted over long distances from biosynthetic sites to functioning sites. Here, we discuss recent advances in understanding the importance of apoplastic signals and cell walls for plant-parasite interactions.

Apoplastic interactions between plants and plant root intruders.

Science.gov (United States)

Mitsumasu, Kanako; Seto, Yoshiya; Yoshida, Satoko

2015-01-01

Numerous pathogenic or parasitic organisms attack plant roots to obtain nutrients, and the apoplast including the plant cell wall is where the plant cell meets such organisms. Root parasitic angiosperms and nematodes are two distinct types of plant root parasites but share some common features in their strategies for breaking into plant roots. Striga and Orobanche are obligate root parasitic angiosperms that cause devastating agricultural problems worldwide. Parasitic plants form an invasion organ called a haustorium, where plant cell wall degrading enzymes (PCWDEs) are highly expressed. Plant-parasitic nematodes are another type of agriculturally important plant root parasite. These nematodes breach the plant cell walls by protruding a sclerotized stylet from which PCWDEs are secreted. Responding to such parasitic invasion, host plants activate their own defense responses against parasites. Endoparasitic nematodes secrete apoplastic effectors to modulate host immune responses and to facilitate the formation of a feeding site. Apoplastic communication between hosts and parasitic plants also contributes to their interaction. Parasitic plant germination stimulants, strigolactones, are recently identified apoplastic signals that are transmitted over long distances from biosynthetic sites to functioning sites. Here, we discuss recent advances in understanding the importance of apoplastic signals and cell walls for plant-parasite interactions.

Common breast cancer susceptibility alleles and the risk of breast cancer for BRCA1 and BRCA2 mutation carriers: implications for risk prediction

DEFF Research Database (Denmark)

Antoniou, Antonis C; Beesley, Jonathan; McGuffog, Lesley

2010-01-01

The known breast cancer susceptibility polymorphisms in FGFR2, TNRC9/TOX3, MAP3K1, LSP1, and 2q35 confer increased risks of breast cancer for BRCA1 or BRCA2 mutation carriers. We evaluated the associations of 3 additional single nucleotide polymorphisms (SNPs), rs4973768 in SLC4A7/NEK10, rs650495...

Chemical signaling between plants and plant-pathogenic bacteria.

Science.gov (United States)

Venturi, Vittorio; Fuqua, Clay

2013-01-01

Studies of chemical signaling between plants and bacteria in the past have been largely confined to two models: the rhizobial-legume symbiotic association and pathogenesis between agrobacteria and their host plants. Recent studies are beginning to provide evidence that many plant-associated bacteria undergo chemical signaling with the plant host via low-molecular-weight compounds. Plant-produced compounds interact with bacterial regulatory proteins that then affect gene expression. Similarly, bacterial quorum-sensing signals result in a range of functional responses in plants. This review attempts to highlight current knowledge in chemical signaling that takes place between pathogenic bacteria and plants. This chemical communication between plant and bacteria, also referred to as interkingdom signaling, will likely become a major research field in the future, as it allows the design of specific strategies to create plants that are resistant to plant pathogens.

Four planting devices for planting no-till maize

Directory of Open Access Journals (Sweden)

Osei Bonsu Patterson

2015-05-01

Full Text Available An experiment was conducted at the CSIR-Crops Research Institute (CSIR-CRI Experimental station at Ejura in Ghana to compare the efficiency of four devices for planting no-till maize: Tractor drawn seeder, Chinese made jab planter, Locally made jab planter and a Cutlass. It took two (2 hours 48 minutes to plant one hectare of maize with the tractor drawn seeder, which was significantly (p less than 1% faster than all the planting methods. Cutlass was the slowest planting device lasting more than 14 hours per hectare. There was no significant difference in planting time between the Chinese planter and local planter. Economic analysis showed that cutlass planting produced the highest net benefit, whilst tractor drawn seeder produced the least benefit. In this study cutlass planting was done with precision by collaborating farmers. In actual farm situation however, hired laborers (planting gangs often plant in haste which often results in poor plant population leading to low yields. Tractor drawn seeders or jab planters could reduce drudgery in planting and encourage farm expansion.

Operation and maintenance of the RB reactor, Annual report for 1979

International Nuclear Information System (INIS)

Sotic, O.; Vranic, S.; Petronijevic, M.

1979-01-01

The annual report for 1979 includes the following: utilization of the RB reactor; accident analysis; dosimetry and radiation protection; description of the reactor equipment status; reactor staff; financial data. Six Annexes to this report are concerned with: scientific program orientation; producing the new safety report; maintenance of the reactor components and equipment; purchase of new equipment; financial report; and program for training the staff of the Krsko NPP

Plant aquaporins: roles in plant physiology.

Science.gov (United States)

Li, Guowei; Santoni, Véronique; Maurel, Christophe

2014-05-01

Aquaporins are membrane channels that facilitate the transport of water and small neutral molecules across biological membranes of most living organisms. Here, we present comprehensive insights made on plant aquaporins in recent years, pointing to their molecular and physiological specificities with respect to animal or microbial counterparts. In plants, aquaporins occur as multiple isoforms reflecting a high diversity of cellular localizations and various physiological substrates in addition to water. Of particular relevance for plants is the transport by aquaporins of dissolved gases such as carbon dioxide or metalloids such as boric or silicic acid. The mechanisms that determine the gating and subcellular localization of plant aquaporins are extensively studied. They allow aquaporin regulation in response to multiple environmental and hormonal stimuli. Thus, aquaporins play key roles in hydraulic regulation and nutrient transport in roots and leaves. They contribute to several plant growth and developmental processes such as seed germination or emergence of lateral roots. Plants with genetically altered aquaporin functions are now tested for their ability to improve plant resistance to stresses. This article is part of a Special Issue entitled Aquaporins. Copyright © 2013 Elsevier B.V. All rights reserved.

Integrated Gasification SOFC Plant with a Steam Plant

DEFF Research Database (Denmark)

Rokni, Masoud; Pierobon, Leonardo

2011-01-01

A hybrid Solid Oxide Fuel Cell (SOFC) and Steam Turbine (ST) plant is integrated with a gasification plant. Wood chips are fed to the gasification plant to produce biogas and then this gas is fed into the anode side of a SOFC cycle to produce electricity and heat. The gases from the SOFC stacks...... enter into a burner to burn the rest of the fuel. The offgases after the burner are now used to generate steam in a Heat Recovery Steam Generator (HRSG). The generated steam is expanded in a ST to produce additional power. Thus a triple hybrid plant based on a gasification plant, a SOFC plant...... and a steam plant is presented and studied. The plant is called as IGSS (Integrated Gasification SOFC Steam plant). Different systems layouts are presented and investigated. Electrical efficiencies up to 56% are achieved which is considerably higher than the conventional integrated gasification combined...

Plant ecdysteroids: plant sterols with intriguing distributions, biological effects and relations to plant hormones.

Science.gov (United States)

Tarkowská, Danuše; Strnad, Miroslav

2016-09-01

The present review summarises current knowledge of phytoecdysteroids' biosynthesis, distribution within plants, biological importance and relations to plant hormones. Plant ecdysteroids (phytoecdysteroids) are natural polyhydroxylated compounds that have a four-ringed skeleton, usually composed of either 27 carbon atoms or 28-29 carbon atoms (biosynthetically derived from cholesterol or other plant sterols, respectively). Their physiological roles in plants have not yet been confirmed and their occurrence is not universal. Nevertheless, they are present at high concentrations in various plant species, including commonly consumed vegetables, and have a broad spectrum of pharmacological and medicinal properties in mammals, including hepatoprotective and hypoglycaemic effects, and anabolic effects on skeletal muscle, without androgenic side-effects. Furthermore, phytoecdysteroids can enhance stress resistance by promoting vitality and enhancing physical performance; thus, they are considered adaptogens. This review summarises current knowledge of phytoecdysteroids' biosynthesis, distribution within plants, biological importance and relations to plant hormones.

Plant toxicity, adaptive herbivory, and plant community dynamics

Science.gov (United States)

Feng, Z.; Liu, R.; DeAngelis, D.L.; Bryant, J.P.; Kielland, K.; Stuart, Chapin F.; Swihart, R.K.

2009-01-01

We model effects of interspecific plant competition, herbivory, and a plant's toxic defenses against herbivores on vegetation dynamics. The model predicts that, when a generalist herbivore feeds in the absence of plant toxins, adaptive foraging generally increases the probability of coexistence of plant species populations, because the herbivore switches more of its effort to whichever plant species is more common and accessible. In contrast, toxin-determined selective herbivory can drive plant succession toward dominance by the more toxic species, as previously documented in boreal forests and prairies. When the toxin concentrations in different plant species are similar, but species have different toxins with nonadditive effects, herbivores tend to diversify foraging efforts to avoid high intakes of any one toxin. This diversification leads the herbivore to focus more feeding on the less common plant species. Thus, uncommon plants may experience depensatory mortality from herbivory, reducing local species diversity. The depensatory effect of herbivory may inhibit the invasion of other plant species that are more palatable or have different toxins. These predictions were tested and confirmed in the Alaskan boreal forest. ?? 2009 Springer Science+Business Media, LLC.

Targeting the UPR to Circumvent Endocrine Resistance in Breast Cancer

Science.gov (United States)

2016-12-01

cells, and re-sensitize resistant cells, to both estrogen withdrawal (analogous to treatment with an AI ) and to two different classes of AE (TAM and...following hits for NPPTA-TsOH and JS20- TsOH: NPPTA-TsOH: c-KIT<PDGFRB<FLT-3 JS20-TsOH: MEK6<NEK1 Future directions and publication(s): Currently

Saturated Particle Transport in Porous Media: An Investigation into the Influence of Flow Direction and Particle Size Distribution

Science.gov (United States)

2015-06-28

also as a sorbed phase on moving particulate matter such as humic substances, clay particles, colloidal silica and metal oxides [Šimůnek et al., 2006a...dynamic viscosity , µ 9.98·10-6 kg/m/sec Cation valance, zce 2 Separation distance, h 1·10-6 m Molar concentration of cations, C0 1·10-5 moles Hamaker

Erich Fromm: ke kořenům etiky

Directory of Open Access Journals (Sweden)

Pavel Žďárský

2008-05-01

Full Text Available Článek je zaměřený na Frommovu nenáboženskou, psychologicky pojatou interpretaci židovsko-křesťanské tradice o dvou cestách člověka. Jde o upravenou verzi článku publikovaného v e-journalu PAIDEIA 2/2005, www.pedf.cuni.cz/paideia.

