Analysis of PACTEL small break LOCA experiment using TRACE

A small break loss-of-coolant accident (SBLOCA) is one of problems investigated in an NPP operation. Such accident can be analyzed using an experiment facility and TRACE thermal-hydraulic system code. A series of SBLOCA experiments was carried out on Parallel Channel Test Loop (PACTEL) facility, exploited together with Technical Research Centre of Finland VTT Energy and Lappeenranta University of Technology (LUT), in order to investigate two-phase phenomena related to a VVER-type reactor. The experiments and a TRACE model of the PACTEL facility are described in the paper. In addition, there is the TRACE code description with main field equations. At the work, calculations of a SBLOCA series are implemented and after the calculations, the thesis discusses the validation of TRACE and concludes with an assessment of the usefulness and accuracy of the code in calculating small breaks.

Analysis of PWR-PACTEL Small Break LOCA experiment using TRACE

Currently, the power generation is one of the most significant life aspects for the whole man-kind. Barely one can imagine our life without electricity and thermal energy. Thus, different technologies for producing those types of energy need to be used. Each of those technologies will always have their own advantages and disadvantages. Nevertheless, every technology must satisfy such requirements as efficiency, ecology safety and reliability. In the matter of the power generation with nuclear energy utilization these requirements needs to be highly main-tained, especially since accidents on nuclear power plants may cause very long term deadly consequences. In order to prevent possible disasters related to the accident on a nuclear power plant strong and powerful algorithms were invented in last decades. Such algorithms are able to manage calculations of different physical processes and phenomena of real facilities. How-ever, the results acquired by the computing must be verified with experimental data.

Scaling analysis of small break experiments in PACTEL

The purpose of this thesis is to study the scalability of small break LOCA experiments. The study is performed on the experimental data, as well as on the results of thermal hydraulic computation performed on TRACE code. The SBLOCA experiments were performed on PACTEL facility situated at LUT. The temporal scaling of the results was done by relating the total coolant mass in the system with the initial break mass flow and using the quotient to scale the experiment time. The results showed many similarities in the behaviour of pressure and break mass flow between the experiments.

Experiment data report for LOFT anticipated transient with multiple failures experiment L9-1 and small break experiment L3-3 /

"Published June 1981."

Accident Management Actions In An Upper-Head Small-Break Loss-Of-Coolant Accident With High-Pressure Safety Injection Failed

Since the Three Mile Island accident, an important focus of pressurized water reactor (PWR) transient analyses has been a small-break loss-of-coolant accident (SBLOCA). In 2002, the discovery of thinning of the vessel head wall at the Davis Besse nuclear power plant reactor indicated the possibility of an SBLOCA in the upper head of the reactor vessel as a result of circumferential cracking of a control rod drive mechanism penetration nozzle - which has cast even greater importance on the study of SBLOCAs. Several experimental tests have been performed at the Large Scale Test Facility to simulate the behavior of a PWR during an upper-head SBLOCA. The last of these tests, Organisation for Economic Co-operation and Development Nuclear Energy Agency Rig of Safety Assessment (OECD/NEA ROSA) Test 6.1, was performed in 2005. This test was simulated with the TRACE 5.0 code, and good agreement with the experimental results was obtained. Additionally, a broad analysis of an upper-head SBLOCA with high-pressure safety injection failed in a Westinghouse PWR was performed taking into account different accident management actions and conditions in order to check their suitability. This issue has been analyzed also in the framework of the OECD/NEA ROSA project and the Code Applications and Maintenance Program (CAMP). The main conclusion is that the current emergency operating procedures for Westinghouse reactor design are adequate for these kinds of sequences, and they do not need to be modified.

Interdisciplinarity and Design Conceptualisation: Contributions from a Small-Scale Design Experiment

Literature emphasises the sparse research focused in collaborative and open approaches in the design conceptualisation stage, also known as the Fuzzy Front-End (FFE). Presently, the most challenging discussion arising from this specific field of research lies in understanding on whether or not to structure the referred conceptual stage. Accordingly, the established hypothesis behind this study sustains that a structured approach in the FFE would benefit the interdisciplinary dialogue. Therefore, two objectives support this study: to understand the benefits of an interdisciplinary approach in the FFE, and to test one proposed model for this conceptual stage. By means of a small-scale design experiment, this paper pretends to give additional contributions to this area of research, in the context of new product development (NPD). The general research supporting this specific study aims to conceptualise in the area of newly and futuristic aircraft configurations. Hence, this same topic based the conceptualisation process in the conducted ideation sessions, which are conducted by five different teams of three elements each. The results of the different ideation sessions reinforce the contemporary paradigm of Open Innovation (OI), which is based in trust and communication to better collaborate. The postulated hypothesis for this study is partially validated as teams testing the proposed and structured model generally consider that its usage would benefit the integration of different disciplines. Besides, a general feeling that a structured approach integrates different perspectives and gives creativity a focus pervades. Nevertheless, the small-scale of the design experiment attributes some limitations to this study, despite giving new insights in how to better organise coming and more sustained studies. Interestingly, the importance of sketching as an interdisciplinary means of communication is underlined with the obtained results.