[Development of Plant Metabolomics and Medicinal Plant Genomics].

Science.gov (United States)

Saito, Kazuki

2018-01-01

 A variety of chemicals produced by plants, often referred to as 'phytochemicals', have been used as medicines, food, fuels and industrial raw materials. Recent advances in the study of genomics and metabolomics in plant science have accelerated our understanding of the mechanisms, regulation and evolution of the biosynthesis of specialized plant products. We can now address such questions as how the metabolomic diversity of plants is originated at the levels of genome, and how we should apply this knowledge to drug discovery, industry and agriculture. Our research group has focused on metabolomics-based functional genomics over the last 15 years and we have developed a new research area called 'Phytochemical Genomics'. In this review, the development of a research platform for plant metabolomics is discussed first, to provide a better understanding of the chemical diversity of plants. Then, representative applications of metabolomics to functional genomics in a model plant, Arabidopsis thaliana, are described. The extension of integrated multi-omics analyses to non-model specialized plants, e.g., medicinal plants, is presented, including the identification of novel genes, metabolites and networks for the biosynthesis of flavonoids, alkaloids, sulfur-containing metabolites and terpenoids. Further, functional genomics studies on a variety of medicinal plants is presented. I also discuss future trends in pharmacognosy and related sciences.

7 CFR 302.2 - Movement of plants and plant products.

Science.gov (United States)

2010-01-01

... 7 Agriculture 5 2010-01-01 2010-01-01 false Movement of plants and plant products. 302.2 Section... INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE DISTRICT OF COLUMBIA; MOVEMENT OF PLANTS AND PLANT PRODUCTS § 302.2 Movement of plants and plant products. Inspection or documentation of the plant health status of...

PLANT BIOPRINTING: NOVEL PERSPECTIVE FOR PLANT BIOTECHNOLOGY

Directory of Open Access Journals (Sweden)

Adhityo WICAKSONO

2015-12-01

Full Text Available Bioprinting is a technical innovation that has revolutionized tissue engineering. Using conventional printer cartridges filled with cells as well as a suitable scaffold, major advances have been made in the biomedical field, and it is now possible to print skin, bones, blood vessels, and even organs. Unlike animal systems, the application of bioprinting in simple plant tissue cells is still in a nascent phase and has yet to be studied. One major advantage of plants is that all living parts are reprogrammable in the form of totipotent cells. Plant bioprinting may improve scientists’understanding of plant shape and morphogenesis, and could serve for the mass production of desired tissues or plants, or even the production of plant-based biomaterial for industrial uses. This perspectives paper explores these possibilities using knowledge on what is known about bioprinting in other biosystems.

Plant responses to plant growth-promoting rhizobacteria

NARCIS (Netherlands)

Loon, L.C. van

2007-01-01

Non-pathogenic soilborne microorganisms can promote plant growth, as well as suppress diseases. Plant growth promotion is taken to result from improved nutrient acquisition or hormonal stimulation. Disease suppression can occur through microbial antagonism or induction of resistance in the plant.

The iPlant Collaborative: Cyberinfrastructure for Plant Biology

Science.gov (United States)

Goff, Stephen A.; Vaughn, Matthew; McKay, Sheldon; Lyons, Eric; Stapleton, Ann E.; Gessler, Damian; Matasci, Naim; Wang, Liya; Hanlon, Matthew; Lenards, Andrew; Muir, Andy; Merchant, Nirav; Lowry, Sonya; Mock, Stephen; Helmke, Matthew; Kubach, Adam; Narro, Martha; Hopkins, Nicole; Micklos, David; Hilgert, Uwe; Gonzales, Michael; Jordan, Chris; Skidmore, Edwin; Dooley, Rion; Cazes, John; McLay, Robert; Lu, Zhenyuan; Pasternak, Shiran; Koesterke, Lars; Piel, William H.; Grene, Ruth; Noutsos, Christos; Gendler, Karla; Feng, Xin; Tang, Chunlao; Lent, Monica; Kim, Seung-Jin; Kvilekval, Kristian; Manjunath, B. S.; Tannen, Val; Stamatakis, Alexandros; Sanderson, Michael; Welch, Stephen M.; Cranston, Karen A.; Soltis, Pamela; Soltis, Doug; O'Meara, Brian; Ane, Cecile; Brutnell, Tom; Kleibenstein, Daniel J.; White, Jeffery W.; Leebens-Mack, James; Donoghue, Michael J.; Spalding, Edgar P.; Vision, Todd J.; Myers, Christopher R.; Lowenthal, David; Enquist, Brian J.; Boyle, Brad; Akoglu, Ali; Andrews, Greg; Ram, Sudha; Ware, Doreen; Stein, Lincoln; Stanzione, Dan

2011-01-01

The iPlant Collaborative (iPlant) is a United States National Science Foundation (NSF) funded project that aims to create an innovative, comprehensive, and foundational cyberinfrastructure in support of plant biology research (PSCIC, 2006). iPlant is developing cyberinfrastructure that uniquely enables scientists throughout the diverse fields that comprise plant biology to address Grand Challenges in new ways, to stimulate and facilitate cross-disciplinary research, to promote biology and computer science research interactions, and to train the next generation of scientists on the use of cyberinfrastructure in research and education. Meeting humanity's projected demands for agricultural and forest products and the expectation that natural ecosystems be managed sustainably will require synergies from the application of information technologies. The iPlant cyberinfrastructure design is based on an unprecedented period of research community input, and leverages developments in high-performance computing, data storage, and cyberinfrastructure for the physical sciences. iPlant is an open-source project with application programming interfaces that allow the community to extend the infrastructure to meet its needs. iPlant is sponsoring community-driven workshops addressing specific scientific questions via analysis tool integration and hypothesis testing. These workshops teach researchers how to add bioinformatics tools and/or datasets into the iPlant cyberinfrastructure enabling plant scientists to perform complex analyses on large datasets without the need to master the command-line or high-performance computational services. PMID:22645531

The iPlant Collaborative: Cyberinfrastructure for Plant Biology.

Science.gov (United States)

Goff, Stephen A; Vaughn, Matthew; McKay, Sheldon; Lyons, Eric; Stapleton, Ann E; Gessler, Damian; Matasci, Naim; Wang, Liya; Hanlon, Matthew; Lenards, Andrew; Muir, Andy; Merchant, Nirav; Lowry, Sonya; Mock, Stephen; Helmke, Matthew; Kubach, Adam; Narro, Martha; Hopkins, Nicole; Micklos, David; Hilgert, Uwe; Gonzales, Michael; Jordan, Chris; Skidmore, Edwin; Dooley, Rion; Cazes, John; McLay, Robert; Lu, Zhenyuan; Pasternak, Shiran; Koesterke, Lars; Piel, William H; Grene, Ruth; Noutsos, Christos; Gendler, Karla; Feng, Xin; Tang, Chunlao; Lent, Monica; Kim, Seung-Jin; Kvilekval, Kristian; Manjunath, B S; Tannen, Val; Stamatakis, Alexandros; Sanderson, Michael; Welch, Stephen M; Cranston, Karen A; Soltis, Pamela; Soltis, Doug; O'Meara, Brian; Ane, Cecile; Brutnell, Tom; Kleibenstein, Daniel J; White, Jeffery W; Leebens-Mack, James; Donoghue, Michael J; Spalding, Edgar P; Vision, Todd J; Myers, Christopher R; Lowenthal, David; Enquist, Brian J; Boyle, Brad; Akoglu, Ali; Andrews, Greg; Ram, Sudha; Ware, Doreen; Stein, Lincoln; Stanzione, Dan

2011-01-01

The iPlant Collaborative (iPlant) is a United States National Science Foundation (NSF) funded project that aims to create an innovative, comprehensive, and foundational cyberinfrastructure in support of plant biology research (PSCIC, 2006). iPlant is developing cyberinfrastructure that uniquely enables scientists throughout the diverse fields that comprise plant biology to address Grand Challenges in new ways, to stimulate and facilitate cross-disciplinary research, to promote biology and computer science research interactions, and to train the next generation of scientists on the use of cyberinfrastructure in research and education. Meeting humanity's projected demands for agricultural and forest products and the expectation that natural ecosystems be managed sustainably will require synergies from the application of information technologies. The iPlant cyberinfrastructure design is based on an unprecedented period of research community input, and leverages developments in high-performance computing, data storage, and cyberinfrastructure for the physical sciences. iPlant is an open-source project with application programming interfaces that allow the community to extend the infrastructure to meet its needs. iPlant is sponsoring community-driven workshops addressing specific scientific questions via analysis tool integration and hypothesis testing. These workshops teach researchers how to add bioinformatics tools and/or datasets into the iPlant cyberinfrastructure enabling plant scientists to perform complex analyses on large datasets without the need to master the command-line or high-performance computational services.

The iPlant Collaborative: Cyberinfrastructure for Plant Biology

Directory of Open Access Journals (Sweden)

Stephen A Goff

2011-07-01

Full Text Available The iPlant Collaborative (iPlant is a United States National Science Foundation (NSF funded project that aims to create an innovative, comprehensive, and foundational cyberinfrastructure in support of plant biology research (PSCIC, 2006. iPlant is developing cyberinfrastructure that uniquely enables scientists throughout the diverse fields that comprise plant biology to address Grand Challenges in new ways, to stimulate and facilitate cross-disciplinary research, to promote biology and computer science research interactions, and to train the next generation of scientists on the use of cyberinfrastructure in research and education. Meeting humanity's projected demands for agricultural and forest products and the expectation that natural ecosystems be managed sustainably will require synergies from the application of information technologies. The iPlant cyberinfrastructure design is based on an unprecedented period of research community input, and leverages developments in high-performance computing, data storage, and cyberinfrastructure for the physical sciences. iPlant is an open-source project with application programming interfaces that allow the community to extend the infrastructure to meet its needs. iPlant is sponsoring community-driven workshops addressing specific scientific questions via analysis tool integration and hypothesis testing. These workshops teach researchers how to add bioinformatics tools and/or datasets into the iPlant cyberinfrastructure enabling plant scientists to perform complex analyses on large datasets without the need to master the command-line or high-performance computational services.

Metodika auditu webových stránek

OpenAIRE

Jirsa, Tomáš

2010-01-01

Websites have a significant impact on the competitiveness of organizations. Therefore it is necessary to deal with aspects that affect their success. At least it is worth to detect weaknesses which can be repaired with minimal effort and which baffle effective use of the site. It is possible to use quite a number of audit methods and tools but the global approach to this issue is missing. The aim of this thesis is to create audit methodology and its implementation into the online tool, to all...

Kaks kiirpilku festivalile "Credo" / Igor Garšnek

Index Scriptorium Estoniae

Garšnek, Igor, 1958-

2011-01-01

Rahvusvahelise õigeusu vaimuliku muusika festivali "Credo" raames toimunud kahest kontserdist: 21. septembril Kaarli kirikus toimunud müsteeriumist "Jumalaema palve", esitajaks festivali "Credo" meesansambel Stanislav Šeljahhovski dirigeerimisel ja 13. septembril Tallinna Jaani kirikus toimunud Pariisi Neeva vaga suurvürsti Aleksandri paekiriku koori kontserdist ülemdiakon Aleksandr Kedrovi juhatusel

Aboveground mechanical stimuli affect belowground plant-plant communication.

Science.gov (United States)

Elhakeem, Ali; Markovic, Dimitrije; Broberg, Anders; Anten, Niels P R; Ninkovic, Velemir

2018-01-01

Plants can detect the presence of their neighbours and modify their growth behaviour accordingly. But the extent to which this neighbour detection is mediated by abiotic stressors is not well known. In this study we tested the acclimation response of Zea mays L. seedlings through belowground interactions to the presence of their siblings exposed to brief mechano stimuli. Maize seedling simultaneously shared the growth solution of touched plants or they were transferred to the growth solution of previously touched plants. We tested the growth preferences of newly germinated seedlings toward the growth solution of touched (T_solution) or untouched plants (C_solution). The primary root of the newly germinated seedlings grew significantly less towards T_solution than to C_solution. Plants transferred to T_solution allocated more biomass to shoots and less to roots. While plants that simultaneously shared their growth solution with the touched plants produced more biomass. Results show that plant responses to neighbours can be modified by aboveground abiotic stress to those neighbours and suggest that these modifications are mediated by belowground interactions.

Aboveground mechanical stimuli affect belowground plant-plant communication.

Directory of Open Access Journals (Sweden)

Ali Elhakeem

Full Text Available Plants can detect the presence of their neighbours and modify their growth behaviour accordingly. But the extent to which this neighbour detection is mediated by abiotic stressors is not well known. In this study we tested the acclimation response of Zea mays L. seedlings through belowground interactions to the presence of their siblings exposed to brief mechano stimuli. Maize seedling simultaneously shared the growth solution of touched plants or they were transferred to the growth solution of previously touched plants. We tested the growth preferences of newly germinated seedlings toward the growth solution of touched (T_solution or untouched plants (C_solution. The primary root of the newly germinated seedlings grew significantly less towards T_solution than to C_solution. Plants transferred to T_solution allocated more biomass to shoots and less to roots. While plants that simultaneously shared their growth solution with the touched plants produced more biomass. Results show that plant responses to neighbours can be modified by aboveground abiotic stress to those neighbours and suggest that these modifications are mediated by belowground interactions.

Design of plant safety model in plant enterprise engineering environment

International Nuclear Information System (INIS)

Gabbar, Hossam A.; Suzuki, Kazuhiko; Shimada, Yukiyasu

2001-01-01

Plant enterprise engineering environment (PEEE) is an approach aiming to manage the plant through its lifecycle. In such environment, safety is considered as the common objective for all activities throughout the plant lifecycle. One approach to achieve plant safety is to embed safety aspects within each function and activity within such environment. One ideal way to enable safety aspects within each automated function is through modeling. This paper proposes a theoretical approach to design plant safety model as integrated with the plant lifecycle model within such environment. Object-oriented modeling approach is used to construct the plant safety model using OO CASE tool on the basis of unified modeling language (UML). Multiple views are defined for plant objects to express static, dynamic, and functional semantics of these objects. Process safety aspects are mapped to each model element and inherited from design to operation stage, as it is naturally embedded within plant's objects. By developing and realizing the plant safety model, safer plant operation can be achieved and plant safety can be assured

Aquatic plants

DEFF Research Database (Denmark)

Madsen, T. V.; Sand-Jensen, K.

2006-01-01

Aquatic fl owering plants form a relatively young plant group on an evolutionary timescale. The group has developed over the past 80 million years from terrestrial fl owering plants that re-colonised the aquatic environment after 60-100 million years on land. The exchange of species between terre...... terrestrial and aquatic environments continues today and is very intensive along stream banks. In this chapter we describe the physical and chemical barriers to the exchange of plants between land and water.......Aquatic fl owering plants form a relatively young plant group on an evolutionary timescale. The group has developed over the past 80 million years from terrestrial fl owering plants that re-colonised the aquatic environment after 60-100 million years on land. The exchange of species between...

Plants, plant pathogens, and microgravity--a deadly trio

Science.gov (United States)

Leach, J. E.; Ryba-White, M.; Sun, Q.; Wu, C. J.; Hilaire, E.; Gartner, C.; Nedukha, O.; Kordyum, E.; Keck, M.; Leung, H.;

Plant life management optimized utilization of existing nuclear power plants

International Nuclear Information System (INIS)

Watzinger, H.; Erve, M.

1999-01-01

For safe, reliable and economical nuclear power generation it is of central importance to understand, analyze and manage aging-related phenomena and to apply this information in the systematic utilization and as-necessary extension of the service life of components and systems. An operator's overall approach to aging and plant life management which also improves performance characteristics can help to optimize plant operating economy. In view of the deregulation of the power generation industry with its increased competition, nuclear power plants must today also increasingly provide for or maintain a high level of plant availability and low power generating costs. This is a difficult challenge even for the newest, most modern plants, and as plants age they can only remain competitive if a plant operator adopts a strategic approach which takes into account the various aging-related effects on a plant-wide basis. The significance of aging and plant life management for nuclear power plants becomes apparent when looking at their age: By the year 2000 roughly fifty of the world's 434 commercial nuclear power plants will have been in operation for thirty years or more. According to the International Atomic Energy Agency, as many as 110 plants will have reached the thirty-year service mark by the year 2005. In many countries human society does not push the construction of new nuclear power plants and presumably will not change mind within the next ten years. New construction licenses cannot be expected so that for economical and ecological reasons existing plants have to be operated unchallengeably. On the other hand the deregulation of the power production market is asking just now for analysis of plant life time to operate the plants at a high technical and economical level until new nuclear power plants can be licensed and constructed. (author)

Dipping Strawberry Plants in Fungicides before Planting to Control Anthracnose

Directory of Open Access Journals (Sweden)

Myeong Hyeon Nam

2014-03-01

Full Text Available Anthracnose crown rot (ACR, caused by Colletotrichum fructicola, is a serious disease of strawberry in Korea. The primary inoculums of ACR were symptomless strawberry plants, plant debris, and other host plants. To effectively control anthracnose in symptomless transplanted strawberries, it is necessary to use diseasefree plants, detect the disease early, and apply a fungicide. Therefore, in 2010 and 2011, we evaluated the efficacy of pre-plant fungicide dips by using strawberry transplants infected by C. fructicola for the control of anthracnose. Dipping plants in prochloraz-Mn for 10 min before planting was most effective for controlling anthracnose in symptomless strawberry plants and resulted in more than 76% control efficacy. Azoxystrobin showed a control efficacy of over 40%, but plants treated with pyraclostrobin, mancozeb and iminoctadine tris showed high disease severity. The control efficacy of the dip treatment with prochloraz-Mn did not differ with temperature and time. Treatment with prochloraz-Mn for more than an hour caused growth suppression in strawberry plants. Therefore, the development of anthracnose can be effectively reduced by dipping strawberry plants for 10 min in prochloraz-Mn before planting.

„Bez Havránka si nikdo ani neškrtl.” Poválečné vztahy katedry českého jazyka pražské filozofické fakulty a akademického Ústavu pro jazyk český

Czech Academy of Sciences Publication Activity Database

Dvořáčková, Věra

2017-01-01

Roč. 57, č. 1 (2017), s. 105-122 ISSN 0323-0562 R&D Projects: GA ČR GA13-09541S Institutional support: RVO:67985921 Keywords : Czechoslovak Academy of Sciences * Faculty of Arts, Charles University * Bohuslav Havránek Subject RIV: AB - History OBOR OECD: History (history of science and technology to be 6.3, history of specific sciences to be under the respective headings)

Plant traits related to nitrogen uptake influence plant-microbe competition.

Science.gov (United States)

Moreau, Delphine; Pivato, Barbara; Bru, David; Busset, Hugues; Deau, Florence; Faivre, Céline; Matejicek, Annick; Strbik, Florence; Philippot, Laurent; Mougel, Christophe

2015-08-01

Plant species are important drivers of soil microbial communities. However, how plant functional traits are shaping these communities has received less attention though linking plant and microbial traits is crucial for better understanding plant-microbe interactions. Our objective was to determine how plant-microbe interactions were affected by plant traits. Specifically we analyzed how interactions between plant species and microbes involved in nitrogen cycling were affected by plant traits related to 'nitrogen nutrition in interaction with soil nitrogen availability. Eleven plant species, selected along an oligotrophic-nitrophilic gradient, were grown individually in a nitrogen-poor soil with two levels of nitrate availability. Plant traits for both carbon and nitrogen nutrition were measured and the genetic structure and abundance of rhizosphere. microbial communities, in particular the ammonia oxidizer and nitrate reducer guilds, were analyzed. The structure of the bacterial community in the rhizosphere differed significantly between plant species and these differences depended on nitrogen availability. The results suggest that the rate of nitrogen uptake per unit of root biomass and per day is a key plant trait, explaining why the effect of nitrogen availability on the structure of the bacterial community depends on the plant species. We also showed that the abundance of nitrate reducing bacteria always decreased with increasing nitrogen uptake per unit of root biomass per day, indicating that there was competition for nitrate between plants and nitrate reducing bacteria. This study demonstrates that nitrate-reducing microorganisms may be adversely affected by plants with a high nitrogen uptake rate. Our work puts forward the role of traits related to nitrogen in plant-microbe interactions, whereas carbon is commonly considered as the main driver. It also suggests that plant traits related to ecophysiological processes, such as nitrogen uptake rates, are more

Status report - expert knowledge of operators in fuel reprocessing plants, enrichment plants and fuel fabrication plants

International Nuclear Information System (INIS)

Preuss, W.; Kramer, J.; Wildberg, D.