Experimental thermal hydraulic studies on the enhancement of safety of LWRs

The safe use of nuclear power plants (NPPs) requires a deep understanding of the functioning of physical processes and systems involved. Studies on thermal hydraulics have been carried out in various separate effects and integral test facilities at Lappeenranta University of Technology (LUT) either to ensure the functioning of safety systems of light water reactors (LWR) or to produce validation data for the computer codes used in safety analyses of NPPs. Several examples of safety studies on thermal hydraulics of the nuclear power plants are discussed. Studies are related to the physical phenomena existing in different processes in NPPs, such as rewetting of the fuel rods, emergency core cooling (ECC), natural circulation, small break loss-of-coolant accidents (SBLOCA), non-condensable gas release and transport, and passive safety systems. Studies on both VVER and advanced light water reactor (ALWR) systems are included. The set of cases include separate effects tests for understanding and modeling a single physical phenomenon, separate effects tests to study the behavior of a NPP component or a single system, and integral tests to study the behavior of the whole system. In the studies following steps can be found, not necessarily in the same study. Experimental studies as such have provided solutions to existing design problems. Experimental data have been created to validate a single model in a computer code. Validated models are used in various transient analyses of scaled facilities or NPPs. Integral test data are used to validate the computer codes as whole, to see how the implemented models work together in a code. In the final stage test results from the facilities are transferred to the NPP scale using computer codes. Some of the experiments have confirmed the expected behavior of the system or procedure to be studied; in some experiments there have been certain unexpected phenomena that have caused changes to the original design to avoid the recognized problems. This is the main motivation for experimental studies on thermal hydraulics of the NPP safety systems. Naturally the behavior of the new system designs have to be checked with experiments, but also the existing designs, if they are applied in the conditions that differ from what they were originally designed for. New procedures for existing reactors and new safety related systems have been developed for new nuclear power plant concepts. New experiments have been continuously needed.

Laskentamalli PKL-koelaitteiston pienen vuodon kokeen simuloimiseksi Apros-ohjelmistolla

Työn tavoitteena oli tehdä Apros-laskentamalli PKL-koelaitteistosta ja testata kuinka hyvin Apros pystyy laskemaan PKL-koelaitteistolla suoritetun E2.2 pienen vuodon kokeen. Tavoitteena oli myös tarkastella boorittoman veden tulpan etenemistä pienen vuodon kokeen aikana. PKL-koelaitteisto vastaa saksalaista sähköteholtaan 1300 MW olevaa Philippsburg 2 painevesilaitosta. Koelaitteiston tilavuudet ja teho on skaalattu kertoimella 145. Työssä tehdyllä laskentamallilla tarkasteltiin boorittoman veden tulpan liikkumista pienen vuodon kokeen aikana. Kun malli oli valmis, laskenta suoritettiin Apros 5.05 versiolla. Boorittoman veden tulpan etenemisen laskennassa käytettiin toisen kertaluvun diskretointia, jolla booripitoisuuden muutokset säilyvät teräväreunaisina. Laskentamalli pystyi kuvaamaan koelaitteistolla suoritetussa pienen vuodon kokeessa tapahtuneet ilmiöt varsin hyvin. Eroa koetuloksiintuli pääkiertopiirien luonnonkiertojen alkamishetkistä ja primääripaineen käyttäytymisessä. Kokeen alkutilanne ei ollut stationääritila, joten alkutilanteen asettamisessa oli hankaluuksia. Varsinkin pääkiertopiirien veden pinnankorkeuksienasettamisessa oli vaikeuksia, koska veden pinnankorkeuksien erot pyrkivät tasoittumaan nopeasti kokeen aikana. Apros pystyi laskemaan PKL-koelaitteistolla suoritetun pienen vuodon kokeen hyvin. Mallilla tulisi kuitenkin laskea vielä toisentyyppisiäkin kokeita, ennen kuin voidaan varmuudella tietää mallin toimivuus. PKL-koelaitteisto vastaa pääpiirteiltään Suomeen rakennettavaa Olkiluoto 3 ydinvoimalaitosta. Tehty työ antaa lisävarmuutta, kun Olkiluoto 3 laitoksen turvallisuustarkasteluita tehdään.

High Plains Ag Lab Rotations Show Fallow Still Works in Western Nebraska

The High Plains Ag Laboratory (HPAL) in Sidney, Nebraska is the dryland research site for the University of Nebraska located in the Panhandle. In addition to the typical small plot agriculture experiment areas, there is a significant dryland production area. There are a total of 718.5 acres in production, divided into 27 individual fields, ranging from the smallest unit at 19.7 acres to the largest at 36.7 acres. Within these fields there are presently seven different crop rotations, each with winter wheat as the base crop, including everything from the traditional wheat-fallow system to a continuous cropping system.

Stretching dependence of the vibration modes of a single-molecule Pt-H2-Pt bridge

A conducting bridge of a single hydrogen molecule between Pt electrodes is formed in a break junction experiment. It has a conductance near the quantum unit, G0=2e2∕h, carried by a single channel. Using point-contact spectroscopy three vibration modes are observed and their variation upon isotope substitution is obtained. The stretching dependence for each of the modes allows uniquely classifying them as longitudinal or transversal modes. The interpretation of the experiment in terms of a Pt-H2-Pt bridge is verified by density-functional theory calculations for the stability, vibrational modes, and conductance of the structure.

Propulsive small expendable deployer system experiment

Relatively short electrodynamic tethers can extract orbital energy to "push" against a planetary magnetic field to achieve propulsion without the expenditure of propellant. The Propulsive Small Expendable Deployer System experiment will use the flight-proven Small Expendable Deployer System to deploy a 5-km bare aluminum tether from a Delta II upper stage to achieve ~0.4-N drag thrust, thus lowering the altitude of the stage. The experiment will use a predominantly bare tether for current collection in lieu of the endmass collector and insulated tether used on previous missions. The flight experiment is a precursor to a more ambitious electrodynamic tether upper-stage demonstration mission that will be capable of orbit-raising,lowering, and inclination changes, all using electrodynamic thrust. The expected performance of the tether propulsion system during the experiment is described.

Experiment in assessing color separation techniques for identifying small density variations in tires. Interim report.

National Highway Traffic Safety Administration, Research Institute, Washington, D.C.

Small business guide for getting a clean break : good for business and the environment /

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