1987-01-01

The necessary qualifications of the responsible personnel and the knowledge required by personnel otherwise employed in nuclear plants are among the requirements for licensing laid down in paragraph 7 of the German Atomic Energy Act. The formal regulations for nuclear power plants are not directly applicable to plants in the fuel cycle because of the differences in the technical processes and the plant and work organisation. The aim of the project was therefore to establish a possible need for regulations for the nuclear plants with respect to the qualification of the personnel, and to determine a starting point for the definition of the required qualifications. An extensive investigation was carried out in the Federal Republic of Germany into: the formal requirements for training; the plant and personnel organisation structures; the tasks carried out by the responsible and otherwise employed personnel; and the state of training. For this purpose plant owners and managers were interviewed and the literature and plant specific documentation (e.g. plant rules) were reviewed. On the basis of literature research, foreign practices were determined and used to make comparative evaluations. The status report is divided into three separate parts for the reprocessing, the uranium enrichment, and the manufacture of the fuel elements. On the basis of the situation for reprocessing plants (particularly that of the WAK) and fuel element manufacturing plants, the development of a common (not uniform) regulation for all the examined plants in the fuel cycle was recommended. The report gives concrete suggestions for the content of the regulations. (orig.) [de

Conservation law of plants' energy value dependence of plants ...

African Journals Online (AJOL)

The plants differences in biochemical composition are analyzed, and the conservation law of energy value in plants is obtained. The link between the need for the nutrients and the plants biochemical composition is examined, Liebig's law is specified. Keywords: plant's biochemical composition, biochemistry, energy value in ...

An Automated and Continuous Plant Weight Measurement System for Plant Factory.

Science.gov (United States)

Chen, Wei-Tai; Yeh, Yu-Hui F; Liu, Ting-Yu; Lin, Ta-Te

2016-01-01

In plant factories, plants are usually cultivated in nutrient solution under a controllable environment. Plant quality and growth are closely monitored and precisely controlled. For plant growth evaluation, plant weight is an important and commonly used indicator. Traditional plant weight measurements are destructive and laborious. In order to measure and record the plant weight during plant growth, an automated measurement system was designed and developed herein. The weight measurement system comprises a weight measurement device and an imaging system. The weight measurement device consists of a top disk, a bottom disk, a plant holder and a load cell. The load cell with a resolution of 0.1 g converts the plant weight on the plant holder disk to an analog electrical signal for a precise measurement. The top disk and bottom disk are designed to be durable for different plant sizes, so plant weight can be measured continuously throughout the whole growth period, without hindering plant growth. The results show that plant weights measured by the weight measurement device are highly correlated with the weights estimated by the stereo-vision imaging system; hence, plant weight can be measured by either method. The weight growth of selected vegetables growing in the National Taiwan University plant factory were monitored and measured using our automated plant growth weight measurement system. The experimental results demonstrate the functionality, stability and durability of this system. The information gathered by this weight system can be valuable and beneficial for hydroponic plants monitoring research and agricultural research applications.

An Automated and Continuous Plant Weight Measurement System for Plant Factory

Directory of Open Access Journals (Sweden)

Wei-Tai eChen

2016-03-01

Full Text Available In plant factories, plants are usually cultivated in nutrient solution under a controllable environment. Plant quality and growth are closely monitored and precisely controlled. For plant growth evaluation, plant weight is an important and commonly used indicator. Traditional plant weight measurements are destructive and laborious. In order to measure and record the plant weight during plant growth, an automated measurement system was designed and developed herein. The weight measurement system comprises a weight measurement device and an imaging system. The weight measurement device consists of a top disk, a bottom disk, a plant holder and a load cell. The load cell with a resolution of 0.1 g converts the plant weight on the plant holder disk to an analogue electrical signal for a precise measurement. The top disk and bottom disk are designed to be durable for different plant sizes, so plant weight can be measured continuously throughout the whole growth period, without hindering plant growth. The results show that plant weights measured by the weight measurement device are highly correlated with the weights estimated by the stereo-vision imaging system; hence, plant weight can be measured by either method. The weight growth of selected vegetables growing in the National Taiwan University plant factory were monitored and measured using our automated plant growth weight measurement system. The experimental results demonstrate the functionality, stability and durability of this system. The information gathered by this weight system can be valuable and beneficial for hydroponic plants monitoring research and agricultural research applications.

Plant walkdown

International Nuclear Information System (INIS)

Kostov, M.

2000-01-01

This report covers the following: preparatory steps for performing plant walk-down; the objective of the first plant walk-down; plant walk-down procedures; earthquake screening evaluation; walk-down documentation; second plant walk-down. The following objectives concerning the plant walk-down(s) were achieved. The plant system configuration is verified in order to proceed with event tree and fault tree analyses. Systems interactions, other types of dependencies or plant unique features are identified. he safety related components that are judged to generically possess high capacities (i.e., larger than the earthquake review level) have been verified to contain no weaknesses. Further analyses needed to establish the capacities of remaining safety-related components are identified and necessary field data are obtained. Information on components is obtained to assist in HCLPF (fragility) evaluation and peer review of the seismic margin study

Konec akademické svobody v éře neoliberalismu?/ The End of Academic Freedom in the Era of Neoliberalism?

Directory of Open Access Journals (Sweden)

Kateřina Lojdová

2016-04-01

Full Text Available Tento článek diskutuje možné konsekvence neoliberalismu pro současné university. Zaměřuje se v perspektivě kritické pedagogiky na možné konflikty neoliberalismu s akademickou svobodou jakožto hlavní součástí akademického ducha na univerzitách. Článek je rozdělen do dvou částí. První část přibližuje kritickou pedagogiku, její kořeny a současnou podobu, včetně limitů, které tento koncept má. Druhá část se již v kriticko-pedagogickém pohledu věnuje neoliberální proměně výzkumu a výuky na univerzitách na příkladu pedagogických fakult. Závěr nastiňuje možnosti kritické pedagogiky k pěstování akademického ducha na univerzitách. Shledává je například ve výzkumu nezávislém na grantových schématech, avšak relevantních pro odbornou komunitu, v citlivém managementu univerzit a v kurikulu pregraduální přípravy učitelů akcentujícím spíše svobodného učitele nežli kompetenční orientaci vzdělávání diktovanou shora. Článek tak ústí do smířlivé vize udržitelného akademického života, která balancuje na pomezí mezi ekonomickou dimenzí univerzit na straně jedné a akademickou svobodou nezávislou na trhu práce na straně druhé.

Spektrální radiometry pro měření světelných podmínek pro růst rostlin

Czech Academy of Sciences Publication Activity Database

Oupický, Pavel

2006-01-01

Roč. 51, č. 10 (2006), s. 270-273 ISSN 0447-6441 R&D Projects: GA AV ČR(CZ) 1QS100820502 Institutional research plan: CEZ:AV0Z20430508 Keywords : Radiometer * spectral * plant * growth Subject RIV: BH - Optics, Masers, Lasers

Advanced plant design recommendations from Cook Nuclear Plant experience

International Nuclear Information System (INIS)

Zimmerman, W.L.

1993-01-01

A project in the American Electric Power Service Corporation to review operating and maintenance experience at Cook Nuclear Plant to identify recommendations for advanced nuclear plant design is described. Recommendations so gathered in the areas of plant fluid systems, instrument and control, testing and surveillance provisions, plant layout of equipment, provisions to enhance effective maintenance, ventilation systems, radiological protection, and construction, are presented accordingly. An example for a design review checklist for effective plant operations and maintenance is suggested

PlantDB – a versatile database for managing plant research

Directory of Open Access Journals (Sweden)

Gruissem Wilhelm

2008-01-01

Full Text Available Abstract Background Research in plant science laboratories often involves usage of many different species, cultivars, ecotypes, mutants, alleles or transgenic lines. This creates a great challenge to keep track of the identity of experimental plants and stored samples or seeds. Results Here, we describe PlantDB – a Microsoft® Office Access database – with a user-friendly front-end for managing information relevant for experimental plants. PlantDB can hold information about plants of different species, cultivars or genetic composition. Introduction of a concise identifier system allows easy generation of pedigree trees. In addition, all information about any experimental plant – from growth conditions and dates over extracted samples such as RNA to files containing images of the plants – can be linked unequivocally. Conclusion We have been using PlantDB for several years in our laboratory and found that it greatly facilitates access to relevant information.

One dimensional reactor core model

International Nuclear Information System (INIS)

Kostadinov, V.; Stritar, A.; Radovo, M.; Mavko, B.

1984-01-01

The one dimensional model of neutron dynamic in reactor core was developed. The core was divided in several axial nodes. The one group neutron diffusion equation for each node is solved. Feedback affects of fuel and water temperatures is calculated. The influence of xenon, boron and control rods is included in cross section calculations for each node. The system of equations is solved implicitly. The model is used in basic principle Training Simulator of NPP Krsko. (author)

The Baltic Klint beneath the central Baltic Sea and its comparison with the North Estonian Klint

Science.gov (United States)

Tuuling, Igor; Flodén, Tom

2016-06-01

Along its contact with the Baltic Shield, the margin of the East European Platform reveals a well-developed, flooded terraced relief. The most striking and consistent set of escarpments at the contact of the Lower Palaeozoic calcareous and terrigenous rocks, known as the Baltic Klint (BK), extends from northwest of Russia to the Swedish island of Öland. Marine seismic reflection profiling in 1990-2004 revealed the central Baltic Sea Klint (BSK) section in detail and enabled comparison of its geology/geomorphology with a classical klint-section onshore, namely the North Estonian Klint (NEK). The conception of the BK onshore, which is based on the land-sea separating terraced relief in northern Estonia, is not fully applicable beneath the sea. Therefore, we consider that the BSK includes the entire terraced Cambrian outcrop. We suggest the term "Baltic Klint Complex" to include the well-terraced margin of the Ordovician limestone outcrop, which is weakly developed in Estonia. Because of a steady lithological framework of the bedrock layers across the southern slope of the Fennoscandian Shield, the central BSK in the western and the NEK in the eastern part of the Baltic Homocline have largely identical morphologies. The North Estonian Ordovician limestone plateau with the calcareous crest of the BK extends across the central Baltic Sea, whereas morphological changes/variations along the Klint base occur due to the east-westerly lithostratigraphic/thickness changes in the siliciclastic Cambrian sequence. The verge of the NEK, located some 30-50 m above sea level, starts to drop in altitude as its east-westerly course turns to northeast-southwest in western Estonia. Further westwards, the BK shifts gradually into southerly deepening (0.1-0.2°) layers as its crest drops to c. 150 m below sea level (b.s.l.) near Gotska Sandön. This course change is accompanied by a considerable decrease in thickness of the platform sedimentary cover, as below the central Baltic Sea the

Top 10 plant viruses in molecular plant pathology.

Science.gov (United States)

Scholthof, Karen-Beth G; Adkins, Scott; Czosnek, Henryk; Palukaitis, Peter; Jacquot, Emmanuel; Hohn, Thomas; Hohn, Barbara; Saunders, Keith; Candresse, Thierry; Ahlquist, Paul; Hemenway, Cynthia; Foster, Gary D

2011-12-01

Many scientists, if not all, feel that their particular plant virus should appear in any list of the most important plant viruses. However, to our knowledge, no such list exists. The aim of this review was to survey all plant virologists with an association with Molecular Plant Pathology and ask them to nominate which plant viruses they would place in a 'Top 10' based on scientific/economic importance. The survey generated more than 250 votes from the international community, and allowed the generation of a Top 10 plant virus list for Molecular Plant Pathology. The Top 10 list includes, in rank order, (1) Tobacco mosaic virus, (2) Tomato spotted wilt virus, (3) Tomato yellow leaf curl virus, (4) Cucumber mosaic virus, (5) Potato virus Y, (6) Cauliflower mosaic virus, (7) African cassava mosaic virus, (8) Plum pox virus, (9) Brome mosaic virus and (10) Potato virus X, with honourable mentions for viruses just missing out on the Top 10, including Citrus tristeza virus, Barley yellow dwarf virus, Potato leafroll virus and Tomato bushy stunt virus. This review article presents a short review on each virus of the Top 10 list and its importance, with the intent of initiating discussion and debate amongst the plant virology community, as well as laying down a benchmark, as it will be interesting to see in future years how perceptions change and which viruses enter and leave the Top 10. © 2011 The Authors. Molecular Plant Pathology © 2011 BSPP and Blackwell Publishing Ltd.

Nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

Data concerning the existing nuclear power plants in the world are presented. The data was retrieved from the SIEN (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: nuclear plants, its status and type; installed nuclear power plants by country; nuclear power plants under construction by country; planned nuclear power plants by country; cancelled nuclear power plants by country; shut-down nuclear power plants by country. (E.G.) [pt

Evolutionary responses of native plant species to invasive plants : a review

OpenAIRE

Oduor, Ayub M. O.

2013-01-01

Strong competition from invasive plant species often leads to declines in abundances and may,in certain cases, cause localized extinctions of native plant species. Nevertheless, studies have shown that certain populations of native plant species can co-exist with invasive plant species, suggesting the possibility of adaptive evolutionary responses of those populations to the invasive plants. Empirical inference of evolutionary responses of the native plant species to invasive plants has invol...

[Review on application of plant growth retardants in medicinal plants cultivation].

Science.gov (United States)

Zhai, Yu-Yao; Guo, Bao-Lin; Cheng, Ming

2013-09-01

Plant growth retardants are widely used in cultivation of medicinal plant, but there is still lack of scientific guidance. In order to guide the use of plant growth retardants in medicinal plant cultivation efficiently and reasonably, this paper reviewed the mechanism, function characteristic, plant and soil residue of plant growth retardants, such as chlorocholine chloride, mepiquat chloride, paclobutrazol, unicnazle and succinic acid, and summarized the application of plant growth retardants in medicinal plants cultivation in recent years, with focus on the effect of growth and yield of the officinal organs and secondary metabolites.

Evolutionary responses of native plant species to invasive plants: a review.

Science.gov (United States)

Oduor, Ayub M O

2013-12-01

Strong competition from invasive plant species often leads to declines in abundances and may, in certain cases, cause localized extinctions of native plant species. Nevertheless, studies have shown that certain populations of native plant species can co-exist with invasive plant species,suggesting the possibility of adaptive evolutionary responses of those populations to the invasive plants. Empirical inference of evolutionary responses of the native plant species to invasive plants has involved experiments comparing two conspecific groups of native plants for differences in expression of growth/reproductive traits: populations that have experienced competition from the invasive plant species (i.e. experienced natives) versus populations with no known history of interactions with the invasive plant species (i.e. naıve natives). Here, I employ a meta-analysis to obtain a general pattern of inferred evolutionary responses of native plant species from 53 such studies. In general, the experienced natives had significantly higher growth/reproductive performances than naıve natives, when grown with or without competition from invasive plants.While the current results indicate that certain populations of native plant species could potentially adapt evolutionarily to invasive plant species, the ecological and evolutionary mechanisms that probably underlie such evolutionary responses remain unexplored and should be the focus of future studies.

Analysis of plant height between male sterile plants obtained by space flight and male fertile plants in Maize

International Nuclear Information System (INIS)

Cao Moju; Huang Wenchao; Pan Guangtang; Rong Tingzhao; Zhu Yingguo

2004-01-01

F 2 fertility segregation population and the sister-cross fertility segregation population, which descended from the male sterile material, were analysed by their plant height of different growing stage between 2 populations of male sterile plants and male fertile plants. The plant height of different fertility plants come to the significance at 0.01 level in different stage through the whole growing period. The differences become more and more large with the development of plants, the maximum difference happens in adult stage. The increasing amount of different stage also shows significance at 0.01 level between two kinds of different fertility plants

Configuration management of plant modifications for nuclear power plants

International Nuclear Information System (INIS)

Ritsch, W.J.

1987-01-01

Due to the increasing complexity of nuclear power plant operation, regulatory pressure, and the large numbers of people required to operate and support the stations, the control of plant modifications at these plants needs to be expanded and improved. The aerospace and defense industries, as well as the owners or operators of large energy projects have established configuration management programs (CMPs) to control plant design changes. These programs are composed of well-defined functions for identifying, evaluating, recording, tracking, issuing, and documenting the established baseline conditions, as well as required changes to these baseline conditions. The purpose of this paper is to describe a recommended CMP for plant modifications consisting of a computerized data base installed on the utility's computer to provide a central storage of plant design and operations data necessary to control the following activities as they are affected by plant design changes: training; record management; operations; maintenance; health physics; planning/scheduling; procurement/inventory control; outage management (including modifications); and emergency response

Plant diversity surpasses plant functional groups and plant productivity as driver of soil biota in the long term.

Directory of Open Access Journals (Sweden)

Nico Eisenhauer

2011-01-01

Full Text Available One of the most significant consequences of contemporary global change is the rapid decline of biodiversity in many ecosystems. Knowledge of the consequences of biodiversity loss in terrestrial ecosystems is largely restricted to single ecosystem functions. Impacts of key plant functional groups on soil biota are considered to be more important than those of plant diversity; however, current knowledge mainly relies on short-term experiments.We studied changes in the impacts of plant diversity and presence of key functional groups on soil biota by investigating the performance of soil microorganisms and soil fauna two, four and six years after the establishment of model grasslands. The results indicate that temporal changes of plant community effects depend on the trophic affiliation of soil animals: plant diversity effects on decomposers only occurred after six years, changed little in herbivores, but occurred in predators after two years. The results suggest that plant diversity, in terms of species and functional group richness, is the most important plant community property affecting soil biota, exceeding the relevance of plant above- and belowground productivity and the presence of key plant functional groups, i.e. grasses and legumes, with the relevance of the latter decreasing in time.Plant diversity effects on biota are not only due to the presence of key plant functional groups or plant productivity highlighting the importance of diverse and high-quality plant derived resources, and supporting the validity of the singular hypothesis for soil biota. Our results demonstrate that in the long term plant diversity essentially drives the performance of soil biota questioning the paradigm that belowground communities are not affected by plant diversity and reinforcing the importance of biodiversity for ecosystem functioning.

Analysis of containment parameters during the main steam line break with the failure of the feedwater control valves

International Nuclear Information System (INIS)

Fabjan, L.; Petelin, S.; Mavko, B.; Gortnar, O.; Tiselj, I.

1992-01-01

U.S. Nuclear Regulatory Commission (NRC) information notice 91-69: 'Errors in Main Steam Line Break Analyses for Determining Containment Parameters' shows the possibility of an accident which could lead to beyond design containment pressure and temperature. Such accident would be caused by the continuation of feedwater flow following a main stream line break (MSLB) inside the containment. Krsko power plant already experienced problems with main feedwater control valves. For that reason, analysis of MSLB has been performed taking into account continuous feedwater addition scenario and different containment safety systems capabilities availability. Steam and water released into the containment during MSLB was calculated using RELAP5/MOD2 computer code. The containment response to MSLB was calculated using CONTEMPT-LT/028 computer code. The results indicated that the continuous feedwater flow following a MSLB could lead to beyond design containment pressure. The peak pressure and temperature depend on isolation time for main- and auxiliary-feedwater supply. In the case of low boron concentration injection, the core recriticality is characteristic for this type of accidents. It was concluded that the presented analysis of MSLB with continuous feedwater addition scenario is the worst case for containment design

Real time source term and dose assessment

International Nuclear Information System (INIS)

Breznik, B.; Kovac, A.; Mlakar, P.

2001-01-01

The Dose Projection Programme is a tool for decision making in case of nuclear emergency. The essential input data for quick emergency evaluation in the case of hypothetical pressurised water reactor accident are following: source term, core damage assessment, fission product radioactivity, release source term and critical exposure pathways for an early phase of the release. A reduced number of radio-nuclides and simplified calculations can be used in dose calculation algorithm. Simple expert system personal computer programme has been developed for the Krsko Nuclear Power Plant for dose projection within the radius of few kilometers from the pressurised water reactor in early phase of an accident. The input data are instantaneous data of core activity, core damage indicators, release fractions, reduction factor of the release pathways, spray operation, release timing, and dispersion coefficient. Main dose projection steps are: accurate in-core radioactivity determination using reactor power input; core damage and in-containment source term assessment based on quick indications of instrumentation or on activity analysis data; user defines release pathway for typical PWR accident scenarius; dose calculation is performed only for exposure pathway critical for decision about evacuation or sheltering in early phase of an accident.(author)

Perspectives on plant vulnerabilities ampersand other plant and containment improvements

International Nuclear Information System (INIS)

LaChance, J.; Kolaczkowski, A.; Kahn, J.

1996-01-01

The primary goal of the Individual Plant Examination (IPE) Program was for licensees to identify plant-unique vulnerabilities and actions to address these vulnerabilities. A review of these vulnerabilities and plant improvements that were identified in the IPEs was performed as part of the IPE Insights Program sponsored by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this effort was to characterize the identified vulnerabilities and the impact of suggested plant improvements. No specific definition for open-quotes vulnerabilityclose quotes was provided in NRC Generic Letter 88-20 or in the subsequent NRC IPE submittal guidance documented in NUREG-1335. Thus licensees were left to use their own definitions. Only 20% of the plants explicitly stated that they had vulnerabilities. However, most licensees identified other plant improvements to address issues not explicitly classified as vulnerabilities, but pertaining to areas in which overall plant safety could potentially be increased. The various definitions of open-quotes vulnerabilityclose quotes used by the licensees, explicitly identified vulnerabilities, proposed plant improvements to address these vulnerabilities, and other plant improvements are summarized and discussed

Life management plants at nuclear power plants PWR

International Nuclear Information System (INIS)

Esteban, G.

2014-01-01

Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

Historical plant cost and annual production expenses for selected electric plants, 1982

International Nuclear Information System (INIS)

1984-01-01

This publication is a composite of the two prior publications, Hydroelectric Plant Construction Cost and Annual Production Expenses and Thermal-Electric Plant Construction Cost and Annual Production Expenses. Beginning in 1979, Thermal-Electric Plant Construction Cost and Annual Production Expenses contained information on both steam-electric and gas-turbine electric plant construction cost and annual production expenses. The summarized historical plant cost described under Historical Plant Cost in this report is the net cumulative-to-date actual outlays or expenditures for land, structures, and equipment to the utility. Historical plant cost is the initial investment in plant (cumulative to the date of initial commercial operation) plus the costs of all additions to the plant, less the value of retirements. Thus, historical plant cost includes expenditures made over several years, as modifications are made to the plant. Power Production Expenses is the reporting year's plant operation and maintenance expenses, including fuel expenses. These expenses do not include annual fixed charges on plant cost (capital costs) such as interest on debt, depreciation or amortization expenses, and taxes. Consequently, total production expenses and the derived unit costs are not the total cost of producing electric power at the various plants. This publication contains data on installed generating capacity, net generation, net capability, historical plant cost, production expenses, fuel consumption, physical and operating plant characteristics, and other relevant statistical information for selected plants

Aquatic Plant Control Research Program. Allelopathic Aquatic Plants for Aquatic Plant Management: A Feasibility Study

Science.gov (United States)

1989-10-01

1978. " Ecotoxicology of aquatic plant communi- ties," Principles of Ecotoxicology , SCOPE Report 12, Chapter 11, pp 239-255. [Heavy metals, Pollutants...Phragmites communis and Equisetum limosum were cultivated . They found plant-plant influences depend on soil type. Typha latifolia, S. A2 lacustris, and

Archeological monitoring at Munga and Sepa streets in the old town of Viljandi / Andres Tvauri, Kärt Metsoja

Index Scriptorium Estoniae

Tvauri, Andres, 1970-

2014-01-01

Kogu Munga tänava alal oli jälgitav punase liiva kihistus. Varasemate uuringute põhjal on teada, et see sillutis pärineb keskajast. Sillutise alune kiht sisaldas leide, mida võib dateerida 13. sajandi keskpaigast 14. sajandi keskpaigani. Sillutise pealne kiht sisaldas rohkesti leide 16. sajandi teisest poolest. Sepa tänava lääneküljel avastati keskaegse kivihoone müürid.

Making Plant-Support Structures From Waste Plant Fiber

Science.gov (United States)

Morrow, Robert C.; < oscjmocl. < attjew K/; {ertzbprm. A,amda; Ej (e. Cjad); Hunt, John

2006-01-01

Environmentally benign, biodegradable structures for supporting growing plants can be made in a process based on recycling of such waste plant fiber materials as wheat straw or of such derivative materials as paper and cardboard. Examples of structures that can be made in this way include plant plugs, pots, planter-lining mats, plant fences, and root and shoot barriers. No chemical binders are used in the process. First, the plant material is chopped into smaller particles. The particles are leached with water or steam to remove material that can inhibit plant growth, yielding a fibrous slurry. If the desired structures are plugs or sheets, then the slurry is formed into the desired shapes in a pulp molding subprocess. If the desired structures are root and shoot barriers, pots, or fences, then the slurry is compression-molded to the desired shapes in a heated press. The processed materials in these structures have properties similar to those of commercial pressboard, but unlike pressboard, these materials contain no additives. These structures have been found to withstand one growth cycle, even when wet

Chapter 15. Plant pathology and managing wildland plant disease systems

Science.gov (United States)

David L. Nelson

2004-01-01

Obtaining specific, reliable knowledge on plant diseases is essential in wildland shrub resource management. However, plant disease is one of the most neglected areas of wildland resources experimental research. This section is a discussion of plant pathology and how to use it in managing plant disease systems.

Biogeographical diversity of plant associated microbes in arcto-alpine plants

NARCIS (Netherlands)

Kumar, Manoj Gopala Krishnan

2016-01-01

Terrestrial plants and microbes have co-evolved since the emergence of the former on Earth. Associations with microorganisms can be either beneficial or detrimental for plants. Microbes can be found in the soil surrounding the plant roots, but also in all plant tissues, including seeds. In

Exotic plant species attack revegetation plants in post-coal mining areas

Science.gov (United States)

Yusuf, Muhammad; Arisoesilaningsih, Endang

2017-11-01

This study aimed to explore some invasive exotic plant species that have the potential to disrupt the growth of revegetation plants in post-coal mining areas. This research was conducted in a revegetation area of PT, Amanah Anugerah Adi Mulia (A3M) Kintap site, South Borneo. Direct observation was carried out on some revegetation areas by observing the growth of revegetation plants disturbed by exotic plant species and the spread of exotic plant species. Based on observation, several invasive exotic plant species were identified including Mikania cordata, Centrosema pubescence, Calopogonium mucunoides, Mimosa pudica, Ageratum conyzoides, and Chromolaena odorata. These five plant species grew wild in the revegetation area and showed ability to disrupt the growth of other plants. In some tree species, such as Acacia mangium, Paraserianthes falcataria, M. cordata could inhibit the growth and even kill the trees through covering the tree canopy. So, the trees could not receive optimum sun light for photosynthesis processes. M. cordata was also observed to have the most widespread distribution. Several exotic plant species such as C. mucunoides, M. pudica, and A. conyzoides were observed to have deep root systems compared with plant species used for revegetation. This growth characteristic allowed exotic plant species to win the competition for nutrient absorption with other plant species.

Electronic plants

Science.gov (United States)

Stavrinidou, Eleni; Gabrielsson, Roger; Gomez, Eliot; Crispin, Xavier; Nilsson, Ove; Simon, Daniel T.; Berggren, Magnus

2015-01-01

The roots, stems, leaves, and vascular circuitry of higher plants are responsible for conveying the chemical signals that regulate growth and functions. From a certain perspective, these features are analogous to the contacts, interconnections, devices, and wires of discrete and integrated electronic circuits. Although many attempts have been made to augment plant function with electroactive materials, plants’ “circuitry” has never been directly merged with electronics. We report analog and digital organic electronic circuits and devices manufactured in living plants. The four key components of a circuit have been achieved using the xylem, leaves, veins, and signals of the plant as the template and integral part of the circuit elements and functions. With integrated and distributed electronics in plants, one can envisage a range of applications including precision recording and regulation of physiology, energy harvesting from photosynthesis, and alternatives to genetic modification for plant optimization. PMID:26702448

Stress tolerant plants

OpenAIRE

Rubio, Vicente; Iniesto Sánchez, Elisa; Irigoyen Miguel, María Luisa

2014-01-01

[EN] The invention relates to transgenic plants and methods for modulating abscisic acid (ABA) perception and signal transduction in plants. The plants find use in increasing yield in plants, particularly under abiotic stress.

The application of plant information system on third Qinshan nuclear power plant

International Nuclear Information System (INIS)

Liu Wangtian

2005-01-01

Plant overall control has been applied in Qinshan Nuclear Power Plant, which enhances the security of plant operation, but it is not enough to improve the technical administration level. In order to integrate the overall information and to improve the technical administration level more. Third Qinshan Nuclear Power Plant applies the plant information system. This thesis introduces the application of plant information system in Third Qinshan Nuclear Power Plant and the effect to the plant after the system is carried into execution, in addition, it does more analysis and exceptions for application of plant information system in the future. (authors)

Linking plant nutritional status to plant-microbe interactions.

Science.gov (United States)

Carvalhais, Lilia C; Dennis, Paul G; Fan, Ben; Fedoseyenko, Dmitri; Kierul, Kinga; Becker, Anke; von Wiren, Nicolaus; Borriss, Rainer

2013-01-01

Plants have developed a wide-range of adaptations to overcome nutrient limitation, including changes to the quantity and composition of carbon-containing compounds released by roots. Root-associated bacteria are largely influenced by these compounds which can be perceived as signals or substrates. Here, we evaluate the effect of root exudates collected from maize plants grown under nitrogen (N), phosphate (P), iron (Fe) and potassium (K) deficiencies on the transcriptome of the plant growth promoting rhizobacterium (PGPR) Bacillus amyloliquefaciens FZB42. The largest shifts in gene expression patterns were observed in cells exposed to exudates from N-, followed by P-deficient plants. Exudates from N-deprived maize triggered a general stress response in FZB42 in the exponential growth phase, which was evidenced by the suppression of numerous genes involved in protein synthesis. Exudates from P-deficient plants induced bacterial genes involved in chemotaxis and motility whilst exudates released by Fe and K deficient plants did not cause dramatic changes in the bacterial transcriptome during exponential growth phase. Global transcriptional changes in bacteria elicited by nutrient deficient maize exudates were significantly correlated with concentrations of the amino acids aspartate, valine and glutamate in root exudates suggesting that transcriptional profiling of FZB42 associated with metabolomics of N, P, Fe and K-deficient maize root exudates is a powerful approach to better understand plant-microbe interactions under conditions of nutritional stress.

Plant diversity and plant identity influence Fusarium communities in soil.

Science.gov (United States)

LeBlanc, Nicholas; Kinkel, Linda; Kistler, H Corby

2017-01-01

Fusarium communities play important functional roles in soil and in plants as pathogens, endophytes, and saprotrophs. This study tests how rhizosphere Fusarium communities may vary with plant species, changes in the diversity of the surrounding plant community, and soil physiochemical characteristics. Fusarium communities in soil associated with the roots of two perennial prairie plant species maintained as monocultures or growing within polyculture plant communities were characterized using targeted metagenomics. Amplicon libraries targeting the RPB2 locus were generated from rhizosphere soil DNAs and sequenced using pyrosequencing. Sequences were clustered into operational taxonomic units (OTUs) and assigned a taxonomy using the Evolutionary Placement Algorithm. Fusarium community composition was differentiated between monoculture and polyculture plant communities, and by plant species in monoculture, but not in polyculture. Taxonomic classification of the Fusarium OTUs showed a predominance of F. tricinctum and F. oxysporum as well of the presence of a clade previously only found in the Southern Hemisphere. Total Fusarium richness was not affected by changes in plant community richness or correlated with soil physiochemical characteristics. However, OTU richness within two predominant phylogenetic lineages within the genus was positively or negatively correlated with soil physiochemical characteristics among samples within each lineage. This work shows that plant species, plant community richness, and soil physiochemical characteristics may all influence the composition and richness of Fusarium communities in soil.

Plant Density Effect in Different Planting Dates on Growth Indices, Yield and

Directory of Open Access Journals (Sweden)

F Azizi

2013-04-01

Full Text Available In order to determine the appropriate plant density in different planting dates for sweet corn cultivar KSC403su, an experiment was conducted using a randomized complete block design in split plot lay out with three replications at Seed and Plant Improvement Institute in Karaj in 2006. Three planting dates (22 May, 5 June and 22 June were assigned as main plots and three plant densities (65000, 75000 and 85000 plants per hectare were considered as sub plots. Effect of planting date on row/ear, 1000 kernels weight, biological yield and harvest index was significant at 1% probability level and it was significant at 5% probability level for kernels/ear row and grain yield. All traits decreased with postponement of planting date to 5 June except for row/ear, kernels/row and grain yield. More delay in planting from 22 May to 22 June caused that grain yield was decreased significantly about 32.5% (from 14.45 to 9.78 ton/ha. Effect of plant density was significant at 1% probability level for all the traits. All of the traits decreased significantly with increasing plant density except for biological yield. The highest grain yield was resulted from 65000 plants per hectare density (14.20 ton/ha. Interaction effect of planting date and plant density was significant at 5% probability level for biological yield and harvest index but it wasn’t significant for the other traits. Growth indices decreased with delay in planting date and increasing plant density. Only leaf area index increased in more plant densities. From the results of this experiment it might be resulted that appropriate planting date to produce the highest grain yield is 22 May to 5 June for sweet corn cultivar KSC403su and also the highest grain yield can obtain from 65000 plants per hectare density.

Medicinal Plants.

Science.gov (United States)

Phillipson, J. David

1997-01-01

Highlights the demand for medicinal plants as pharmaceuticals and the demand for health care treatments worldwide and the issues that arise from this. Discusses new drugs from plants, anticancer drugs, antiviral drugs, antimalarial drugs, herbal remedies, quality, safety, efficacy, and conservation of plants. Contains 30 references. (JRH)

Regulatory requirements for desalination plant coupled with nuclear reactor plant

International Nuclear Information System (INIS)

Yune, Young Gill; Kim, Woong Sik; Jo, Jong Chull; Kim, Hho Jung; Song, Jae Myung

2005-01-01

A small-to-medium sized reactor has been developed for multi-purposes such as seawater desalination, ship propulsion, and district heating since early 1990s in Korea. Now, the construction of its scaled-down research reactor, equipped with a seawater desalination plant, is planned to demonstrate the safety and performance of the design of the multi-purpose reactor. And the licensing application of the research reactor is expected in the near future. Therefore, a development of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant is necessary for the preparation of the forthcoming licensing review of the research reactor. In this paper, the following contents are presented: the design of the desalination plant, domestic and foreign regulatory requirements relevant to desalination plants, and a draft of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant

Plant simulator

International Nuclear Information System (INIS)

Fukumitsu, Hiroyuki

1998-01-01

A simulator of a reactor plant of the present invention comprises a plurality of distributed computers, an indication processing section and an operation section. The simulation calculation functions of various kinds of plant models in the plant are shared by the plurality of computers. The indication processing section controls collection of data of the plant simulated by the computers and instructions of an operator. The operation section is operated by the operator and the results of operation are transmitted to the indication processing section, to conduct operation trainings and display the results of the simulation. Each of the computers and the indication processing portion are connected with each other by a network having a memory for common use. Data such as the results of calculation of plant models and various kinds of parameters of the plant required commonly to the calculators and the indication processing section are stored in the common memory, and adapted to be used by way of the network. (N.H.)

[Distribution of HCB discharged from a chemical plant in plants].

Science.gov (United States)

Chen, Jing; Wang, Lin-Ling; Lu, Xiao-Hua; Yuan, Song-Hu; Liu, Xi-Xiang; Wang, Yue; Zhao, Qian; Mei, Ling-Fang

2009-04-15

The distribution characteristics of hexachlorobenzene (HCB) in plant and rhizosphere soil in contamination conduit, a nearby river and a cropland were studied and the impact factors were also discussed. The results are summarized as follows: the range of the HCB concentration in plant and rhizosphere soil in investigation area were respectively from 4.45 microg x kg(-1) to 1,189.89 microg x kg(-1) (dw) and from 27.93 microg x kg(-1) to 3,480.71 microg x kg(-1) (dw). Higher enrichment of HCB in woodplant than herbs due to higher fat concentration in woodplant in the contamination conduit and the rich concentrtion factor of woodplant and herbs were 0.41-2.55 and 0.01-1.34. The range of HCB concentrations in plants in nearby croplands was significantly wide (4.45-333.1 microg x kg(-1)) while HCB concentrations in different parts of plant were various, e.g. HCB concentrations in fruit, root and shoot of taro were 318.77 microg x kg(-1), 281.02 microg x kg(-1) and 10.94 microg x kg(-1). There was a remarkable positive relation between the concentrations of HCB in plant and fat concentration of plant while no relativity between the concentrations of HCB in plant and those in ground soils in the contamination conduit and cropland. The concentration levels of HCB in plant and rhizosphere soil in river were dramatically decreased with increasing distance from contaminated conduit. There was a remarkable positive relation between the concentrations of HCB in plant and those in ground soils but no relation between concentrations of HCB in plant and fat concentration of plant in river. The distribution characteristics of HCB in plants were influenced by contaminated levels, fat concentration and Partition-transfer model.

Plant extraction process

DEFF Research Database (Denmark)

2006-01-01

A method for producing a plant extract comprises incubating a plant material with an enzyme composition comprising a lipolytic enzyme.......A method for producing a plant extract comprises incubating a plant material with an enzyme composition comprising a lipolytic enzyme....

Integrating Studies on Plant-Pollinator and Plant-Herbivore Interactions

NARCIS (Netherlands)

Lucas-Barbosa, Dani

2016-01-01

Research on herbivore-induced plant defence and research on pollination ecology have had a long history of separation. Plant reproduction of most angiosperm species is mediated by pollinators, and the effects of herbivore-induced plant defences on pollinator behaviour have been largely neglected.

On-line acquisition of plant related and environmental parameters (plant monitoring) in gerbera: determining plant responses

NARCIS (Netherlands)

Baas, R.; Slootweg, G.

2004-01-01

For on-line plant monitoring equipment to be functional in commercial glasshouse horticulture, relations between sensor readings and plant responses on both the short (days) and long term (weeks) are required. For this reason, systems were installed to monitor rockwool grown gerbera plants on a

Flow-induced vibration analysis of a helical coil steam generator experiment using large eddy simulation

Energy Technology Data Exchange (ETDEWEB)

Yuan, Haomin; Solberg, Jerome; Merzari, Elia; Kraus, Adam; Grindeanu, Iulian

2017-10-01

This paper describes a numerical study of flow-induced vibration in a helical coil steam generator experiment conducted at Argonne National Laboratory in the 1980s. In the experiment, a half-scale sector model of a steam generator helical coil tube bank was subjected to still and flowing air and water, and the vibrational characteristics were recorded. The research detailed in this document utilizes the multi-physics simulation toolkit SHARP developed at Argonne National Laboratory, in cooperation with Lawrence Livermore National Laboratory, to simulate the experiment. SHARP uses the spectral element code Nek5000 for fluid dynamics analysis and the finite element code DIABLO for structural analysis. The flow around the coil tubes is modeled in Nek5000 by using a large eddy simulation turbulence model. Transient pressure data on the tube surfaces is sampled and transferred to DIABLO for the structural simulation. The structural response is simulated in DIABLO via an implicit time-marching algorithm and a combination of continuum elements and structural shells. Tube vibration data (acceleration and frequency) are sampled and compared with the experimental data. Currently, only one-way coupling is used, which means that pressure loads from the fluid simulation are transferred to the structural simulation but the resulting structural displacements are not fed back to the fluid simulation

Plutonium Plant, Trombay

International Nuclear Information System (INIS)

Yadav, J.S.; Agarwal, K.

2017-01-01

The journey of Indian nuclear fuel reprocessing started with the commissioning of Plutonium Plant (PP) at Trombay on 22"n"d January, 1965 with an aim to reprocess the spent fuel from research reactor CIRUS. The basic process chosen for the plant was Plutonium Uranium Reduction EXtraction (PUREX) process. In seventies, the plant was subjected to major design modifications and replacement of hardware, which later met the additional demand from research reactor DHRUVA. The augmented plutonium plant has been operating since 1983. Experience gained from this plant was very much helpful to design future reprocessing plant in the country

[Intoxications with plants].

Science.gov (United States)

Kupper, Jacqueline; Reichert, Cornelia

2009-05-01

Ingestions of plants rarely lead to life-threatening intoxications. Highly toxic plants, which can cause death, are monkshood (Aconitum sp.), yew (Taxus sp.) and autumn crocus (Colchicum autumnale). Lethal ingestions of monkshood and yew are usually suicides, intoxications with autumn crocus are mostly accidental ingestions of the leaves mistaken for wild garlic (Allium ursinum). Severe intoxications can occur with plants of the nightshade family like deadly nightshade (Atropa belladonna), angel's trumpet (Datura suaveolens) or jimsonweed (Datura stramonium). These plants are ingested for their psychoactive effects. Ingestion of plant material by children most often only causes minor symptoms or no symptoms at all, as children usually do not eat great quantities of the plants. They are especially attracted by the colorful berries. There are plants with mostly cardiovascular effects like monkshood, yew and Digitalis sp. Some of the most dangerous plants belong to this group. Plants of the nightshade family cause an anticholinergic syndrome. With golden chain (Laburnum anagyroides), castor bean (Ricinus communis) and raw beans (Phaseolus vulgaris) we see severe gastrointestinal effects. Autumn crocus contains a cell toxin, colchicine, which leads to multiorgan failure. Different plants are irritative or even caustic to the skin. Treatment is usually symptomatic. Activated charcoal is administered within one hour after ingestion (1 g/kg). Endoscopic removal of plant material can be considered with ingestions of great quantities of highly toxic plants. Administration of repeated doses of charcoal (1-2 g/h every 2-4 hours) may be effective in case of oleander poisoning. There exist only two antidotes: Anti-digoxin Fab fragments can be used with cardenolide glycoside-containing plants (Digitalis sp., Oleander). Physostigmine is the antidote for severe anticholinergic symptoms of the CNS. Antibodies against colchicine, having been developed in France, are not available at

Plant life management and maintenance technologies for nuclear power plants

International Nuclear Information System (INIS)

Ikegami, Tsukasa; Aoki, Masataka; Shimura, Takao; Kaimori, Kimihiro; Koike, Masahiro

2001-01-01

Nuclear power generation occupying an important position for energy source in Japan and supplying about one third of total electric power usage is now required for further upgrading of its economics under regulation relaxation of electric power business. And, under execution retardation of its new planning plant, it becomes important to operate the already established plants for longer term and to secure their stability. Therefore, technical development in response to the plant life elongation is promoted under cooperation of the Ministry of Economics and Industries, electric power companies, literate, and plant manufacturers. Under such conditions, the Hitachi, Ltd. has progressed some technical developments on check inspection, repairs and maintenance for succession of the already established nuclear power plants for longer term under securing of their safety and reliability. And in future, by proposing the check inspection and maintenance program combined with these technologies, it is planned to exert promotion of maintenance program with minimum total cost from a viewpoint of its plant life. Here were described on technologies exerted in the Hitachi, Ltd. such as construction of plant maintenance program in response to plant life elongation agreeing with actual condition of each plant, yearly change mechanism grasping, life evaluation on instruments and materials necessary for maintenance, adequate check inspection, repairs and exchange, and so forth. (G.K.)

Plant life management

International Nuclear Information System (INIS)

Charbonneau, S.; Framatome, J.B.

1992-01-01

Plant life assessment and extension studies have been performed by numerous companies all over the world. Critical equipment has been identified as well as various degradation mechanisms involved in the plant aging process. Nowadays one has to think what to implement to improve the existing situation in the Nuclear Power Plant (NPP). FRAMATOME has undertaken this thought process in order to find the right answers and bring them to utilities facing either critical concern for plant life extension or the problem of management of power plant potential longevity. This is why we prepared a Plant Life Improvement Action Plan, comprising 10 (ten) major items described hereafter using examples of work performed by FRAMATOME for its utility customers desiring to manage the lives of their plants, both in France with EDF and abroad

Plant Research '75

Energy Technology Data Exchange (ETDEWEB)

1975-01-01

Research is reported on stomatal regulation of the gas exchanges between plant and environment; inhibitory effects in flower formation; plant growth and development through hormones; hormone action; development and nitrogen fixation in algae; primary cell wall glycoprotein ectensin; enzymic mechanisms and control of polysaccharide and glycoprotein synthesis; molecular studies of membrane studies; sensory transduction in plants; regulation of formation of protein complexes and enzymes in higher plant cell and mechanism of sulfur dioxide toxicity in plants. (PCS)

Plant air systems safety study: Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

1982-05-01

The Portsmouth Gaseous Diffusion Plant Air System facilities and operations are reviewed for potential safety problems not covered by standard industrial safety procedures. Information is presented under the following section headings: facility and process description (general); air plant equipment; air distribution system; safety systems; accident analysis; plant air system safety overview; and conclusion

PlantCV v2: Image analysis software for high-throughput plant phenotyping

Directory of Open Access Journals (Sweden)

Malia A. Gehan

2017-12-01

Full Text Available Systems for collecting image data in conjunction with computer vision techniques are a powerful tool for increasing the temporal resolution at which plant phenotypes can be measured non-destructively. Computational tools that are flexible and extendable are needed to address the diversity of plant phenotyping problems. We previously described the Plant Computer Vision (PlantCV software package, which is an image processing toolkit for plant phenotyping analysis. The goal of the PlantCV project is to develop a set of modular, reusable, and repurposable tools for plant image analysis that are open-source and community-developed. Here we present the details and rationale for major developments in the second major release of PlantCV. In addition to overall improvements in the organization of the PlantCV project, new functionality includes a set of new image processing and normalization tools, support for analyzing images that include multiple plants, leaf segmentation, landmark identification tools for morphometrics, and modules for machine learning.

Are atomic power plants saver than nuclear power plants

International Nuclear Information System (INIS)

Roeglin, H.C.

1977-01-01

It is rather impossible to establish nuclear power plants against the resistance of the population. To prevail over this resistance, a clarification of the citizens-initiatives motives which led to it will be necessary. This is to say: It is quite impossible for our population to understand what really heappens in nuclear power plants. They cannot identify themselves with nuclear power plants and thus feel very uncomfortable. As the total population feels the same way it is prepared for solidarity with the citizens-initiatives even if they believe in the necessity of nuclear power plants. Only an information-policy making transparent the social-psychological reasons of the population for being against nuclear power plants could be able to prevail over the resistance. More information about the technical procedures is not sufficient at all. (orig.) [de

Stem parasitic plant Cuscuta australis (dodder) transfers herbivory-induced signals among plants.

Science.gov (United States)

Hettenhausen, Christian; Li, Juan; Zhuang, Huifu; Sun, Huanhuan; Xu, Yuxing; Qi, Jinfeng; Zhang, Jingxiong; Lei, Yunting; Qin, Yan; Sun, Guiling; Wang, Lei; Baldwin, Ian T; Wu, Jianqiang

2017-08-08

Cuscuta spp. (i.e., dodders) are stem parasites that naturally graft to their host plants to extract water and nutrients; multiple adjacent hosts are often parasitized by one or more Cuscuta plants simultaneously, forming connected plant clusters. Metabolites, proteins, and mRNAs are known to be transferred from hosts to Cuscuta , and Cuscuta bridges even facilitate host-to-host virus movement. Whether Cuscuta bridges transmit ecologically meaningful signals remains unknown. Here we show that, when host plants are connected by Cuscuta bridges, systemic herbivory signals are transmitted from attacked plants to unattacked plants, as revealed by the large transcriptomic changes in the attacked local leaves, undamaged systemic leaves of the attacked plants, and leaves of unattacked but connected hosts. The interplant signaling is largely dependent on the jasmonic acid pathway of the damaged local plants, and can be found among conspecific or heterospecific hosts of different families. Importantly, herbivore attack of one host plant elevates defensive metabolites in the other systemic Cuscuta bridge-connected hosts, resulting in enhanced resistance against insects even in several consecutively Cuscuta -connected host plants over long distances (> 100 cm). By facilitating plant-to-plant signaling, Cuscuta provides an information-based means of countering the resource-based fitness costs to their hosts.

PlantPAN: Plant promoter analysis navigator, for identifying combinatorial cis-regulatory elements with distance constraint in plant gene groups

Directory of Open Access Journals (Sweden)

Huang Hsien-Da

2008-11-01

Full Text Available Abstract Background The elucidation of transcriptional regulation in plant genes is important area of research for plant scientists, following the mapping of various plant genomes, such as A. thaliana, O. sativa and Z. mays. A variety of bioinformatic servers or databases of plant promoters have been established, although most have been focused only on annotating transcription factor binding sites in a single gene and have neglected some important regulatory elements (tandem repeats and CpG/CpNpG islands in promoter regions. Additionally, the combinatorial interaction of transcription factors (TFs is important in regulating the gene group that is associated with the same expression pattern. Therefore, a tool for detecting the co-regulation of transcription factors in a group of gene promoters is required. Results This study develops a database-assisted system, PlantPAN (Plant Promoter Analysis Navigator, for recognizing combinatorial cis-regulatory elements with a distance constraint in sets of plant genes. The system collects the plant transcription factor binding profiles from PLACE, TRANSFAC (public release 7.0, AGRIS, and JASPER databases and allows users to input a group of gene IDs or promoter sequences, enabling the co-occurrence of combinatorial transcription factor binding sites (TFBSs within a defined distance (20 bp to 200 bp to be identified. Furthermore, the new resource enables other regulatory features in a plant promoter, such as CpG/CpNpG islands and tandem repeats, to be displayed. The regulatory elements in the conserved regions of the promoters across homologous genes are detected and presented. Conclusion In addition to providing a user-friendly input/output interface, PlantPAN has numerous advantages in the analysis of a plant promoter. Several case studies have established the effectiveness of PlantPAN. This novel analytical resource is now freely available at http://PlantPAN.mbc.nctu.edu.tw.

Biografická glosa: Šedesátiny Františka Znebejánka

Directory of Open Access Journals (Sweden)

Helena Kubátová

2017-10-01

Full Text Available V květnu 2011 oslavil významné životní jubileum PhDr. František Znebejánek, Ph.D., odborný asistent na Katedře sociologie a andragogiky Filozofické fakulty Univerzity Palackého v Olomouci. V neposlední řadě tak ovšem jubiluje také významný člen redakční rady časopisu Historická sociologie.

International assistance for the implementation of the modernization programme of Kozloduy NPP, units 5 and 6

International Nuclear Information System (INIS)

Almarza, J.; Ivanov, A.; Velichkov, V.

2001-01-01

The project provides assistance and adequate information to the companies acting as guarantors on the Bulgarian side, i. e. SAEER, Natsionalna Elektricheska Kompania (NEK) and other Bulgarian institutions, in order to control the investment and the Implementation Project progress. In addition, it provides assistance to the KNPP management during the programme implementation, and appropriate training for the key personnel in positions related to the Management, Investment Process and Technical Process (quality of the supplies). (author)

Los Alamos Nuclear Plant Analyzer: an interactive power-plant simulation program

International Nuclear Information System (INIS)

Steinke, R.; Booker, C.; Giguere, P.; Liles, D.R.; Mahaffy, J.H.; Turner, M.R.

1984-01-01

The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware-adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

Nuclear Plant Analyzer: an interactive TRAC/RELAP Power-Plant Simulation Program

International Nuclear Information System (INIS)

Steinke, R.; Booker, C.; Giguere, P.; Liles, D.; Mahaffy, J.; Turner, M.; Wiley, R.

1984-01-01

The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis