The geology of the Olkiluoto area

International Nuclear Information System (INIS)

Anttila, P.; Paulamaeki, S.; Lindberg, A.; Paananen, M.; Koistinen, T.; Front, K.; Pitkaenen, P.

1992-12-01

Teollisuuden Voima Oy (TVO) is preparing for the final disposal of spent nuclear fuel from the Olkiluoto nuclear power plant deep in the Finnish bedrock. An area close to the power plant at Olkiluoto, Eurajoki, was one of the five areas selected in 1987 for the preliminary site investigations. A summary of the geological conditions at the Olkiluoto site is presented in the report

Beliefs concerning the reliability of nuclear power plant in-service inspections; Uskomuksia ydinvoimalaitoksissa suoritettavien tarkastusten luotettavuudesta

Energy Technology Data Exchange (ETDEWEB)

Kettunen, J. [VTT Automation, Espoo (Finland)

1997-01-01

The aim of the study was to investigate belief systems held by the officials responsible for the planning and supervision of NDT operations within the Finnish nuclear industry. They were asked to express their opinions on (1) the reliability of NDT methods in general, (2) the factors influencing the reliability of in-service inspections, and (3) the degree of reliability of the current inspections operations conducted by means of NDT methods in the Finnish nuclear power plants. Another goal of the study was to assess the adequacy of officials` beliefs (or belief systems). The research data was collected by interviewing representatives from Finnish power companies (Imatran Voima Oy and Teollisuuden Voima Oy), independent inspection organisations, and the Finnish Centre for Radiation and Nuclear Safety (STUK). The adequacy of the beliefs expressed was assessed by means of the results obtained from international NDT reliability studies and on the basis of interviewees` own justification. (refs.).

Beliefs concerning the reliability of nuclear power plant in-service inspections

International Nuclear Information System (INIS)

Kettunen, J.

1997-01-01

The aim of the study was to investigate belief systems held by the officials responsible for the planning and supervision of NDT operations within the Finnish nuclear industry. They were asked to express their opinions on (1) the reliability of NDT methods in general, (2) the factors influencing the reliability of in-service inspections, and (3) the degree of reliability of the current inspections operations conducted by means of NDT methods in the Finnish nuclear power plants. Another goal of the study was to assess the adequacy of officials' beliefs (or belief systems). The research data was collected by interviewing representatives from Finnish power companies (Imatran Voima Oy and Teollisuuden Voima Oy), independent inspection organisations, and the Finnish Centre for Radiation and Nuclear Safety (STUK). The adequacy of the beliefs expressed was assessed by means of the results obtained from international NDT reliability studies and on the basis of interviewees' own justification. (refs.)

Human and organisational factors influencing the reliability of non-destructive testing. An international literary survey

International Nuclear Information System (INIS)

Kettunen, J.; Norros, L.

1996-04-01

The aim of the study is to chart human and organisational factors influencing the reliability of non-destructive testing (NDT). The emphasis will be in ultrasonic testing (UT) and in the planning and execution of in-service inspections during nuclear power plant maintenance outages. Being a literary survey this study is mainly based on the foreign and domestic research available on the topic. In consequence, the results presented in this report reflect the ideas of international research community. In addition to this, Finnish nuclear power plant operators (Imatran Voima Oy and Teollisuuden Voima Oy), independent inspection organisations and the Finnish Centre for Radiation and Nuclear Safety have provided us with valuable information on NDT theory and practice. Especially, a kind of 'big picture' of non-destructive testing has been pursued in the study. (6 figs., 2 tabs.)

Human and organisational factors influencing the reliability of non-destructive testing. An international literary survey; Inhimillisten ja organisatoristen tekijoeiden yhteys NDT- tarkastusten luotettavuuteen. Katsaus kansainvaeliseen kirjallisuuteen

Energy Technology Data Exchange (ETDEWEB)

Kettunen, J.; Norros, L.

1996-04-01

The aim of the study is to chart human and organisational factors influencing the reliability of non-destructive testing (NDT). The emphasis will be in ultrasonic testing (UT) and in the planning and execution of in-service inspections during nuclear power plant maintenance outages. Being a literary survey this study is mainly based on the foreign and domestic research available on the topic. In consequence, the results presented in this report reflect the ideas of international research community. In addition to this, Finnish nuclear power plant operators (Imatran Voima Oy and Teollisuuden Voima Oy), independent inspection organisations and the Finnish Centre for Radiation and Nuclear Safety have provided us with valuable information on NDT theory and practice. Especially, a kind of `big picture` of non-destructive testing has been pursued in the study. (6 figs., 2 tabs.).

A critical review of published groundwater flow models for safety of nuclear waste disposal

International Nuclear Information System (INIS)

Laine, E.

1997-04-01

Flow models have been simulated for the potential nuclear waste sites in Precambrian bedrock of Finland in the Technical Research Centre of Finland (VTT). The work had been commissioned by Teollisuuden Voima Oy. In the present study, the published flow models are critically reviewed. The work concentrates on qualitative evaluation of the applied equivalent continuum approach applied to crystalline bedrock. Special attention is paid to the use of the geological information in connection with flow modelling. (35 refs., 6 figs.)

Local opinion - the impact of visitor centre two studies at Olkiluoto

International Nuclear Information System (INIS)

Aemmaelae, V.M.

1993-01-01

Teollisuuden Voima Oy (TVO) has recently commissioned two opinion polls about attitudes towards nuclear power. The target group of the first research was teachers in the nearby community. The subject of the poll was attitudes towards nuclear power and the impact of a visit. The second research handles the company image of TVO target groups being local elected officials, press, teachers and local representatives of trade organizations. The aim of these two studies was to measure the impact of the company's information and visits activities to the attitudes. (author)

Application of the REMIX thermal mixing calculation program for the Loviisa reactor

International Nuclear Information System (INIS)

Kokkonen, I.; Tuomisto, H.

1987-08-01

The REMIX computer program has been validated to be used in the pressurized thermal shock study of the Loviisa reactor pressure vessel. The program has been verified against the data from the thermal and fluid mixing experiments. These experiments have been carried out in Imatran voima Oy to study thermal mixing of the high-pressure safety injection water in the Loviisa VVER-440 type pressurized water reactor. The verified REMIX-versions were applied to reactor calculations in the probabilistic pressurized thermal shock study of the Loviisa Plant

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

International Nuclear Information System (INIS)

Aurela, Jorma; Koivisto, Katarina

2000-01-01

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

Fuel cycle management in Finland

International Nuclear Information System (INIS)

Vaeyrynen, H.; Mikkola, I.

1987-01-01

Both Finnish utilities producing nuclear power - Imatran Voima Oy (IVO) and Teollisuuden Voima Oy (Industrial Power Co. Ltd, TVO) - have created efficient fuel cycle management systems. The systems however differ in almost all respects. The reason is that the principal supplier for IVO is the Soviet Union and for TVO is Sweden. A common feature of both systems at the front end of the cycle is the building of stockpiles in order to provide for interruptions in fuel deliveries. Quality assurance supervision at the fuel factory for IVO is regulated by the Soviet Chamber of Commerce and Industry and a final control is made in Finland. The in-core fuel management is done by IVO using codes developed in Finland. The whole IVO fuel cycle is basically a leasing arrangement. The spent fuel is returned to the USSR after five years cooling. TVO carries out the in-core fuel management using a computer code system supplied by Asea-Atom. TVO is responsable for the back end of the cycle and makes preparations for the final disposal of the spent fuel in Finland. 6 refs., 2 figs

Regulatory control of nuclear safety in Finland. Annual report 1998

Energy Technology Data Exchange (ETDEWEB)

Tossavainen, K. [ed.

1999-10-01

The report describes regulatory control of the safe use of nuclear energy by the Radiation and Nuclear Safety Authority (STUK) in 1998. STUK is the Finnish nuclear safety authority. The submission of this report to the Ministry of Trade and Industry is stipulated in Section 121 of the Nuclear Energy Decree. It was verified by regulatory control that the operation of Finnish NPPs was in compliance with conditions set out in the operating licences of the plants and with regulations currently in force. In addition to supervising the normal operation of the plants, STUK oversaw projects carried out at the plant units, which related to the uprating of their power and the improvement of their safety. STUK issued to the Ministry of Trade and Industry a statement about applications for the renewal of the operating licences of Loviisa and Olkiluoto NPPs, which had been submitted by Imatran Voima Oy and Teollisuuden Voima Oy. Regulatory activities in the field of nuclear waste management were focused on the storage and final disposal of spent fuel as well as the treatment, storage and final disposal of reactor waste. STUK issued a statement to the Ministry of Trade and Industry about an environmental impact assessment programme pertaining to a spent fuel repository project, which had been submitted by Posiva Oy, as well as on Imatran Voima Oy's application concerning the operation of a repository for medium- and low-level reactor waste from Loviisa NPP. The use of nuclear materials was in compliance with the regulations currently in force and also the whereabouts of every batch of nuclear material were ensured by safeguards control. In international safeguards, important changes took place, which were reflected also in safeguards activities at national level. International co-operation continued based on financing both from STUK's budget and from additional sources. The focus of co-operation funded from outside sources was as follows: improvement of the safety of

Regulatory control of nuclear safety in Finland. Annual report 1998

International Nuclear Information System (INIS)

Tossavainen, K.

1999-10-01

The report describes regulatory control of the safe use of nuclear energy by the Radiation and Nuclear Safety Authority (STUK) in 1998. STUK is the Finnish nuclear safety authority. The submission of this report to the Ministry of Trade and Industry is stipulated in Section 121 of the Nuclear Energy Decree. It was verified by regulatory control that the operation of Finnish NPPs was in compliance with conditions set out in the operating licences of the plants and with regulations currently in force. In addition to supervising the normal operation of the plants, STUK oversaw projects carried out at the plant units, which related to the uprating of their power and the improvement of their safety. STUK issued to the Ministry of Trade and Industry a statement about applications for the renewal of the operating licences of Loviisa and Olkiluoto NPPs, which had been submitted by Imatran Voima Oy and Teollisuuden Voima Oy. Regulatory activities in the field of nuclear waste management were focused on the storage and final disposal of spent fuel as well as the treatment, storage and final disposal of reactor waste. STUK issued a statement to the Ministry of Trade and Industry about an environmental impact assessment programme pertaining to a spent fuel repository project, which had been submitted by Posiva Oy, as well as on Imatran Voima Oy's application concerning the operation of a repository for medium- and low-level reactor waste from Loviisa NPP. The use of nuclear materials was in compliance with the regulations currently in force and also the whereabouts of every batch of nuclear material were ensured by safeguards control. In international safeguards, important changes took place, which were reflected also in safeguards activities at national level. International co-operation continued based on financing both from STUK's budget and from additional sources. The focus of co-operation funded from outside sources was as follows: improvement of the safety of Kola and

Parliament's decision specified the energy policy in Finland

International Nuclear Information System (INIS)

Aurela, J.

2002-01-01

The Finnish Parliament decided on Friday 24 May 2002, to ratify the favourable decision-in-principle on the fifth nuclear power plant unit made by the Government last January, with 107 votes in favour and 92 votes against. Thus Teollisuuden Voima Oy (TVO), the Finnish privately owned electricity generation company responsible for the project, is authorised to continue the preparations for the construction of a new nuclear power plant unit. The article handles the process in the coming years if TVO will go on with the process. The most important steps according to the nuclear legislation are to have construction and operating licenses in due time. (author)

Bedrock model of the Veitsivaara area

International Nuclear Information System (INIS)

Saksa, P.; Kuivamaeki, A.; Kurimo, M.; Anttila, P.; Front, K.; Pitkaenen, P.; Korkealaakso, J.; Vaittinen, T.

1993-07-01

Site investigations were carried out at Veitsivaara, in 1987-1991 in accordance with an investigation programme for radioactive waste disposal drawn up by Teollisuuden Voima Oy (TVO). The site was modelled in terms of rock types, fracturing, fracture structures and geophysical conditions, the main focus of examination was on fracturing and associated hydraulic conductivity. The various properties of the bedrock structures were classified by means a three-dimensional model. The descriptions of the models were stored in a computer system for illustration purposes. The rock types at Veitsivaara are tonalite gneiss, Tuliniemet potassium granite, amphipolite, granite porphyry and metadiabase, the last two of which occur in dykes

SAFIR. The Finnish research programme on nuclear power plant safety 2003-2006. Executive summary

International Nuclear Information System (INIS)

Puska, E.

2006-12-01

Major part of Finnish public research on nuclear power plant safety during the years 2003-2006 has been carried out in the SAFIR programme. The programme has been administrated by the steering group that was nominated by the Ministry of Trade and Industry (KTM). The steering group of SAFIR has consisted of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Trade and Industry (KTM), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oy (TVO), Fortum Power and Heat Oy, Fortum Nuclear Services Oy (Fortum), Finnish Funding Agency for Technology and Innovation (Tekes), Helsinki University of Technology (TKK) and Lappeenranta University of Technology (LTY). The key research areas of SAFIR have been (1) reactor fuel and core, (2) reactor circuit and structural safety, (3) containment and process safety functions, that was divided in 2005 into (3a) thermal hydraulics and (3b) severe accidents, (4) automation, control room and IT, (5) organisations and safety management and (6) risk-informed safety management. The research programme has included annually from 20 up to 24 research projects, whose volume has varied from a few person months to several person years. The total volume of the programme during the four year period 2003-2006 has been 19.7 million euros and 148 person years. The research in the programme has been carried out primarily by Technical Research Centre of Finland (VTT). Other research units responsible for the projects include Lappeenranta University of Technology, Fortum Nuclear Services Oy, Helsinki University of Technology and RAMSE Consulting Oy. In addition, there have been a few minor subcontractors in some projects. The programme management structure has consisted of the steering group, a reference group in each of the seven research areas and a number of ad hoc groups in the various research areas. This report gives a short summary of the results of the SAFIR programme for the period January 2003 - November

Bedrock model of the Olkiluoto area

International Nuclear Information System (INIS)

Saksa, P.; Paananen, M.; Paulamaeki, S.; Anttila, P.; Front, K.; Pitkaenen, P.; Hassinen, P.; Ylinen, A.

1993-07-01

Site investigations were carried out at Olkiluoto (in Finland) in 1987-1992 in accordance with an investigation programme drawn up by Teollisuuden Voima Oy (TVO). The site was modelled in terms of rock types, fracturing, fracture structures and geohydrological conditions, the main focus of examination was on fracturing and associated hydraulic conductivity. The various properties of the bedrock structures were classified by means of a three-dimensional model. The descriptions of the models were gathered in a computer system for illustration and storage purposes. The rock types at Olkiluoto are migmatite, which may be divided into mica gneiss and veined gneiss, and also tonalite and coarse-grained migmatite granite (pegmatite). (64 refs., 65 figs.)

TVO-92 safety analysis of spent fuel disposal

International Nuclear Information System (INIS)

Vieno, T.; Hautojaervi, A.; Koskinen, L.; Nordman, H.

1993-08-01

The spent fuel from the TVO I and TVO II reactors at the Olkiluoto nuclear power plant is planned to be disposed in a repository constructed at a depth of about 500 meters in crystalline bedrock. Teollisuuden Voima Oy (TVO) has carried out preliminary site investigations for spent fuel disposal between 1987 and 1992 at five areas in Finland (Olkiluoto, Kivetty, Romuvaara, Syyry and Veitsivaara). The Safety analysis of the disposal system is presented in the report. Spent fuel will be encapsulated in composite copper-steel canisters. The canister design (ACP canister) consists of an inner container of steel as a load-bearing element and an outer container of oxygen-free copper to provide a shield against corrosion. In the repository the canisters will be emplaced in vertical holes drilled in the floors of horizontal deposition tunnels. The annulus between the canister and the rock is filled with compacted bentonite. The results of the safety analysis attest that the planned disposal system fulfils the safety requirements. Suitable places for the repository can be found at each of the five investigation sites

The Geology of the Kivetty area

International Nuclear Information System (INIS)

Anttila, P.; Paulamaeki, S.; Lindberg, A.; Paananen, M.; Koistinen, T.; Front, K.; Pitkaenen, P.

1992-05-01

Teollisuuden Voima Oy (TVO) is preparing for the final disposal of spent nuclear fuel from the Olkiluoto nuclear power plant (TVO-I and TVO-II) deep in the Finnish bedrock. Kivetty in Konginkangas was one of the five areas selected in 1987 for preliminary site investigations for this purpose. The Kivetty area in Central Finland is located in a Svecokarelian granitoid environment consisting of a complex of synorogenic granitoids 1900 - 1860 million years in age. The bedrock consists almost entirely of plutonic rocks, i.e. gabbro, porphyritic granodiorite and granite, eguigranular granodiorite and granite, listed in order of age. The majority of the rock types are porphyritic in character, and supracrustal rocks such as quartz-feldspar schist and gneiss are found occasionally in small xenoliths

The international INTRAVAL project. Summary and conclusions by the TVO/VTT Team

International Nuclear Information System (INIS)

Hautojaervi, A.

1994-12-01

Teollisuuden Voima Oy (TVO) participated the international cooperation project INTRAVAL and VTT Energy acted as a project team. The Finnish participation focused on flow and transport in crystalline fractured rock and six test cases out of thirteen were tackled. The experimental results were evaluated mainly by means of analytical transport models. The report presents a short review of the experience obtained in the course of the project. It concentrates on the issues revealed in the discussions and analyses of the six test cases in which the TVO/VTT team actively participated but some of the conclusions are even more general in nature. Some suggestions are made for future experimental and theoretical work in the field of geosphere. (15 refs., 2 tabs.)

Design principle of TVO's final repository and preliminary adaptation to site specific conditions

International Nuclear Information System (INIS)

Salo, J-P.; Reikkola, R.

1995-01-01

Teollisuuden Voima Oy (TVO) is responsible for the management of spent fuel produced by the Olkiluoto power plant. TVO's current programme of spent fuel management is based on the guidelines and time schedule set by the Finnish Government. TVO has studied a final disposal concept in which the spent fuel bundles are encapsulated in copper canisters and emplaced in Finnish bedrock. According to the plan the final repository for spent fuel will be in operation by 2020. TVO's updated technical plans for the disposal of spent fuel together with a performance analysis (TVO-92) were submitted to the authorities in 1992. The paper describes the design principle of TVO's final repository and preliminary adaptation of the repository to site specific conditions. (author). 10 refs., 5 figs

Finnish participation in the European utility requirements work

International Nuclear Information System (INIS)

Patrakka, E.

2000-01-01

The Finnish participation in the EUR process started already in April 1994 when IVO (Imatran Voima Oy presently Fortum Oyj) and TVO (Teollisuuden Voima Oy) were asked to comment EUR Volume 1 and 2 Revision A in April 1994. A formal application for the Finnish membership in the EUR organisation was sent on 20 November 1995, and Finland was accepted as an associated member on the next day. The Finnish representatives in the various EUR bodies were appointed in March 1996, at which time the formal participation in these bodies commenced. On 7 November 1996, EUR Steering Committee approved a full membership of IVO and TVO that are joint EUR members representing Finland together. A major Finnish contribution was made in 1997 when IVO and TVO performed a comparison between the EUR document and YVL guides. The period of the Finnish membership has been characterised by the compilation of EUR Volume 3 subsets, in which process IVO/Fortum and TVO have been actively participating. From the Finnish point of view, the EUR work can also be seen as a part of getting prepared to proceed with a possible new NPP project. The EUR document is a substantial aid when preparing the technical specifications for a NPP bid inquiry. The information received in connection with the detailed assessment work for Volume 3 subsets is very valuable when considering the feasibility of NPP concepts. In addition. the experiences gained in the Volume 3 activities enable to develop even better requirements that are manifested by Revision C of Volumes 1 and 2. (author)

Bedrock model of the Kivetty area

International Nuclear Information System (INIS)

Saksa, P.; Paulamaeki, S.; Paananen, M.; Anttila, P.; Front, K.; Pitkaenen, P.; Korkealaakso, J.; Okko, O.

1993-07-01

Preliminary site investigations were carried out at Kivetty (in Finland), in 1987-1992 in accordance with the investigation programme drawn up by Teollisuuden Voima Oy (TVO). The site was modelled in terms of rock type, fracturing, fracture structures and geohydrological conditions, with the main emphasis being placed on fracturing and associated hydraulic conductivity. The various properties of the bedrock structures were classified in relation to a three-dimensional model. The descriptions of the models were stored in a computer system for the purpose of illustration. The principal rock types encountered at the Kivetty site are porphyritic granodiorite and porphyritic granite, in addition to which even-grained granite and granodiorite, gabbro, and small felsic and mafic veins occur. The rocks have undergone two distinct phases of deformation. (41 refs., 50 figs.)

Geophysical borehole logging. Final disposal of spent fuel

International Nuclear Information System (INIS)

Rouhiainen, P.

1984-01-01

Teollisuuden Voima Oy (Industrial Power Company Ltd.) will take precautions for final disposal of spent fuel in the Finnish bedrock. The first stage of the site selection studies includes drilling of a deep borehole down to approximately 1000 meters in the year 1984. The report deals with geophysical borehole logging methods, which could be used for the studies. The aim of geophysical borehole logging methods is to descripe specially hydrogeological and structural features. Only the most essential methods are dealt with in this report. Attention is paid to the information produced with the methods, derscription of the methods, interpretation and limitations. The feasibility and possibilities for the aims are evaluated. The evaluations are based mainly on the results from Sweden, England, Canada and USA as well as experiencies gained in Finland

Diffusion of water, cesium and neptunium in pores of rocks

International Nuclear Information System (INIS)

Puukko, E.; Heikkinen, T.; Hakanen, M.

1993-10-01

Teollisuuden Voima Oy (TVO) is investigating the feasibility to dispose of spent nuclear fuel within Finland. The present plan calls for the repository to be located in crystalline rock at a depth of several hundred meters. The safety assessment of the repository includes calculations of migration of waste nuclides. The flow of waste elements in groundwater will be retarded through sorption interaction with minerals and through diffusion into rock. Diffusion is the only mechanism retarding the migration of non-sorbing species and, it is expected to be the dominating retardation mechanism of many of the sorbing elements. In the investigation the simultaneous diffusion of tritiated water (HTO), cesium and neptunium in rocks of TVO investigation sites at Kivetty, Olkiluoto and Romuvaara were studied. (11 refs., 33 figs., 9 tabs.)

Experimental testing of an ABB Master application

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.; Korhonen, J.; Tuulari, E.

1995-10-01

A prototype dynamic testing harness for programmable automation systems has been specified and implemented at the Technical Research Centre of Finland (VTT). In order to get experience on the methodology and equipment for the testing of systems important to the safety of nuclear power plants, where the safety and reliability requirements often are very high, two different pilot systems have been tested. One system was an ABB Master application, which was loaned for testing from ABB Atom by Teollisuuden Voima Oy (TVO). Another system, loaned from Siemens AG (SAG) by IVO International Oy (IVO), was an application realized with SAG's digital SILT technology. The report describes the experiences gained in testing an APRM pilot system realized with ABB Master technology. The testing of the pilot application took place in the VTT Automation laboratory in Otaniemi in September-October 1994. The purpose of the testing was not to assess the quality of the pilot system, but to get experience in the testing methodology and find out the further development needs and potentials of the test methodology and equipment. (7 refs., 14 figs., 9 tabs.)

An approach to quality classification of deep groundwaters in Sweden and Finland

International Nuclear Information System (INIS)

Laaksoharju, M.; Smellie, J.; Ruotsalainen, P.; Snellman, M.

1993-11-01

In Sweden and Finland high quality groundwater samples are required in the site characterization programmes relating to safe disposal of spent nuclear fuel. SKB (Swedish Nuclear Fuel and Waste Management Co.) and TVO (Teollisuuden Voima Oy, Finland) initiated a cooperative task to critically evaluate the quality of the earlier sampling programmes and to further develop the understanding of quality or representativeness of the groundwater samples. The major aim in this report has been, therefore, to make an attempt to classify groundwaters from site investigations in Sweden and Finland based on quality. Different classification systems have been tested and developed. These can be divided in two main groups; manual methods and computer-based mathematical methods. Manual, statistical, mixing ratio and scoring systems have all been used to illustrate the difficulty in judging groundwater quality. (28 refs., 19 figs., 11 tabs.)

The geology of the Romuvaara area

International Nuclear Information System (INIS)

Anttila, P.; Paulamaeki, S.; Lindberg, A.; Paananen, M.; Pitkaenen, P.; Front, K.

1990-12-01

Teollisuuden Voima Oy (TVO) is preparing for the final disposal of spent uranium fuel from the Olkiluoto nuclear power plant deep in the Finnish bedrock. The report presents a summary of the geological conditions at Romuvaara in Kuhmo, which was one of the five areas selected in 1987 for the preliminary site investigations. The Romuvaara site and its surroundings belong to the Archaean basement complex, the age of the oldest parts of which is over 2800 Ma. The bedrock consists mainly of migmatic banded gneisses (tonalite, leucotonalite and mica gneiss). These rock types are intersected by granodiorite and metadiabase dykes. Proterozoic metadiabases represent the youngest rock unit in the area. Except for the metadiabase, the rocks have undergone a multiphase Archaean deformation. The bedrock structures are interpreted as representing six deformation phases, after which sharp faults developed during at least four further movement phases

3D-mainosvideo teollisuusyritykselle : Case: Leppäkosken Lämpö

OpenAIRE

Utriainen, Sari

2015-01-01

Toimeksiantajana opinnäytetyölle toimi biolämmitysjärjestelmiä valmistava ja markkinoiva Ariterm Oy. Tavoitteena oli tuottaa messu- ja markkinointikäyttöön 3D-mainosvideo Ariterm Oy:n toimittamasta, elokuussa 2014 käyttöönotetusta Leppäkosken Lämpö Oy:n pellettilämpölaitoksesta. Opinnäytetyössä käsiteltiin 3D-mallien hyödyntämistä eri teollisuuden aloilla sekä tutustuttiin 3D-mainosvideoprojektissa käytettyihin ohjelmistoihin ja teollisuuden 3D-suunnitteluohjelmien eri tiedostomuotoihin se...

Research into basic rocks types

International Nuclear Information System (INIS)

1993-06-01

Teollisuuden Voima Oy (TVO) has carried out research into basic rock types in Finland. The research programme has been implemented in parallel with the preliminary site investigations for radioactive waste disposal in 1991-1993. The program contained two main objectives: firstly, to study the properties of the basic rock types and compare those with the other rock types under the investigation; secondly, to carry out an inventory of rock formations consisting of basic rock types and suitable in question for final disposal. A study of environmental factors important to know regarding the final disposal was made of formations identified. In total 159 formations exceeding the size of 4 km 2 were identified in the inventory. Of these formations 97 were intrusive igneous rock types and 62 originally extrusive volcanic rock types. Deposits consisting of ore minerals, industrial minerals or building stones related to these formations were studied. Environmental factors like natural resources, protected areas or potential for restrictions in land use were also studied

Summary report of the experiences from TVO's site investigations

International Nuclear Information System (INIS)

Oehberg, A.; Saksa, P.; Ahokas, H.; Ruotsalainen, P.; Snellman, M.

1994-09-01

In 1992 Teollisuuden Voima Oy (TVO) completed preliminary site investigations for radioactive waste disposal at five sites in Finland. The aim of this report was the compilation of the experiences from TVO's site investigations. The main interest was focused on investigation strategies and the most important investigation methods for the conceptual modelling. The objective of the preliminary site investigations was to obtain data on the bedrock properties in order to evaluate the areas. The programme was divided into four stages, each stage having its own subobjective. The site-specific investigation programme for each site included a large common part and a small site-specific part. The strategies (objectives) and experiences from different disciplines, geology, hydrogeochemistry, geophysics and geohydrology, are presented in the report. The conceptual modelling work procedure including both bedrock and groundwater modelling is described briefly using the Olkiluoto site as an example. Each of the other areas has undergone similar phases of work. (52 refs., 45 figs., 5 tabs.)

Simulation of the groundwater flow of the Kivetty area

International Nuclear Information System (INIS)

Taivassalo, V.; Meszaros, F.

1994-02-01

Teollisuuden Voima Oy (TVO) is preparing for the final disposal of spent nuclear fuel into crystalline bedrock in Finland. Groundwater flow modelling is a part of the preliminary site investigation work. The aim is to simulate groundwater flow as realistically as possible in view of the experimental data available. Three dimensional groundwater flow modelling is based on a conceptual bedrock model. The modelling results will be used in the site evaluation process. Observations from flow simulations will also be used to identify and study uncertainties included in the site characterization. First a conceptual flow model for the Kivetty site in Konginkangas was developed. As a second stage the flow model was calibrated. The goal was to increase the reality of the model. To evaluate the reality of the flow model, the values of the input and output parameters were compared with the field data. Finally groundwater flow simulation results were computed and groundwater flow at the Kivetty area was analysed. (50 refs., 78 figs., 7 tabs.)

Colloids or artefacts? A TVO/SKB cooperation project in Olkiluoto, Finland

International Nuclear Information System (INIS)

Laaksoharju, M.; Vuorinen, U.; Snellman, M.; Helenius, J.; Allard, B.; Pettersson, C.; Hinkkanen, H.

1993-12-01

TVO (Teollisuuden Voima Oy, Finland) initiated a co-operative task with SKB (Swedish Nuclear Fuel and Waste Management Co.) to critically evaluate colloid sampling methods at the test site in Olkiluoto, SW Finland. Three different colloid sampling methods were compared when sampling borehole OL-KR1 at 613-618 m depth. One possible way to make a conservative in-situ colloid estimation is to omit the contribution from calcite precipitation which is considered to be the main artefact. When this is made the inorganic colloid content (size 1-1000 nm) in Olkiluoto is 184 ±177 ppb consisting of clay minerals, silica, pyrite, goethite and magnesium oxide; the concentration of organic substances are around 100 ppb. The in-situ colloid concentration seems to be low which is in good agreement with experiences from years of sampling in similar environment and depths. The exercise shows the many difficulties encountered when sampling colloids. Small error in the planning, pump rate selection, a lack of precautionary measures, artefact sensitivity of the method etc have a tendency to affect significantly the results on the measured ppb colliod level

Bedrock Model of the Syyry area

International Nuclear Information System (INIS)

Saksa, P.; Kuivamaeki, A.; Kurimo, M.; Paananen, M.; Anttila, P.; Front, K.; Pitkaenen, P.; Hassinen, P.; Ylinen, A.

1993-09-01

Preliminary site investigations implemented in accordance with the research programme drawn up by Teollisuuden Voima Oy (TVO) were carried out at Syyry (in Finland) in 1987-1992. Models of the site were compiled and used for describing the rock types, fracturing, fracture structures and geohydrological conditions, the main emphasis being on the examination of the bedrock fracturing and related hydraulic conductivity. Three-dimensional models were used for the classification of the various properties of the bedrock structures. The descriptive models were gathered into a computer system to facilitate illustration and storage. The main rock type at Syyry is tonalite. A mica gneiss formation SE of the investigation site dips towards the NW and delimits the tonalite as far as the central part of the investigation site. The miga gneiss has a heterogeneous composition and includes intermediate layers consisting of quartz feldspar schist and amphibolite. There are mafic formations in the vicinity of the investigation site. The intrusive rocks have been deformed during three plastic and three mainly brittle deformation stages. (47 refs., 61 figs.)

Local negotiation on compensation siting of the spent nuclear fuel repository in Finland

International Nuclear Information System (INIS)

Kojo, Matti

2007-01-01

The aim of the paper is to analyse the local negotiation process between the Municipality of Eurajoki and the nuclear power company Teollisuuden Voima (TVO) and the nuclear waste management company Posiva Oy. The aim of the negotiations was to find an acceptable form of compensation for siting a spent nuclear fuel repository in Olkiluoto, Finland. The paper includes background information on the siting process in Finland, the local political setting in the Municipality of Eurajoki and a description of the negotiation process. The analysis of the negotiations on compensation is important for better understanding the progress of the Finnish siting process. The paper describes the picture of the contest to host the spent nuclear fuel repository. It also provides more information on the relationship between the Municipality of Eurajoki and the power company TVO. The negotiations on compensation and the roles of various players in the negotiations have not been studied in detail because the minutes of the Vuojoki liaison group were not available before the decision of the Supreme Administrative Court in May 2006. (author)

Compiling Utility Requirements For New Nuclear Power Plant Project

International Nuclear Information System (INIS)

Patrakka, Eero

2002-01-01

Teollisuuden Voima Oy (TVO) submitted in November 2000 to the Finnish Government an application for a Decision-in-Principle concerning the construction of a new nuclear power plant in Finland. The actual investment decision can be made first after a positive decision has been made by the Government and the Parliament. Parallel to the licensing process, technical preparedness has been upheld so that the procurement process can be commenced without delay, when needed. This includes the definition of requirements for the plant and preliminary preparation of bid inquiry specifications. The core of the technical requirements corresponds to the specifications presented in the European Utility Requirement (EUR) document, compiled by major European electricity producers. Quite naturally, an amount of modifications to the EUR document are needed that take into account the country- and site-specific conditions as well as the experiences gained in the operation of the existing NPP units. Along with the EUR-related requirements concerning the nuclear island and power generation plant, requirements are specified for scope of supply as well as for a variety of issues related to project implementation. (author)

Geophysical investigations in the Veitsivaara area, Finland summary report

International Nuclear Information System (INIS)

Heikkinen, E.; Saksa, P.; Hinkkanen, H.

1991-10-01

Teollisuuden Voima Oy (TVO carries out site investigations in Finland for final disposal of nuclear high level waste during 1987-2000. Investigations by geological, geophysical, geohydrological and geochemical methods were carried out in the Veitsivaara area in 1987-90 to determine the suitability of the bedrock for the final disposal of spent nuclear fuel. Airborne, ground and borehole geophysical methods were used to study the rock type distribution, fracturing and hydraulic conductivity. Airborne surveys were performed by magnetic, radiometric and two electromagnetic methods and ground investigations by VLF magnetic and resistivity, magnetic and impulse radar methods. Electromagnetic and seismic refraction surveys were used to locate crushed and fracture zones. The properties of weak electrical conductors, e.g. their depth dimensions, were studied by direct current resistivity measurements. The rock type distribution was studied by single-hole logging of susceptibility, natural γ-radiation and radiometric γ γ-density. Electrical and acoustic logging allowed water bearing fractures to be mapped and the results of water injection tests to be interpreted. Flow conditions in the boreholes were studied by both fluid logging and tube wave sounding

Final disposal of spent fuel in the Finnish bedrock

International Nuclear Information System (INIS)

1992-12-01

Teollisuuden Voima Oy (TVO) is preparing for the final disposal of spent nuclear fuel from the Olkiluoto nuclear power plant (TVO-I and TVO-II reactors). According to present estimates, a total of 1840 tU of spent fuel will be accumulated during the 40-year lifetime of the power plant. An interim storage facility for spent fuel (TVO-KPA Store) has operated at Olkiluoto since 1987. The spent fuel will be held in storage for several decades before it is shipped to the repository site. Both train and road transportation are possible. The spent fuel will be encapsulated in composite copper and steel canisters (ACP Canister) in a facility that will be build above the ground on the site where the repository is located. The repository will be constructed at the depth of several hundreds of meters in the bedrock. In 1987 five areas were selected for preliminary site investigations. The safety analysis (TVO-92) that was carried out shows that the proposed safety criteria would be met at each of the candidate sites. In future expected conditions there would never be significant releases of radioactive substances to the biosphere. The site investigations will be continued in the period 1993 to 2000. In parallel, a R and D programme will be devoted to the safety and technology of final disposal. The site for final disposal will be selected in the year 2000 with the aim of having the capability to start the disposal operations in 2020

Operation of Finnish nuclear power plants. Quarterly report 4th quarter, 1994 and annual summary

Energy Technology Data Exchange (ETDEWEB)

Tossavainen, K [ed.

1995-05-01

The Loviisa NPP units were in power operation the whole last quarter, with the exception of a reactor scram at Loviisa 1. The load factor average of all Finnish plant units was 100.2 %. The annual average was 90.0 %. All events in the fourth annual quarter were assigned level 0 (no safety significance) on the international INES scale. Four events in 1994 were classified level 1 (an anomaly). The Finnish Centre for Radiation and Nuclear Safety in December approved Imatran Voima Oy`s application to extend the operation of the reactor pressure vessel of Loviisa 2 until the annual maintenance outage of 2010. During this quarter, a batch of spent fuel from Loviisa power plant was transported to Russia. Occupational doses and radioactive releases off-site were below authorised limits. Only such quantities of plant-based radioactive materials were measurable in samples collected around the plants as have no bearing on the radiation exposure of the population. The report includes a summary of all the items described in the Quarterly Reports of 1994. (8 figs., 4 tabs.).

Finnish research programmes on nuclear power plant safety

International Nuclear Information System (INIS)

Puska, E. K.

2010-01-01

The current Finnish national research programme on nuclear power plant safety SAFIR2010 for the years 2007-2010 as well as the coming SAFIR2014 programme for the years 2011-2014 are based on the chapter 7a, 'Ensuring expertise', of the Finnish Nuclear Energy Act. The objective of this chapter is realised in the research work and education of experts in the projects of these research programmes. SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). All the research areas include both projects in their own area and interdisciplinary co-operational projects. Research projects of the programme are chosen on the basis of annual call for proposals. In 2010 research is carried out in 33 projects in SAFIR2010. VTT is the responsible research organisation in 26 of these projects and VTT is also the coordination unit of SAFIR2010 and SAFIR2014. In 2007-2009 SAFIR2010 produced 497 Specified research results (Deliverables), 618 Publications, and 33 Academic degrees. SAFIR2010 programme covers approximately half of the reactor safety research volume in Finland currently. In 2010 the programme volume is EUR 7.1 million and 47 person years. The major funding partners are VYR with EUR 2.96 million, VTT with EUR 2.66 million, Fortum with EUR 0.28 million, TVO with EUR 0.19 million, NKS with EUR 0.15 million, EU with only EUR 0.03 million and other partners with EUR 0.85 million. The new decisions-in-principle on Olkiluoto unit 4 for Teollisuuden Voima and new nuclear power plant for Fennovoima ratified by the Finnish Parliament on 1 July 2010 increase the annual funding collected according to the Finnish Nuclear Energy Act from Fennovoima, Fortum and Teollisuuden Voima for the SAFIR2014 programme to EUR 5.2 million from the current level of EUR 3

Operation set for 2018 as regulator considers olkiluoto-3 licence application

Energy Technology Data Exchange (ETDEWEB)

Kraev, Kamen [NucNet, Brussels (Belgium)

2017-02-15

Finland has announced progress with its delayed nuclear project and has confirmed it will not be affected by anomalies discovered in some components manufactured for EPRs in France. The Olkiluoto-3 European Pressurised Reactor (EPR) nuclear plant under construction in Finland is on schedule to begin commercial operation in 2018 with the country's regulator preparing a safety assessment that will pave the way for fuel loading. Jouni Silvennoinen, senior vice-president for Olkiluoto-3 at Teollisuuden Voima Oyj (TVO), told NucNet that fuel loading at the EPR plant, which is nine years behind schedule, is expected in the spring of 2018. He said construction and licensing of the plant are progressing.

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

International Nuclear Information System (INIS)

Sillanpaeae, T.

1997-02-01

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

Finnish experiences on licensing and using of programmable digital systems in nuclear power plants

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.; Heimburger, H.; Hall, L.E.; Manninen, T.

1993-01-01

Finnish utility companies, Imatran Voima Oy (IVO) and Teollisuuden Voima (TVO), and the licensing authority, the Finnish Centre for Radiation and Nuclear Safety (STUK), are preparing for a new nuclear power plant in Finland. Plant vendors are proposing programmable digital automation systems for both the safety-related and the operational I and C (instrumentation and control) systems in this new unit. Also in existing plant units the replacement of certain old analog systems with state-of-the-art digital ones will become necessary in the years to come. Licensing of programmable systems for safety critical applications requires a new approach due to the special properties and failure modes of these systems. The major difficulties seem to be in the assessment and quantification of software reliability. The Technical Research Centre of Finland has in co-operation with the authority and the utilities conducted a project (AJA) to develop domestically applicable licensing requirements, guidelines and practices. International standards, guidelines and licensing practices have been analyzed in order to specify national licensing requirements. The paper describes and discusses the findings and experiences of the AJA project so far. The experience in introducing advanced programmable digital control and computer systems in the operating nuclear power plants will be covered briefly. Although these systems are not safety-related but systems of more general interest regarding nuclear safety, some routines regarding the licensing of safety- related systems have been followed. In these backfitting and replacement projects some experience have been gained in how to license safety-related programmable systems. (Author) 31 refs., 2 figs

Final disposal of spent nuclear fuel in the Finnish bedrock

International Nuclear Information System (INIS)

1992-12-01

Teollisuuden Voima Oy (TVO) studies Finnish bedrock for the final disposal of the spent nuclear fuel from the Olkiluoto nuclear power plant. The study is in accordance with the decision in principle by Finnish government in 1983. The report is the summary of the preliminary site investigations carried out during the years 1987-1992. On the basis of these investigations a few areas will be selected for detailed site investigation. The characterization comprises five areas selected from the shortlist of potential candidate areas resulted in the earlier study during 1983-1985. Areas are located in different parts of Finland and they represent the main formations of the Finnish bedrock. Romuvaara area in Kuhmo and Veitsivaara area in Hyrynsalmi represent the Archean basement. Kivetty area in Konginkangas consists of mainly younger granitic rocks. Syyry in Sievi is located in transition area of Svecofennidic rocks and granitic rocks. Olkiluoto in Eurajoki represents migmatites in southern Finland. For the field investigations area-specific programs were planned and executed. The field investigations have comprised airborne survey by helicopter, geophysical surveys, geological mappings and samplings, deep and shallow core drillings, geophysical and hydrological borehole measurements and groundwater samplings

Ore potential of basic rocks in Finland

International Nuclear Information System (INIS)

Reino, J.; Ekberg, M.; Heinonen, P.; Karppanen, T.; Hakapaeae, A.; Sandberg, E.

1993-02-01

The report is associated with a study programme on basic rocks, which has the aim to complement the preliminary site investigations on repository for TVO's (Teollisuuden Voima Oy) spent nuclear fuel. The report comprises a mining enterprise's view of the ore potential of basic plutonic rocks in Finland. The ores associated with basic plutonic rocks are globally known and constitute a significant share of the global mining industry. The ores comprise chromium, vanadium-titanium-iron, nickel-copper and platinum group element ores. The resources of the metals in question and their mining industry are examined globally. A review of the use of these metals in the industry is presented as well. General factors affecting the mining industry, such as metal prices, political conjunctures, transport facilities, environmental requirements and raw material sources for the Finnish smelters have been observed from the point of view of their future effect on exploration activity and industrial development in Finland. Information on ores and mineralizations associated with Finnish basic rocks have been compiled in the report. The file comprises 4 chromium occurrences, 8 vanadium-titanium-iron occurrences, 13 PGE occurrences and 38 nickel-copper occurrences

Review of the sorption of radionuclides on the bedrock of Haestholmen and on construction and backfill materials of a final repository for reactor wastes

International Nuclear Information System (INIS)

Kulmala, S.; Hakanen, M.

1992-10-01

Imatran Voima Oy (IVO) has plans to build a final repository for reactor wastes in the bedrock of the nuclear power plant site at Haestholmen, Loviisa. This report summarizes the sorption studies of radionuclides in Finnish bedrock performed at the Department of Radiochemistry, University of Helsinki. The values of mass distribution ratios, K d , and surface distribution ratios, K a ; of carbon, calsium, Zirconium, niobium, cobalt, nickel, strontium, cesium, uranium, plutonium, americium, thorium, chlorine, iodine and technetium are surveyed. Special attention is paid to the sorption data for construction and backfill materials of rector waste repository and the bedrock of Haestholmen. Safety assessment of a repository includes calculations of migration of the waste element in construction materials and backfill in the nearfield and in bedrock. Retardation by sorption of waste nuclides compared to groundwater flow is described by using distribution ratios between solid materials and water. (orig.)

Yritysmarkkinointisuunnitelma : -Case Kakadu Oy

OpenAIRE

Lamberg, Leena

2009-01-01

Opinnäytetyön aihe on yritysmarkkinointisuunnitelman kehittäminen tilasuunnitteluyritys Kakadu Oy:lle. Työn tavoitteena on segmentoida Kakadu Oy:n asiakaskunta ja määrittää tärkein asiakassegmentti sekä tehdä valitulle, potentiaalisimmalle asiakassegmentille kohdistettu markkinointisuunnitelma. Markkinointisuunnitelman tarkoitus on auttaa Kakadu Oy:tä suuntaamaan erittäin rajalliset resurssit mahdollisimman perustellusti ja tuottavasti. Yrityksessä ei ole aikaisemmin toteutettu markkinoin...

Nuclear power and Imatran Voima in the future

International Nuclear Information System (INIS)

Numminen, K.

1995-01-01

As the owner of the Loviisa NPS with two VVER-440 units, Imatran Voima (IVO) has worked with nuclear power for more than twenty years. After the negative decision of the Finnish Parliament in 1993 there are no possibilities to build nuclear power in Finland in the near future. However, the preparation work for increasing the produced power of all four operating NPP's of Finland is going on. The emphasis in the work with new nuclear energy is on the supporting programs in Eastern Europe and the preparation of a building contract of a new NPS to China together with the Russians. With a new decision of the Finnish Parliament, the nuclear option could still be an important part of the future energy strategy of Finland. (orig.)

OL1/OL2 License renewal for extended life-time: Class 1 piping load and strength analyses

International Nuclear Information System (INIS)

Lemettinen, P.

2015-01-01

Teollisuuden Voima Oyj (TVO) operates two NPP units Olkiluoto 1 (OL1) and Olkiluoto 2 (OL2), that are identical 880 MWe BWRs. The units were originally designed for 40 years life-time. TVO is applying license renewal for extended life-time for 60 years plant life. Part of the license renewal project is to evaluate and update all Class 1 piping load and strength analyses. These analyses are done with the help of TVO's in-house Piping and Component Analysis and Monitoring System (PAMS). PAMS is basically a database system, consisting of separate geometry, material, loading, result and document databases. The thermo hydraulic analysis program RELAP5 is used to obtain temperature, pressure and mass flow for the piping loading areas. The piping strength analysis are carried out mainly with the Finnish FPIPE FEA program for all related thermal transient and dynamic load cases. The slides of the presentation have been added to the paper

AquaBuOY

DEFF Research Database (Denmark)

Weinstein, Alla; Fredrikson, Göran; Claeson, Lennart

2003-01-01

BuOY in five representative generic sea states. Ocean energy and offshore wave energy conversion in the United States is at a significant milestone. During the next year, ocean energy technology developers and energy officials have the potential to deploy pilot scale ocean power plants and transition......This paper describes development of the mathematical model simulating ocean performance of an offshore wave energy point absorber device-AquaBuOY. The AquaBuOY is the next generation of the technology, based on the IPS point absorber system and the hose pump, both of Sweden. AquaEnergy Group Ltd......, engineers, and developers can continue to lay the groundwork for government spending and interest in ocean energies....

Experimental testing of a SAG digital SILT application

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.; Heikkinen, J.; Korhonen, J.

1995-10-01

A prototype dynamic testing harness for programmable automation systems has been specified and implemented at the Technical Research Centre of Finland (VTT). In order to get experience on the methodology and equipment for the testing of systems important to the safety of nuclear power plants, where the safety and reliability requirements often are very high, two different pilot systems have been tested. One system was an ABB Master application, which was loaned for testing from ABB Atom by Teollisuuden Voima Oy (TVO). Another system, loaned from Siemens AG(SAG) by IVO International Oy (IVO), was an application realized with SAG's digital SILT technology. The report describes the testing of the SAG application. The purpose of the testing was not to assess the pilot system, but to get experience in the testing methodology and find out the further development needs and potentials of the test methodology and equipment. The experience show that dynamic testing is one feasible way to get more confidence about the safety and reliability of a programmable system that would be hard to achieve by other means. It also shows that more development of the test harness is still needed, especially concerning the comparison of the obtained test response to the expected response provided by the logical model of the system. Also the user interface of the on-line part of the test harness needs development. Methods for generation of the test cases also need further development eg. for achieving statistical significance for the reliability estimates. (10 refs., 90 figs., 9 tabs.)

SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

Energy Technology Data Exchange (ETDEWEB)

Simola, K. [ed.

2013-02-15

The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

International Nuclear Information System (INIS)

Simola, K.

2013-02-01

The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

Customer database for Watrec Oy

OpenAIRE

Melnichikhina, Ekaterina

2016-01-01

This thesis is a development project for Watrec Oy. Watrec Oy is a Finnish company specializes in “waste-to-energy” issues. Customer Relation Management (CRM) strategies are now being applied within the company. The customer database is the first and trial step towards CRM strategy in Watrec Oy. The reasons for database project lie in lacking of clear customers’ data. The main objectives are: - To integrate the customers’ and project data; - To improve the level of sales and mar...

Workshop on iodine aspects of severe accident management. Summary and conclusions

International Nuclear Information System (INIS)

2000-03-01

Following a recommendation of the OECD Workshop on the Chemistry of Iodine in Reactor Safety held in Wuerenlingen (Switzerland) in June 1996 [Summary and Conclusions of the Workshop, Report NEA/CSNI/R(96)7], the CSNI decided to sponsor a Workshop on Iodine Aspects of Severe Accident Management, and their planned or effective implementation. The starting point for this conclusion was the realization that the consolidation of the accumulated iodine chemistry knowledge into accident management guidelines and procedures remained, to a large extent, to be done. The purpose of the meeting was therefore to help build a bridge between iodine research and the application of its results in nuclear power plants, with particular emphasis on severe accident management. Specifically, the Workshop was expected to answer the following questions: - what is the role of iodine in severe accident management? - what are the needs of the utilities? - how can research fulfill these needs? The Workshop was organized in Vantaa (Helsinki), Finland, from 18 to 20 May 1999, in collaboration with Fortum Engineering Ltd. It was attended by forty-six specialists representing fifteen Member countries and the European Commission. Twenty-eight papers were presented. These included four utility papers, representing the views of Electricite de France (EDF), Teollisuuden Voima Oy and Fortum Engineering Ltd (Finland), the Nuclear Energy Institute (USA), and Japanese utilities. The papers were presented in five sessions: - iodine speciation; - organic compound control; - iodine control; - modeling; - iodine management; A sixth session was devoted to a general discussion on iodine management under severe accident conditions. This report summarizes the content of the papers and the conclusions of the workshop

Hierarchical α-MnO2 nanowires@Ni1-x Mnx Oy nanoflakes core-shell nanostructures for supercapacitors.

Science.gov (United States)

Wang, Hsin-Yi; Xiao, Fang-Xing; Yu, Le; Liu, Bin; Lou, Xiong Wen David

2014-08-13

A facile two-step solution-phase method has been developed for the preparation of hierarchical α-MnO2 nanowires@Ni1-x Mnx Oy nanoflakes core-shell nanostructures. Ultralong α-MnO2 nanowires were synthesized by a hydrothermal method in the first step. Subsequently, Ni1-x Mnx Oy nanoflakes were grown on α-MnO2 nanowires to form core-shell nanostructures using chemical bath deposition followed by thermal annealing. Both solution-phase methods can be easily scaled up for mass production. We have evaluated their application in supercapacitors. The ultralong one-dimensional (1D) α-MnO2 nanowires in hierarchical core-shell nanostructures offer a stable and efficient backbone for charge transport; while the two-dimensional (2D) Ni1-x Mnx Oy nanoflakes on α-MnO2 nanowires provide high accessible surface to ions in the electrolyte. These beneficial features enable the electrode with high capacitance and reliable stability. The capacitance of the core-shell α-MnO2 @Ni1-x Mnx Oy nanostructures (x = 0.75) is as high as 657 F g(-1) at a current density of 250 mA g(-1) , and stable charging-discharging cycling over 1000 times at a current density of 2000 mA g(-1) has been realized. © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Seismic VSP and HSP surveys on preliminary investigation areas in Finland for final disposal of spent nuclear fuel

International Nuclear Information System (INIS)

Keskinen, J.; Cosma, C.; Heikkinen, P.

1992-10-01

Seismic reflection surveys in boreholes were carried out for Teollisuuden Voima Oy at five sites in Finland (Eurajoki Olkiluoto, Hyrynsalmi Veitsivaara, Konginkangas Kivetty, Kuhmo Romuvaara and Sievi Syyry). The vertical Seismic Profiling (VSP) surveys were a part of the investigation programme for the final disposal of spent nuclear fuel. The purpose was to detect fractured zones, lithological contacts and other anomalies in the structure of the rockmass and to determine their position and orientation. Horizontal Seismic Profiling (HSP) was used at the Olkiluoto site, additionally to VSP. The data has been organized in profiles containing seismograms recorded from the same shotpoint (shot gathers). One of the most powerful processing methods used with this project has been the Image Space Filtering, a new technique, which has been developed (in the project) for seismic reflection studies in crystalline rock. The method can be applied with other rock types where steeply inclined or vertical anomalies are of interest. It acts like a multichannel filter, enhancing the reflected events and also as an interpretation tool, to estimate the strength and position of the reflectors. This approach has been of great help in emphasizing the weak reflections from uneven and sometimes vanishing interfaces encountered in crystalline

Sähkösuunnittelu osana suunnitteluprojektia

OpenAIRE

Grönroos, Roope

2016-01-01

Insinöörityö tehtiin Sweco Industry Oy:n automaatio-osastolle. Työssä tutkittiin, kuinka teollisuuden sähkösuunnittelu liittyy suunnitteluprojekteissa muihin suunnittelualoihin isomman suunnittelukonsernin näkökulmasta. Alussa perehdytään muihin suunnittelualoihin ja siihen, kuinka ne ovat sidoksissa teollisuuden sähkösuunnitteluun. Alussa käydään läpi suunnitteluprojektin eri vaiheita ja mitä niihin sisältyy. Työtä varten haastateltiin eri suunnittelualojen kokeneita ammattil...

Characteristics of NixFe1−xOy Electrocatalyst on Hematite as Photoanode for Solar Hydrogen Production

Directory of Open Access Journals (Sweden)

Chih-Ping Yen

2017-11-01

Full Text Available The use of hematite as the photoanode for photoelectrochemical hydrogen production by solar energy has been actively studied due to its abundance, stability, and adequate optical properties. Deposition of an electrocatalyst overlayer on the hematite may increase kinetics and lower the onset potential for water splitting. NixFe1−xOy is one of the most effective electrocatalysts reported for this purpose. However, the condition and results of the previous reports vary significantly, and a comprehensive model for NixFe1−xOy/hematite is lacking. Here, we report a simple and novel chemical bath deposition method for depositing low-onset-potential NixFe1−xOy electrocatalyst on hematite. With a Ni percentage of 80% and an immersion time of 2 min, the as-prepared NixFe1−xOy overlayer raised the photovoltage from 0.2 V to 0.7 V, leading to a cathodic shift of the onset potential by 400 mV, while maintaining the same level of current density. The dependence of the electrochemical and photoelectrochemical characteristics of the photoanode on the condition of the electrocatalyst was studied systematically and explained based on energy level diagrams and kinetics.

--- Oy:n tavoitteellinen markkinointi Facebookissa

OpenAIRE

Järventaus, Aino

2012-01-01

Tämä opinnäytetyö on laadittu toimeksiantona ohjelmatoimisto ---- Oy:lle. Toimeksiantosopimus syntyi opinnäytetyön tekijän ehdotuksesta kehittää --- Oy:n digitaalista markkinointia yrityksen toivomasta näkökulmasta. Työn fokukseksi valittiin Facebook koska sillä on merkittävä osa musiikkiteollisuuden markkinoinnissa. Toimeksiantajan Facebook-markkinoinnin hyödyntäminen ja ylläpito oli jäänyt liian vähälle huomiolle. Näin ollen kehittämiskohteeksi valittiin --- Oy:n Facebook-markkinointi ...

Markkinointiviestintäsuunnitelma : Classic Coffee Oy

OpenAIRE

Eerola, Laura

2015-01-01

Opinnäytetyön aiheena oli laatia markkinointiviestintäsuunnitelma kalenterivuodelle 2016 vuosikellon muodossa, toimintansa jo vakiinnuttaneelle Classic Coffee Oy:lle. Classic Coffee Oy on vuonna 2011 perustettu, Tampereella toimiva kahvila-alan yritys joka tarjoaa lounaskahvilatoiminnan lisäksi laadukkaita konditoria-palveluita, yritys- ja kokoustarjoiluja sekä tilavuokrausta. Classic Coffee Oy:llä on yksi kahvila, Classic Coffee Tampella. Kahvila sijaitsee Tampellassa, Tampereen keskustan vä...

Protecting the endangered lake salmon

International Nuclear Information System (INIS)

Soimakallio, H.; Oesch, P.

1997-01-01

In addition to the Ringed Seal, the labyrinthine Saimaa lake system created after the Ice Age also trapped a species of salmon, whose entire life cycle became adapted to fresh water. In order to improve the living conditions of this lake salmon which - like the ringed seal - is today classified as an endangered species, an intensive research programme has been launched. The partners include the Finnish Game and Fisheries Research Institute, fishing and environmental authorities and - in collaboration with UPM-Kymmene Oy and Kuurnan Voima Oy - the IVO subsidiary Pamilo Oy

Protecting the endangered lake salmon

Energy Technology Data Exchange (ETDEWEB)

Soimakallio, H.; Oesch, P. [ed.

1997-11-01

In addition to the Ringed Seal, the labyrinthine Saimaa lake system created after the Ice Age also trapped a species of salmon, whose entire life cycle became adapted to fresh water. In order to improve the living conditions of this lake salmon which - like the ringed seal - is today classified as an endangered species, an intensive research programme has been launched. The partners include the Finnish Game and Fisheries Research Institute, fishing and environmental authorities and - in collaboration with UPM-Kymmene Oy and Kuurnan Voima Oy - the IVO subsidiary Pamilo Oy

Evaluation of incident analysis practices in the Finnish nuclear power industry

Energy Technology Data Exchange (ETDEWEB)

Kettunen, J.; Laakso, K

1999-12-01

This report provides an analysis and evaluation of incident analysis methods and practices applied by the Finnish regulator Radiation and Nuclear Safety Authority (STUK) and the two Finnish nuclear power plant operators Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy (Fortum). The study was conducted in 1998-99. The research material was based on tape-recorded interviews as well as internal directions and event investigation reports provided by the three participating organisations. A framework for analysis and evaluation was developed as part of the study on the basis of referenced root cause analysis and operating experience review methods, selected (foreign) inspection reports, scientific papers and research literature. Well-known inspection methods and principles, such as ASSET and MTO/HPES, provided important guidance to this work. This study shows that although all the evaluated organisations had rather comprehensive incident analysis arrangements, more focus and priorisation is needed. Deficiencies were identified mostly in the areas of recording, assessment and classification of new events and observations, use of existing operating experience data, utilisation of information technology based tools, and allocation of work and resources. In general the direct causes of identified events can be detected and removed, but more emphasis should be given to the prevention of recurrence. This requires a more efficient feedback loop that can be created and maintained by focusing on the root causes of significant events, tasks and activities in which the originating errors occurred, and weaknesses of defensive barriers, and by implementing periodic operational experience reviews. A strategy document for the operating experience feedback process, and firm procedures for the initial assessment of new events and the carrying out of data analyses would help. (orig.)

Regression methodology in groundwater composition estimation with composition predictions for Romuvaara borehole KR10

Energy Technology Data Exchange (ETDEWEB)

Luukkonen, A.; Korkealaakso, J.; Pitkaenen, P. [VTT Communities and Infrastructure, Espoo (Finland)

1997-11-01

Teollisuuden Voima Oy selected five investigation areas for preliminary site studies (1987Ae1992). The more detailed site investigation project, launched at the beginning of 1993 and presently supervised by Posiva Oy, is concentrated to three investigation areas. Romuvaara at Kuhmo is one of the present target areas, and the geochemical, structural and hydrological data used in this study are extracted from there. The aim of the study is to develop suitable methods for groundwater composition estimation based on a group of known hydrogeological variables. The input variables used are related to the host type of groundwater, hydrological conditions around the host location, mixing potentials between different types of groundwater, and minerals equilibrated with the groundwater. The output variables are electrical conductivity, Ca, Mg, Mn, Na, K, Fe, Cl, S, HS, SO{sub 4}, alkalinity, {sup 3}H, {sup 14}C, {sup 13}C, Al, Sr, F, Br and I concentrations, and pH of the groundwater. The methodology is to associate the known hydrogeological conditions (i.e. input variables), with the known water compositions (output variables), and to evaluate mathematical relations between these groups. Output estimations are done with two separate procedures: partial least squares regressions on the principal components of input variables, and by training neural networks with input-output pairs. Coefficients of linear equations and trained networks are optional methods for actual predictions. The quality of output predictions are monitored with confidence limit estimations, evaluated from input variable covariances and output variances, and with charge balance calculations. Groundwater compositions in Romuvaara borehole KR10 are predicted at 10 metre intervals with both prediction methods. 46 refs.

Influence of calcium on transport properties, band spectrum and superconductivity of YBa2Cu3O(y) and YBa(1.5)La(0.5)Cu3O(y)

Science.gov (United States)

Gasumyants, V. E.; Vladimirskaya, E. V.; Patrina, I. B.

1995-01-01

The comparative investigation of transport phenomena in Y(1-x)Ca(x)Ba2Cu3O(y) (0 is less than x is less than 0.25; 6.96 is greater than y is greater than 6.87 and 6.73 is less than x is less than 6.53); Y(1-x)Ca(x)Ba(1.5)La(0.5)Cu3O(y) (0 is less than x is less than 0.5; 7.12 is greater than y is greater than 6.96) and YBa(2-x)La(x)Cu3O(y) (0 is less than x is less than 0.5; 6.95 is less than y is less than 7.21) systems have been carried out. The temperature dependencies of resistivity and thermopower have been measured. It was found that the S(T) dependencies take some additional features with Ca content increase. The results obtained have been analyzed on the basis of the phenomenological theory of electron transport in the case of the narrow conductive band. The main parameters of the band spectrum (the band filling with electrons degree and the total effective band width) have been determined. The dependencies of these from contents of substituting elements are discussed. Analyzing the results obtained simultaneously with the tendencies in oxygen content and critical temperature change we have confirmed the conclusion that the oxygen sublattice disordering has a determinant effect on band structure parameters and superconductive properties of YBa2Cu3O(y). The results obtained suggest that Ca gives rise to some peculiarities in band spectrum of this compound.

Isothermal Kinetics of Diesel Soot Oxidation over La0.7K0.3ZnOy Catalysts

Directory of Open Access Journals (Sweden)

Ram Prasad

2014-10-01

Full Text Available This paper describes the kinetics of catalytic oxidation of diesel soot with air under isothermal conditions (320-350 oC. Isothermal kinetics data were collected in a mini-semi-batch reactor. Experiments were performed over the best selected catalyst composition La0.7K0.3ZnOy prepared by sol-gel method. Characterization of the catalyst by XRD and FTIR confirmed that La1-xKxZnOy did not exhibit perovskite phase but formed mixed metal oxides. 110 mg of the catalyst-soot mixture in tight contact (10:1 ratio was taken in order to determine the kinetic model, activation energy and Arrhenius constant of the oxidation reaction under the high air flow rate assuming pseudo first order reaction. The activation energy and Arrhenius constant were found to be 138 kJ/mol and 6.46x1010 min-1, respectively. © 2014 BCREC UNDIP. All rights reservedReceived: 26th April 2014; Revised: 27th May 2014; Accepted: 28th June 2014How to Cite: Prasad, R., Kumar, A., Mishra, A. (2014. Isothermal Kinetics of Diesel Soot Oxidation over La0.7K0.3ZnOy Catalysts. Bulletin of Chemical Reaction Engineering & Catalysis, 9(3: 192-200. (doi: 10.9767/bcrec.9.3.6773.192-200Permalink/DOI: http://dx.doi.org/10.9767/bcrec.9.3.6773.192-200

Summary report of the experiences from TVO's site investigations

International Nuclear Information System (INIS)

Oehberg, A.; Saksa, P.; Ahokas, H.; Ruotsalainen, P.; Snellman, M.

1994-05-01

Teollisuuden Voima Oy (TVO) has completed preliminary site investigations at five sites in Finland. At the end of 1992 TVO presented the final report to the authorities. The preliminary site investigation phase 1986-1992 was conducted according to the investigation programme compiled by TVO. The aim of this report was to compile a report on experiences from TVOs site investigations. The main interest was focused on investigation strategies and the most important investigation methods for the conceptual modelling. The objective of the preliminary site investigations was to obtain data on the bedrock properties in order to evaluate the areas. The programme was divided into four stages, each stage having its own sub-objective. The site-specific investigation programme for each site included a large common part and a small site-specific part. The strategies (objectives) and experiences from different disciplines, geology, hydrogeochemistry, geophysics and geohydrology, are presented in the report. The conceptual modelling work procedure including both bedrock and groundwater modelling is described briefly using the Olkiluoto site as an example. Each of the other areas has undergone similar phases of work. The uncertainties associated with conceptual modelling are also discussed. The usefulness of the investigation strategy and the investigation methods for conceptual modelling is discussed in the report. Some new equipment, methods or enhancements that have not yet been used in TVOs site investigations have become new tools in site characterisation and are briefly presented in the report. 52 refs, 35 figs, 1 tab

Condensation driven water hammer studies for feedwater distribution pipe

Energy Technology Data Exchange (ETDEWEB)

Savolainen, S.; Katajala, S.; Elsing, B.; Nurkkala, P.; Hoikkanen, J. [Imatran Voima Oy, Vantaa (Finland); Pullinen, J. [IVO Power Engineering Ltd., Vantaa (Finland); Logvinov, S.A.; Trunov, N.B.; Sitnik, J.K. [EDO Gidropress (Russian Federation)

1997-12-31

Imatran Voima Oy, IVO, operates two VVER 440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of the feed water distribution (FWD) pipes were observed in 1989. In closer examinations FWD-pipe T-connection turned out to suffer from severe erosion corrosion damages. Similar damages have been found also in other VVER 440 type NPPs. In 1994 the first new FWD-pipe was replaced and in 1996 extensive water hammer experiments were carried out together with EDO Gidropress in Podolsk. After the first phase of the experiments some fundamental changes were made to the construction of the FWD-pipe. The object of this paper is to give short insight to the design of the new FWD-pipe concentrating on water hammer experiments. (orig.).

Condensation driven water hammer studies for feedwater distribution pipe

International Nuclear Information System (INIS)

Savolainen, S.; Katajala, S.; Elsing, B.; Nurkkala, P.; Hoikkanen, J.; Pullinen, J.; Logvinov, S.A.; Trunov, N.B.; Sitnik, J.K.

1997-01-01

Imatran Voima Oy, IVO, operates two VVER 440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of the feed water distribution (FWD) pipes were observed in 1989. In closer examinations FWD-pipe T-connection turned out to suffer from severe erosion corrosion damages. Similar damages have been found also in other VVER 440 type NPPs. In 1994 the first new FWD-pipe was replaced and in 1996 extensive water hammer experiments were carried out together with EDO Gidropress in Podolsk. After the first phase of the experiments some fundamental changes were made to the construction of the FWD-pipe. The object of this paper is to give short insight to the design of the new FWD-pipe concentrating on water hammer experiments. (orig.)

Condensation driven water hammer studies for feedwater distribution pipe

Energy Technology Data Exchange (ETDEWEB)

Savolainen, S; Katajala, S; Elsing, B; Nurkkala, P; Hoikkanen, J [Imatran Voima Oy, Vantaa (Finland); Pullinen, J [IVO Power Engineering Ltd., Vantaa (Finland); Logvinov, S A; Trunov, N B; Sitnik, J K [EDO Gidropress (Russian Federation)

1998-12-31

Imatran Voima Oy, IVO, operates two VVER 440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of the feed water distribution (FWD) pipes were observed in 1989. In closer examinations FWD-pipe T-connection turned out to suffer from severe erosion corrosion damages. Similar damages have been found also in other VVER 440 type NPPs. In 1994 the first new FWD-pipe was replaced and in 1996 extensive water hammer experiments were carried out together with EDO Gidropress in Podolsk. After the first phase of the experiments some fundamental changes were made to the construction of the FWD-pipe. The object of this paper is to give short insight to the design of the new FWD-pipe concentrating on water hammer experiments. (orig.).

Summary report on groundwater chemistry

International Nuclear Information System (INIS)

Lampen, P.; Snellman, M.

1993-07-01

The preliminary site investigations for radioactive waste disposal (in Finland) carried out by Teollisuuden Voima Oy (TVO) during the period 1987 to 1992 yielded data on hydrogeochemistry from a total 337 water samples. The main objective of the groundwater chemistry studies was to characterize groundwaters at the investigation sites and, specifically, to create a concept for the mean residence times and evolution of groundwater by means of isotopic analyses. Moreover, the studies yielded input data for geochemical modelling and the performance assessment. Samples were taken from deep boreholes (with a depth of 500 to 1000 m), percussion-drilled boreholes (depth approx. 200 m), flushing-water wells (approx. 100 m) and multi-level pietzometers (approx. 100 m) used in the hydrological tests. The water used for drilling the deep boreholes was taken from local flushing-water wells, whose water was also analyzed in detail. The flushing water used in drilling was marked with two tracers, iodine and uranine, analyzed with two different methods. For reference purposes, samples were also taken from surficial and groundwaters over a large area surrounding the investigation site. Precipitation over a period of at least one year was collected at all the five investigation sites and the samples were analyzed in great detail, particularly with regard to isotopes. Similarly, snow profile samples representing precipitation during the entire winter was taken from each site at least once

ROCK-CAD - computer aided geological modelling system

International Nuclear Information System (INIS)

Saksa, P.

1995-12-01

The study discusses surface and solid modelling methods, their use and interfacing with geodata. Application software named ROCK-CAD suitable for geological bedrock modelling has been developed with support from Teollisuuden Voima Oy (TVO). It has been utilized in the Finnish site characterization programme for spent nuclear fuel waste disposal during the 1980s and 1990s. The system is based on the solid modelling technique. It comprises also rich functionality for the particular geological modelling scheme. The ROCK-CAD system provides, among other things, varying graphical vertical and horizontal intersections and perspective illustrations. The specially developed features are the application of the boundary representation modelling method, parametric object generation language and the discipline approach. The ROCK-CAD system has been utilized in modelling spatial distribution of rock types and fracturing structures in TVO's site characterization. The Olkiluoto site at Eurajoki serves as an example case. The study comprises the description of the modelling process, models and illustration examples. The utilization of bedrock models in site characterization, in tentative repository siting as well as in groundwater flow simulation is depicted. The application software has improved the assessment of the sites studied, given a new basis for the documentation of interpretation and modelling work, substituted hand-drawing and enabled digital transfer to numerical analysis. Finally, aspects of presentation graphics in geological modelling are considered. (84 refs., 30 figs., 11 tabs.)

Modernization and power upgrading of the Loviisa NPP

Energy Technology Data Exchange (ETDEWEB)

Keskinen, A. [IVO Power Engineering Ltd., Vantaa (Finland)

1997-12-31

In 1995, Imatran Voima Oy (IVO) started a project for modernization and power upgrading of the Loviisa NPP. The main objectives of the project are to ensure plant safety, to increase electricity production and to improve the expertise of the IVO staff. The total electricity output of Loviisa 1 and 2 units is planned to be increased by about 100 MW. This will be achieved through renovation of the steam turbines and through gradual increase in the thermal reactor power up to 1,500 MW from the present level of 1,375 MW. The Loviisa NPP Final Safety Analysis Report has been revised to a great extent in connection with the licensing process of the reactor power upgrading. The project also includes certain improvements in the primary and safety systems to ensure plant safety. The total cost estimate of the project is around 200 million FIM. The project implementation started in 1995 and in accordance with the plans in 2000 after several phases the last measures at power plant will be completed. (orig.). 4 refs.

Modernization and power upgrading of the Loviisa NPP

International Nuclear Information System (INIS)

Keskinen, A.

1997-01-01

In 1995, Imatran Voima Oy (IVO) started a project for modernization and power upgrading of the Loviisa NPP. The main objectives of the project are to ensure plant safety, to increase electricity production and to improve the expertise of the IVO staff. The total electricity output of Loviisa 1 and 2 units is planned to be increased by about 100 MW. This will be achieved through renovation of the steam turbines and through gradual increase in the thermal reactor power up to 1,500 MW from the present level of 1,375 MW. The Loviisa NPP Final Safety Analysis Report has been revised to a great extent in connection with the licensing process of the reactor power upgrading. The project also includes certain improvements in the primary and safety systems to ensure plant safety. The total cost estimate of the project is around 200 million FIM. The project implementation started in 1995 and in accordance with the plans in 2000 after several phases the last measures at power plant will be completed. (orig.)

Modernization and power upgrading of the Loviisa NPP

Energy Technology Data Exchange (ETDEWEB)

Keskinen, A [IVO Power Engineering Ltd., Vantaa (Finland)

1998-12-31

In 1995, Imatran Voima Oy (IVO) started a project for modernization and power upgrading of the Loviisa NPP. The main objectives of the project are to ensure plant safety, to increase electricity production and to improve the expertise of the IVO staff. The total electricity output of Loviisa 1 and 2 units is planned to be increased by about 100 MW. This will be achieved through renovation of the steam turbines and through gradual increase in the thermal reactor power up to 1,500 MW from the present level of 1,375 MW. The Loviisa NPP Final Safety Analysis Report has been revised to a great extent in connection with the licensing process of the reactor power upgrading. The project also includes certain improvements in the primary and safety systems to ensure plant safety. The total cost estimate of the project is around 200 million FIM. The project implementation started in 1995 and in accordance with the plans in 2000 after several phases the last measures at power plant will be completed. (orig.). 4 refs.

Assessment of health risks brought about by transportation of spent fuel

International Nuclear Information System (INIS)

Suolanen, V.; Lautkaski, R.; Rossi, J.

1999-03-01

In the study health risks caused by transportation of spent fuel from Olkiluoto and from Loviisa NPP's to the planned disposal site have been evaluated. The Olkiluoto NPP is owned by Teollisuuden Voima Oy (TVO) and the Loviisa NPP, situated at Haestholmen, by Fortum Power and Heat Oy. According to the base scenario of 40 years use of the current NPP's the total amount of spent fuel will be 1840 tU (TVO) and 860 tU (Fortum). Annually, 110 tU on the average and at most 250 tU will be transported to the disposal site. The considered transportation routes are from Olkiluoto to Haestholmen, from Olkiluoto to Kivetty, from Olkiluoto to Romuvaara, from Haestholmen to Olkiluoto, from Haestholmen to Kivetty and from Haestholmen to Romuvaara. The considered transportation modes are truck, rail or ship, or combinations of these modes. Each transportation route has been divided into homogenised sequences with respect to population density and/or route type. Total amount of analysed route options were 40, some route sequences are overlapping. Radiation exposures to the population along the routes have been calculated in normal, incident and accident situations during transportation. Occupational radiation doses to the personnel have been estimated for normal transportation only. The consequences of normal transportation have been evaluated based on RADTRAN-model, developed by the Sandia National Laboratories. As incidents, stopping of spent fuel transportation for an exceptionally long period of time, and in another case contamination of outer surface of spent fuel cask have been considered. Expected collective doses and health risks of transportation accidents connected to the routes have been calculated with RADTRAN-model. Single hypothetical transport accidents with pessimistic release assumptions have been further analysed in more detail with the ARANO-model, developed by VTT (Technical Research Centre of Finland). (orig.)

HPK Liiga Oy:n Facebook-markkinoinnin mittaaminen

OpenAIRE

Anttila, Pasi

2016-01-01

Opinnäytetyön toimeksiantaja on HPK Liiga Oy. Työn taustalla toimeksiantajan osalta oli lähteä kehittämään sosiaalisen median mittaamista, ja opinnäytetyön tekijä oli myös kiinnostunut tämän asian tutkimisesta. Taustalla olivat myös HPK Liiga Oy:n strategiset muutokset sekä yhtiöittäminen rekisteröidystä yhdistyksestä osakeyhtiöksi. Työn tavoitteena oli selvittää, millä mittareilla HPK Liiga Oy:n kannattaisi mitata Facebook-markkinointiaan ydintavoitteiden ollessa asiakkaiden sitouttamin...

Operation of Finnish nuclear power plants. Quarterly report 4th quarter, 1994 and annual summary

International Nuclear Information System (INIS)

Tossavainen, K.

1995-05-01

The Loviisa NPP units were in power operation the whole last quarter, with the exception of a reactor scram at Loviisa 1. The load factor average of all Finnish plant units was 100.2 %. The annual average was 90.0 %. All events in the fourth annual quarter were assigned level 0 (no safety significance) on the international INES scale. Four events in 1994 were classified level 1 (an anomaly). The Finnish Centre for Radiation and Nuclear Safety in December approved Imatran Voima Oy's application to extend the operation of the reactor pressure vessel of Loviisa 2 until the annual maintenance outage of 2010. During this quarter, a batch of spent fuel from Loviisa power plant was transported to Russia. Occupational doses and radioactive releases off-site were below authorised limits. Only such quantities of plant-based radioactive materials were measurable in samples collected around the plants as have no bearing on the radiation exposure of the population. The report includes a summary of all the items described in the Quarterly Reports of 1994. (8 figs., 4 tabs.)

Social media marketing communication plan for Hauskafe Oy

OpenAIRE

Uzunova, Aleksandra; Franko, Jan

2017-01-01

The case company of this project-based thesis is Hauskafe Oy, an SME company located in Espoo, Finland. Following examples of best practices in the field, Hauskafe Oy recognised the need of designing a social media marketing plan that will allow to build the brand, improve customer loyalty and as a final goal – increase the sales. A social media marketing communication plan for Hauskafe Oy is the outcome of this thesis. The theoretical framework of the thesis is a desktop study that discu...

Fuel reliability experience in Finland

International Nuclear Information System (INIS)

Kekkonen, L.

2015-01-01

Four nuclear reactors have operated in Finland now for 35-38 years. The two VVER-440 units at Loviisa Nuclear Power Plant are operated by Fortum and two BWR’s in Olkiluoto are operated by Teollisuuden Voima Oyj (TVO). The fuel reliability experience of the four reactors operating currently in Finland has been very good and the fuel failure rates have been very low. Systematic inspection of spent fuel assemblies, and especially all failed assemblies, is a good practice that is employed in Finland in order to improve fuel reliability and operational safety. Investigation of the root cause of fuel failures is important in developing ways to prevent similar failures in the future. The operational and fuel reliability experience at the Loviisa Nuclear Power Plant has been reported also earlier in the international seminars on WWER Fuel Performance, Modelling and Experimental Support. In this paper the information on fuel reliability experience at Loviisa NPP is updated and also a short summary of the fuel reliability experience at Olkiluoto NPP is given. Keywords: VVER-440, fuel reliability, operational experience, poolside inspections, fuel failure identification. (author)

Developing and design a website for mc kalla oy

OpenAIRE

Bekele, Henok

2013-01-01

This bachelor thesis is about Website development and design. I have a chance to work with Mc kalla Oy. Mc kalla Oy is a construction company from Kempele which was founded 2011. They have projects in Central-Finland, through Northern Finland to Lapland. This thesis is to develop and design a new website to Mc kalla Oy. Wordpress is used to develop the new website. For the development process I use school server (.opiskelijaprojektit.net). The Thesis contains two main parts designing the ...

Geological and geophysical investigations in the selection and characterization of the disposal site for high-level nuclear waste in Finland

Energy Technology Data Exchange (ETDEWEB)

Paulamaki, S.; Paananen, M.; Kuivamaki, A. [Geological Survey of Finland, Espoo (Finland); Wikstrom, L. [Posiva Oy, Olkiluoto (Finland)], e-mail: seppo.paulamaki@gtk.fi

2011-07-01

Two power companies, Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy, are preparing for the final disposal of spent nuclear fuel deep in the Finnish bedrock. In the initial phase of the site selection process in the late 1970s and early 1980s, the Geological Survey of Finland (GTK) examined the general bedrock factors that would have to be taken into account in connection with final disposal with reference to the international guidelines adapted to Finnish conditions. On the basis of extensive basic research data, it was concluded that it is possible to find a potential disposal site that fulfils the geological safety criteria. In the subsequent site selection survey covering the whole of Finland, carried out by GTK in 1983-1985, 101 potential investigation areas were discovered. Eventually, five areas were selected by TVO for preliminary site investigations: Romuvaara and Veitsivaara in the Archaean basement complex, Kivetty and Syyry in the Proterozoic granitoid area, and Olkiluoto (TVO's NPP site) in the Proterozoic migmatite area. The preliminary site investigations at the selected sites in 1987-1992 comprised deep drillings together with geological, geophysical, hydrogeological and hydrogeochemical investigations. A conceptual geological bedrock model was constructed for each site, including lithology, fracturing, fracture zones and hydrogeological conditions. On the basis of preliminary site investigations, TVO selected Romuvaara, Kivetty and Olkiluoto for detailed site investigations to be carried out during 1993-2000. After the feasibility studies, the island of Haestholmen, where Fortum's Loviisa nuclear power plant is located, was added to the list of potential disposal sites. In the detailed site investigations, additional data on bedrock were gathered, the previous conceptual geological, hydrogeological and hydrogeochemical models were complemented, the rock mechanical properties of the bedrock were examined, and the constructability

Results of monitoring at Olkiluoto in 2009. Environment

Energy Technology Data Exchange (ETDEWEB)

Haapanen, A. (ed.) (Haapanen Forest Consulting, Vanhakylae (Finland))

2010-10-15

This Working Report presents the main results of Posiva Oy's environmental monitoring programme on Olkiluoto Island in 2009. These summary reports have been published since 2005. The environmental monitoring system supervised by Posiva Oy produces input for biosphere modelling for long-term safety purposes as well as for monitoring the state of the environment during the construction (and later operation) of ONKALO underground characterization facility. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). Monitoring has been carried out for varying periods of time depending on the sector: some monitoring activities performed by TVO originate from the 1970s and the repository-related environmental monitoring of Olkiluoto from the early 2000s. The monitoring programme evolves according to the experiences gained from the modelling work and an increased understanding of the site. Augmentations in 2009 include e.g. establishment of a new forest intensive monitoring plot (FIP14), continuation of studies on fine roots and on the species composition and abundances of small mammals. Line transect samplings of ants, terrestrial snails and earthworms were carried out and a systematic monitoring of island birds was started. In addition, a project was started where the sediment load and factors affecting the sediment transportation into Eurajoensalmi bay is examined. Dust produced during construction of the third nuclear power unit (OL3), ONKALO and related infrastructure can be seen in the soil solution and deposition results. Furthermore, the construction works and road traffic have a raising effect on the noise levels of the immediate surroundings. The land-use continues to change, but the remaining natural environment resembles other coastal locations. The young age of the soils and the closeness of the sea are reflected in the soil properties. Mammalian fauna on the island is typical of coastal

Results of monitoring at Olkiluoto in 2009. Environment

International Nuclear Information System (INIS)

Haapanen, A.

2010-10-01

This Working Report presents the main results of Posiva Oy's environmental monitoring programme on Olkiluoto Island in 2009. These summary reports have been published since 2005. The environmental monitoring system supervised by Posiva Oy produces input for biosphere modelling for long-term safety purposes as well as for monitoring the state of the environment during the construction (and later operation) of ONKALO underground characterization facility. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). Monitoring has been carried out for varying periods of time depending on the sector: some monitoring activities performed by TVO originate from the 1970s and the repository-related environmental monitoring of Olkiluoto from the early 2000s. The monitoring programme evolves according to the experiences gained from the modelling work and an increased understanding of the site. Augmentations in 2009 include e.g. establishment of a new forest intensive monitoring plot (FIP14), continuation of studies on fine roots and on the species composition and abundances of small mammals. Line transect samplings of ants, terrestrial snails and earthworms were carried out and a systematic monitoring of island birds was started. In addition, a project was started where the sediment load and factors affecting the sediment transportation into Eurajoensalmi bay is examined. Dust produced during construction of the third nuclear power unit (OL3), ONKALO and related infrastructure can be seen in the soil solution and deposition results. Furthermore, the construction works and road traffic have a raising effect on the noise levels of the immediate surroundings. The land-use continues to change, but the remaining natural environment resembles other coastal locations. The young age of the soils and the closeness of the sea are reflected in the soil properties. Mammalian fauna on the island is typical of coastal

Geological and geophysical investigations in the selection and characterization of the disposal site for high-level nuclear waste in Finland

Energy Technology Data Exchange (ETDEWEB)

Paulamaki, S; Paananen, M; Kuivamaki, A [Geological Survey of Finland, Espoo (Finland); Wikstrom, L. [Posiva Oy, Olkiluoto (Finland)], e-mail: seppo.paulamaki@gtk.fi

2011-07-01

Two power companies, Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy, are preparing for the final disposal of spent nuclear fuel deep in the Finnish bedrock. In the initial phase of the site selection process in the late 1970s and early 1980s, the Geological Survey of Finland (GTK) examined the general bedrock factors that would have to be taken into account in connection with final disposal with reference to the international guidelines adapted to Finnish conditions. On the basis of extensive basic research data, it was concluded that it is possible to find a potential disposal site that fulfils the geological safety criteria. In the subsequent site selection survey covering the whole of Finland, carried out by GTK in 1983-1985, 101 potential investigation areas were discovered. Eventually, five areas were selected by TVO for preliminary site investigations: Romuvaara and Veitsivaara in the Archaean basement complex, Kivetty and Syyry in the Proterozoic granitoid area, and Olkiluoto (TVO's NPP site) in the Proterozoic migmatite area. The preliminary site investigations at the selected sites in 1987-1992 comprised deep drillings together with geological, geophysical, hydrogeological and hydrogeochemical investigations. A conceptual geological bedrock model was constructed for each site, including lithology, fracturing, fracture zones and hydrogeological conditions. On the basis of preliminary site investigations, TVO selected Romuvaara, Kivetty and Olkiluoto for detailed site investigations to be carried out during 1993-2000. After the feasibility studies, the island of Haestholmen, where Fortum's Loviisa nuclear power plant is located, was added to the list of potential disposal sites. In the detailed site investigations, additional data on bedrock were gathered, the previous conceptual geological, hydrogeological and hydrogeochemical models were complemented, the rock mechanical properties of the bedrock were examined, and the constructability and the

Sunray project - A long-term, nationwide educational process

International Nuclear Information System (INIS)

Nikula, Anneli

2000-01-01

The Sunray project is a nationwide educational process coordinated by the Economic Information Bureau (TaT Group) for ninth graders in Finnish comprehensive schools. The project aims at giving thorough and versatile information on radiation within the framework of various subjects (physics, biology, domestic science, history, European languages, mother tongue, health education etc.). The Sunray project covers all ninth graders of the existing 600 Finnish comprehensive schools; in all involving some 65 000 pupils. The project, which has been repeated five times, was initiated as part of the European Science and Technology week in 1995. During the first two years it was strongly linked with the science week as natural sciences were seen as a good framework for the chosen perspective. Since 1997, the project has been run as an event in its own right. The project has applied the method of processing integrated groups of themes, which is an objective of the comprehensive school system and the experimental method of science. As schools make their own decisions about the educational programmes to be adopted every semester, the project has been marketed to schools at the beginning of May. The TaT Group has arranged marketing events in some 10 localities in Finland. The Economic Information Bureau of Finland coordinates the project and in 1995-2000 the Radiation and Nuclear Safety Authority (STUK), the Finnish Energy Industries' Federation, the Finnish Electricity Association, Fortum Oyj and Teollisuuden Voima Oy have participated in the project

Bedrock model of the Romuvaara area

International Nuclear Information System (INIS)

Saksa, P.; Paananen, M.; Paulamaeki, S.; Anttila, P.; Pitkaenen, P.; Front, K.; Vaittinen, T.

1992-05-01

Site for the final disposal of the spent nuclear fuel investigations implemented in accordance with the research programme drawn up by Teollisuuden Voima Oy were carried out at Romuvaara, Kuhmo, in 1987 - 1991. Model of the site were compiled and used for describing the rock types, fractures, fracturing structures and geohydrological conditions, the main emphasis being on the examination of the bedrock fracturing and related hydraulic conductivity. Three-dimensional models were used for the classification of the various properties of the bedrock structures. The descriptive models were gathered together in a computerized system to facilitate illustration and strage. The rock types at Romuvaara are gneiss, mica gneiss, leucotonalite gneiss, amphibolite, granodiorite and metadiabase. The structural model for fracturing at the site contains 19 zones described in terms of a number of properties. The fracturing observed at Romuvaara ranges from local occurences of dence fracturing to significant, altered fracture zones. The structural model includes deduced values for hydraulic conductivity, deduced points of flow in the boreholes and measured hydraulic heads.Various classifications were used for assessment of hydraulic conductivity in the zones and solid bedrock, and in both cases conductivity was found to diminish with depth. Measured hydraulic heads were mostly found to support structural interpretation. The results were used for estimation of a three-dimensional hydraulic head distribution. Results from pumping tests carried out in the significant flow zone support the geometric interpretation

In-situ experiments to investigate rock matrix retention properties in ONKALO, Olkiluoto, Finland

Energy Technology Data Exchange (ETDEWEB)

Voutilainen, Mikko; Helariutta, Kerttuli [Helsinki Univ. (Finland). Dept. of Chemistry; Poteri, Antti [Technical Research Centre of Finland VTT (Finland); and others

2015-07-01

Spent nuclear fuel from nuclear power plants, owned by TVO (Teollisuuden Voima Oy) and Fortum, is planned to be disposed to a repository at a depth of more than 400 meters in the bedrock of Olkiluoto (Eurajoki, Finland). The repository system of multiple release barriers consists of both manmade and natural barriers. The surrounding rock acts as the last barrier if other barriers fail during passage of the millennia. Therefore, safe disposal of spent nuclear fuel requires information on the radionuclide transport and retention properties within the porous and water-containing rock matrix along the water conducting flow paths. To this end, various types of experiments are being performed and planned within ONKALO, the underground rock characterization facility in Olkiluoto, as part of the project @''rock matrix REtention PROperties'' (REPRO). The research site is located at a depth of 420 meters close to the repository site. The aim is to study the diffusion and sorption properties of nuclear compounds in the rock matrix under real in-situ conditions. The first in-situ experiment was performed during 2012 using HTO, Na-22, Cl-36 and I-125 as tracer nuclides. Breakthrough curves show retention and asymptotic behavior that are in-line with those caused by matrix diffusion and sorption were observed in their breakthrough curves. Weak sorption was also observed in the breakthrough curves of Na-22 and I-125.

KUSTANNUS JA KANNATTAVUUSLASKENNAN KEHITTÄMINEN CASE KOTEK FACTORY SERVICE OY

OpenAIRE

Ilmonen, Hanna

2009-01-01

Opinnäytetyön toimeksiantajana oli Kotek Factory Service Oy ja kohteena oli Kotek Factory Service Oy:n maalaamo. Kotek Factory Service on Chesterton ARC- pinnoitteiden maahantuoja ja myyjä, joka vastaa tuotteidensa erilaisista urakoinneista, täydellisinä palvelukokonaisuuksina. Opinnäytetyön tavoitteena oli saada aikaiseksi toimintaehdotus siitä, kuinka Kotek Factory Service Oy voisi kehittää kustannus ja kannattavuuslaskentaansa maalaamon ja koko yrityksen osalta. Ongelmaan haettiin ratk...

Building a new nuclear power plant in Finland? Studies performed. Annex 2

International Nuclear Information System (INIS)

Patrakka, E.

2002-01-01

The electricity consumption per capita is high in Finland due to the country's industrial structure and to the climatic conditions. Industry consumes 55% of the electricity in Finland. The demand of electricity is expected to grow at a rate of 1.5% a year until 2010, and further at a yearly rate of 1% until 2015. This will require 3800 MW of new generating capacity by 2015. A recent study indicates that in base-load power production in Finland the generating costs of a nuclear plant are the lowest in comparison with generation using coal, natural gas or peat. The difference to coal would be 9%, to gas 18% and to peat 40%. The target for Finland to reduce greenhouse gas emissions under the EU burden sharing is 0%. In comparison with business as usual scenarios, however, the reduction need is of the magnitude of 20%, one of the hardest in the EU. Finland already has taken into use the methods, which now are considered essential within the EU for reducing the CO 2 releases. Teollisuuden Voima Oy (TVO) submitted on 15 November 2000 to the Council of State an application for a decision in principle concerning the construction of additional nuclear capacity. The submission of the application is reasoned by the shareholders' need for additional electricity. Furthermore, nuclear power, together with renewable energy sources, makes it possible to comply with the Kyoto protocol commitments. The actual investment decision can be made first after a positive decision in principle has been received from the Council of State and the Parliament. The submission of the application was preceded by a number of studies, the contents of which are summarised. (author)

Mortality, fertility, and the OY ratio in a model hunter-gatherer system.

Science.gov (United States)

White, Andrew A

2014-06-01

An agent-based model (ABM) is used to explore how the ratio of old to young adults (the OY ratio) in a sample of dead individuals is related to aspects of mortality, fertility, and longevity experienced by the living population from which the sample was drawn. The ABM features representations of rules, behaviors, and constraints that affect person- and household-level decisions about marriage, reproduction, and infant mortality in hunter-gatherer systems. The demographic characteristics of the larger model system emerge through human-level interactions playing out in the context of "global" parameters that can be adjusted to produce a range of mortality and fertility conditions. Model data show a relationship between the OY ratios of living populations (the living OY ratio) and assemblages of dead individuals drawn from those populations (the dead OY ratio) that is consistent with that from empirically known ethnographic hunter-gatherer cases. The dead OY ratio is clearly related to the mean ages, mean adult mortality rates, and mean total fertility rates experienced by living populations in the model. Sample size exerts a strong effect on the accuracy with which the calculated dead OY ratio reflects the actual dead OY ratio of the complete assemblage. These results demonstrate that the dead OY ratio is a potentially useful metric for paleodemographic analysis of changes in mortality and mean age, and suggest that, in general, hunter-gatherer populations with higher mortality, higher fertility, and lower mean ages are characterized by lower dead OY ratios. Copyright © 2014 Wiley Periodicals, Inc.

PUHELINPALVELUN FACEBOOK-MAINOS : Case: Harmonia Care Oy

OpenAIRE

Tirkkonen, Mari

2014-01-01

Opinnäytetyön toimeksiantaja oli Harmonia Care Oy. Tutkimuksessa käytettiin kvantitatiivista tutkimusmenetelmää. Opinnäytetyö oli luonteeltaan toiminnallinen opinnäytetyö, jossa samalla suunniteltiin, toteutettiin ja kehitettiin yrityksen sähköistä markkinointia. Tutkimuksessa haettiin vastausta seuraaviin kysymyksiin: ” Onko Facebook-mainonnasta hyötyä Harmonia Care Oy:lle?” ja ”Millainen markkinointikampanja tukee yrityksen strategiaa parhaiten?” Opinnäytetyössä suunniteltiin ja toteute...

Developing an e-commerce Website for Spicetown Oy, using Drupal.

OpenAIRE

Inegbedion, Usunobun

2015-01-01

This project is aimed at creating a website to be used for e-commerce by Spicetown Oy, a wholesaler of African and Asian food products based in Helsinki. Spicetown Oy is a traditional brick-and-mortar business in the process of transitioning into a business model combining tra-ditional business carried out on physical premises with running an online shop. The main aim of this project is to design and build a website with an online store for Spicetown Oy. The website is implemented using Drup...

Customer Satisfaction in Internal Customer Service : Case: Abloy Oy Internal Customer Service

OpenAIRE

Turunen, Susanna

2011-01-01

ABSTRACT Turunen, Susanna Marita 2011. Customer Satisfaction in Internal Customer Service. Case: Abloy Oy Internal Customer Service. Master’s thesis. Kemi-Tornio University of Applied Sciences. Business and Culture. Pages 73. Appendix 1. This thesis discusses and studies service quality and customer satisfaction in internal customer service. The main objective is to find out what the service quality level in the internal customer service at Abloy Oy is and whether there exists a diffe...

IAEA Mission Sees Safety Commitment at Finland's New Olkiluoto Reactor Before Planned Start in December

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts observed a commitment to safety by the operator of Unit 3 at Finland’s Olkiluoto Nuclear Power Plant, ahead of the Evolutionary Pressurised Water Reactor’s (EPR) planned connection to the grid in December. The team also identified areas for further enhancements as the operator prepares to put the reactor online. The Pre-Operational Safety Review Team (Pre-OSART) concluded an 18-day mission today to assess operational safety at the 1600 MW reactor, located about 280 km northwest of the capital, Helsinki. Finland has engaged France’s Areva SA together with Germany’s Siemens to construct and commission the unit. The operator is Teollisuuden Voima (TVO). Pre-OSART missions aim to improve operational safety by objectively assessing safety performance using the IAEA’s safety standards and proposing recommendations for improvement where appropriate. The review covered the areas of leadership and management for safety; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency preparedness and response; accident management; and commissioning. The team identified a number of good practices that will be shared with the nuclear industry globally, including: • The plant has developed and implemented an efficient system for improving knowledge and skills of staff members. • The plant has developed and validated a unique method for performing suspended solids analysis using a microscope, imaging software and a digital camera. • The plant has introduced a system for systematically assessing nuclear safety culture in the plant supplier organization during construction and commissioning. The mission made several recommendations to improve operational safety, including: • Plant management should set appropriate expectations, communicate them to staff and reinforce them in the field. • The plant should improve the

Local extinction and reignition of the flame; Liekin paikallinen sammuminen ja uudelleen syttyminen

Energy Technology Data Exchange (ETDEWEB)

Kjaeldman, L. [VTT Energia, Espoo (Finland); Brink, A. [Aabo Akademi, Turku (Finland)

1996-12-01

A model of the local extinction and reignition of the flame suitable to be used in computational fluid dynamic analysis of primarily multi-burner furnaces is developed. The model is implemented in the computational environment Ardemus of VTT and Imatran Voima Oy, and tested against well defined experiments. The model makes the simulation of especially the near burner processes more realistic. (author)

Instrumentation renewal at the FIR 1 research reactor in Finland

International Nuclear Information System (INIS)

Bars, Bruno; Kall, Leif

1982-01-01

The Finnish TRIGA Mark II reactor (FIR 1 100 kW, later 250 kW steady state power and pulsing capability up to 250 MW) has been in operation for 20 years. The reactor is the only research reactor in Finland and is an important research training and service facility, which obviously will be operated for 10...20 years ahead. The mechanical parts of the reactor are in good shape. Some minor modifications have previously been made in the instrumentation. However, the original instrumentation could hardly have been used for 10...20 years ahead without extensive modifications and modernization. After a careful evaluation and planning process the whole reactor instrumentation was renewed in 1981 at a cost of about 400 000 dollar. The renewal was carried out in cooperation with the Central Research Institute for Physics (KFKI) at the Hungarian Academy of Sciences, which delivered the nuclear part of the instrumentation and with the Finnish company Valmet Oy Instrument Works, which delivered the conventional instrumentation, including the automatic power control system and the control console. The instrumentation, which is located in-a new isolated control room is based on modern industrial standard modular units with standardized signal ranges, electronic testing possibilities, galvanically isolated outputs etc. The instrument renewal project was brought successfully to completion in November 1981 after only about 10 working days of shut down time. The reactor is now in routine operation and the experiences gained from the new instrumentation are excellent. (author)

Most advanced HTP fuel assembly design for EPR

International Nuclear Information System (INIS)

Francillon, Eric; Kiehlmann, Horst-Dieter

2006-01-01

End 2003, the Finnish electricity utility Teollisuuden Voima Oy (TVO) signed the contract for building an EPR in Olkiluoto (Finland). Mid 2004, the French electricity utility EDF selected an EPR to be built in France. In 2005, Framatome ANP, an AREVA and Siemens company, announced that they will be pursuing a design certification in the U.S. The EPR development is based on the latest PWR product lines of former Framatome (N4) and Siemens Nuklear (Konvoi). As an introductory part, different aspects of the EPR core characteristics connected to fuel assembly design are presented. It includes means of ensuring reactivity control like hybrid AIC/B4C control rod absorbers and gadolinium as burnable absorber integrated in fuel rods, and specific options for in-core instrumentation, such as Aeroball type instrumentation. Then the design requirements for the EPR fuel assembly are presented in term of very high burnup capacity, rod cladding and fuel assembly reliability. Framatome ANP fuel assembly product characteristics meeting these requirements are then described. EPR fuel assembly design characteristics benefit from the experience feedback of the latest fuel assembly products designed within Framatome ANP, leading to resistance to assembly deformation, high fuel rod restraint and prevention of handling hazards. EPR fuel assembly design features the best components composing the cornerstones of the upgraded family of fuel assemblies that FRAMATOME ANP proposes today. This family is based on a set of common characteristics and associated features, which include the HMP grid as bottom end spacer, the MONOBLOC guide tube and the Robust FUELGUARD as lower tie plate, the use of the M5 Alloy, as cladding and structure material. This fully re-crystallized, ternary Zr-Nb-O alloy produces radically improved in-reactor corrosion, very low hydrogen uptake and growth and an excellent creep behavior, which are described there. EPR fuel assembly description also includes fuel rod

Degradation modelling for the concrete silo in TVO's VLJ repository

International Nuclear Information System (INIS)

Alcorn, S.R.; Christian-Frear, T.L.; Wallace, M.

1991-05-01

Teollisuuden Voima Oy (TVO) is currendy construcing in Finland an underground repository (the VLJ repository) for storage of low- and intermediate-level radioactive wastes generated at the Olkiluoto (TVO I and TVO II) nuclear power plant. Intermediate level wastes will be emplaced inside a large concrete silo, which is the principal engineered barrier in the repository. The primary objective of the investigation is to develop an estimate of the length of time it will take for the silo to degrade due to interaction with groundwater to the point that it fails to perform as designed. A secondary objective is to develop a methodology to estimate the length of time required for radio nuclides to migrate from the region inside the silo through the silo wall and floor to the accessible environment as a function of cement and concrete properties. Chemical modeling techniques using the codes EQ3NR/EQ6 were employed to model the degradation of the repository concrete due to interaction with groundwater, and porous flow and diffusion modeling approaches were taken to: (1) estimate the time it would take groundwater and ions to travel into and out of the silo concrete, and (2) determine how these travel times change as the concrete degrades. The results of the investigation suggest that the hydraulic conductivity of the concrete will decrease over time because of the considerable net volume increase (net porosity decrease) from the chemical interactions. Therefore, it appears likely, based on the geochemical and mass transport models, that the silo win perform as required for at least its 500-year design life, and possibly much longer

Finnish Research Programme on Nuclear Waste Management (KYT). Framework Programme for 2002-2005

International Nuclear Information System (INIS)

Rasilainen, K.

2002-12-01

The new Finnish research programme on nuclear waste management (KYT) will be conducted in 2002 - 2005. This framework programme describes the starting point, the basic aims and the organisation of the research programme. The starting point of the KYT programme is derived from the present state and future challenges of Finnish nuclear waste management. The research programme is funded mainly by the Ministry of Trade and Industry (KTM), the Radiation and Nuclear Safety Authority (STUK), Posiva Oy, Fortum Oyj, Teollisuuden Voima Oy (TVO), and the National Technology Agency (Tekes). As both regulators and implementors are involved, the research programme concentrates on neutral research topics that must be studied in any case. Methods and tools for experimental and theoretical studies fall in this category. State of the art -reviews on relevant topics also create national know-how. Topics that directly belong to licensing activities of nuclear waste management are excluded from the research programme. KYT carries out technical studies that increase national know-how in the area of nuclear waste management. The aim is to maintain and develop basic expertise needed in the operations derived from the national nuclear waste management plan. The studies have been divided into strategic studies and studies enhancing the long-term safety of spent nuclear fuel disposal. Strategic studies support the overall feasibility of Finnish nuclear waste management. These studies include basic options and overall safety principles related to nuclear fuel cycle and nuclear waste management. In addition, general cost estimates as well as general safety considerations related to transportations, low- and medium level wastes, and decommissioning are included in strategic studies. Studies supporting the long-term safety of spent fuel disposal include issues related to performance assessment methodology, release of radionuclides from the repository, behaviour of bedrock and groundwater

Applicability of living PSA in NPP modernization

International Nuclear Information System (INIS)

Himanen, R.

1999-01-01

Recently the utility Teollisuuden Voima Oy (TVO) has modernized the Olkiluoto 1 and 2 nuclear units and increased the net electric power by 18 per cent. Level 2 PSA was performed during the modernization project and the living level 1 PSA was used to support the design of the plant modifications. The plant specific living PSA model was a powerful tool when evaluating modernization alternatives. Successive support of safety management with the PSA model requires, that both the utility and the Regulatory Body understand capability and limitations of the model in details. TVO has prepared an internal procedure that presents in detail the practices and responsibilities concerning living PSA. The procedure is based on general guidelines and requirements on probabilistic safety analysis of nuclear power plants in Finland, released by the Regulatory Body. Living PSA requires that also the procedure for the use of living PSA is living. The recently published USNRC Regulatory Guides on PSA will be taken into account in the next version of the TVO PSA procedure. The PSA Peer Review Certification Process is one way to evaluate the quality of PSA in general, but also to detect the weaknesses of the PSA. However, the Certification Process cover only limited scope of PSA omitting e.g. all other external events except internal floods. This paper gives an overview on the scope of living PSA for Olkiluoto 1 and 2, and presents some examples on the real use of PSA concerning the modernization of the plant. Definition of quantitative dependability requirements for renovated systems is possible, but on the other hand, proving of these targets is in some cases extremely difficult, because of lacking dependability data. The problems are mainly concerned in systems with of programmable logic control. (au)

Evaluation of the dose assessment models for routine radioactive releases to the environment

International Nuclear Information System (INIS)

Rossi, J.

1998-05-01

The aim of the work was to evaluate the needs of development concerning the dose calculation models for routine releases and application of the models for exceptional release situations at the NPP plants operated by Imatran Voima Ltd. and Teollisuuden Voima Ltd. in Finland. First, the differences of the calculation models concerning input data, models themselves and output are considered. Subsequently some single features like importance of nuclides in exposure pathways due to change of the release composition, dose calculation for children and importance of time period of particle releases are considered. The existing dose calculation model used by the radiation safety authorities is aimed at a tool for checking the results from calculations of doses arising from routine releases by the power companies. Characteristics of an independent, foreign model and its suitability for safety authorities for dose calculations of releases in normal operation is also assessed. The needs of improvements in the existing calculation models and characteristics of a comprehensive model for safety authorities are discussed as well

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

International Nuclear Information System (INIS)

Dersten, Riitta; Gahmberg, Sini; Takala, Jenni

2008-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2008-07-01

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

Markkinointisuunnitelma, URHOtv Oy

OpenAIRE

Pesonen, Matti

2012-01-01

Opinnäytetyön tarkoituksena on paneutua suomalaiseen maksu-tv markkinaan ja kilpailutilanteeseen jonka jälkeen laatia yritykselle vuoden 2012 markkinointisuunnitelma. URHOtv Oy on suurin kotimaiseen urheiluun keskittyä maksu-tv kanava. URHOtv:llä on noin 300 000 asiakasta. Opinnäytetyön pohjana on käytetty Jobberin markkinointisuunnitelman tekoprosessin teoriaa hiukan mukailtuna URHOtv:n tarpeisiin. Markkinointisuunnitelman tueksi opinnäytetyössä tutkitaan URHOtv:n tilaa analyysie...

Prospects of power ramping and cycling supervision in Finnish power reactors

Energy Technology Data Exchange (ETDEWEB)

Antila, M; Kaikkonen, H T [Imatran Voima Oy, Helsinki (Finland); Mannola, E [Teollisuuden Voima Oy Industries Kraft Ab, Helsinki (Finland)

1983-06-01

Since 1977 2x440 MWe PWR and 2x660 MWe BWR nuclear power has been taken in operation in Finland, which until the middle of 1982 has given favourable fuel operating experiences from 10 reactor years. This paper describes the core supervision systems of the plants especially from the viewpoint of ramp surveillance and the potentials and needs to improve the supervision capability to meet the future needs in case more load follow operation is required. As a special feature for Imatran Voima is the demand of general basic understanding of the behaviour of Loviisa reactors' fuel in different operating conditions. A possibility to investigate the fuel seem to be power cycling tests in Loviisa reactors. (author)

Prospects of power ramping and cycling supervision in Finnish power reactors

International Nuclear Information System (INIS)

Antila, M.; Kaikkonen, H.T.; Mannola, E.

1983-01-01

Since 1977 2x440 MWe PWR and 2x660 MWe BWR nuclear power has been taken in operation in Finland, which until the middle of 1982 has given favourable fuel operating experiences from 10 reactor years. This paper describes the core supervision systems of the plants especially from the viewpoint of ramp surveillance and the potentials and needs to improve the supervision capability to meet the future needs in case more load follow operation is required. As a special feature for Imatran Voima is the demand of general basic understanding of the behaviour of Loviisa reactors' fuel in different operating conditions. A possibility to investigate the fuel seem to be power cycling tests in Loviisa reactors. (author)

Results of monitoring at Olkiluoto in 2010 - Environment

Energy Technology Data Exchange (ETDEWEB)

Haapanen, A. (ed.) [Haapanen Forest Consulting, Vanhakylae (Finland)

2011-10-15

This Working Report presents the main results of Posiva Oy's environmental monitoring programme on Olkiluoto Island in 2010. These summary reports have been published since 2005. The environmental monitoring system supervised by Posiva Oy produces input for biosphere modelling for long-term safety purposes as well as for monitoring the state of the environment during the construction (and later operation) of ONKALO underground rock characterization facility. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). Monitoring has been carried out for varying periods of time depending on the sector: some monitoring activities performed by TVO originate from the 1970s and the repository-related environmental monitoring of Olkiluoto from the early 2000s. The monitoring programme evolves according to experiences gained from the modelling work and increased understanding of the site. Augmentations in 2010 include one previously unmonitored private drilled well, and sampling of crop plants, aquatic macrophytes, and bottom fauna, as well as soil and water in order to obtain more data on site-specific concentration ratios. In addition to Olkiluoto Island, two so called reference lakes have been included in the sampling. Studies have been going on on one reference mire, as well. Bottom fauna studies of River Eurajoki exist from late 1970s, but have not been presented here before. Dust produced during construction of the third nuclear power unit (OL3), ONKALO and related infrastructure can be seen in the analysis results of needle litter. The construction works and road traffic have a raising effect on the noise levels of the immediate surroundings. The land-use continues to change, but the remaining natural environment resembles other coastal locations. The young age of the soils and the closeness of the sea are reflected in the soil properties. Mammalian fauna on the island is typical of coastal

Results of monitoring at Olkiluoto in 2010 - Environment

International Nuclear Information System (INIS)

Haapanen, A.

2011-10-01

This Working Report presents the main results of Posiva Oy's environmental monitoring programme on Olkiluoto Island in 2010. These summary reports have been published since 2005. The environmental monitoring system supervised by Posiva Oy produces input for biosphere modelling for long-term safety purposes as well as for monitoring the state of the environment during the construction (and later operation) of ONKALO underground rock characterization facility. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). Monitoring has been carried out for varying periods of time depending on the sector: some monitoring activities performed by TVO originate from the 1970s and the repository-related environmental monitoring of Olkiluoto from the early 2000s. The monitoring programme evolves according to experiences gained from the modelling work and increased understanding of the site. Augmentations in 2010 include one previously unmonitored private drilled well, and sampling of crop plants, aquatic macrophytes, and bottom fauna, as well as soil and water in order to obtain more data on site-specific concentration ratios. In addition to Olkiluoto Island, two so called reference lakes have been included in the sampling. Studies have been going on on one reference mire, as well. Bottom fauna studies of River Eurajoki exist from late 1970s, but have not been presented here before. Dust produced during construction of the third nuclear power unit (OL3), ONKALO and related infrastructure can be seen in the analysis results of needle litter. The construction works and road traffic have a raising effect on the noise levels of the immediate surroundings. The land-use continues to change, but the remaining natural environment resembles other coastal locations. The young age of the soils and the closeness of the sea are reflected in the soil properties. Mammalian fauna on the island is typical of coastal areas in

Instrumentation of the model in scaled 1:10 to prototype of the AquaBuOY wave energy converter

DEFF Research Database (Denmark)

Margheritini, Lucia; Frigaard, Peter

The objective of this report is to provide guidelines for the instrumentation of a model in scale 1:10 to prototype of the AquaBuOY wave energy converter. The model will be located in Nissum Bredning area: this is an important waterway already used by Aalborg University for real sea tests of wave...... energy converters....

RFID- TEKNIIKAN MAHDOLLISTAMAT TYÖAIKASÄÄSTÖT HUONEKALUTEOLLISUUDESSA : - CASE INCAP FURNITURE OY

OpenAIRE

Taskinen, Jarkko

2009-01-01

Opinnäytetyön tarkoituksena oli selvittää RFID- tekniikan eli radiotaajuudella toimivan etätunnistamisen mahdollistamia työaikasäästöjä huonekaluteollisuudessa. Toimeksiantaja oli Incap Furniture Oy. Incap Furniture Oy on yksi suurimmista mäntyhuonekalusopimusvalmistajista maailmassa. Pääasiakas on Ikea. Incap Furniture Oy on aloittanut projektin, jonka tarkoitus on tutkia RFID- tekniikan mahdollisuuksia ja hyötyjä tehtaiden toiminnassa. Opinnäytetyö oli osa projektia. Opinnäyt...

Digitaalisen markkinointiviestinnän mahdollisuudet : Case Kelloliike EA Lahti Oy

OpenAIRE

Harmaala, Tiina

2011-01-01

TIIVISTELMÄ Harmaala, Tiina. 2011. Digitaalisen markkinointiviestinnän mahdollisuudet – Case Kelloliike EA Lahti Oy. Opinnäytetyö. Kemi-Tornion ammattikorkeakoulu. Kaupan ja kulttuurin toimiala. Sivuja 62. Opinnäytetyön tavoitteena on Kelloliike EA Lahti Oy:n digitaalisen markkinointiviestinnän suunnittelu. Tutkimuksessa tarkastelen digitaalista markkinointiviestintää integroidun markkinointiviestinnän näkökulmasta. Tutkimuksen tarkoituksena on selvittää toimeksiantajalle sen markkino...

Ion-Molecule Reaction of Gas-Phase Chromium Oxyanions: CrxOyHz- + H2O

International Nuclear Information System (INIS)

Gianotto, Anita Kay; Hodges, Brittany DM; Benson, Michael Timothy; Harrington, Peter Boves; Appelhans, Anthony David; Olson, John Eric; Groenewold, Gary Steven

2003-01-01

Chromium oxyanions having the general formula CrxOyHz- play a key role in many industrial, environmental, and analytical processes, which motivated investigations of their intrinsic reactivity. Reactions with water are perhaps the most significant, and were studied by generating CrxOyHz- in the gas phase using a quadrupole ion trap secondary ion mass spectrometer. Of the ions in the Cr1OyHz envelope (y = 2, 3, 4; z = 0, 1), only CrO2- was observed to react with H2O, producing the hydrated CrO3H2- at a slow rate (∼0.07% of the ion-molecule collision constant at 310 K). CrO3-, CrO4-, and CrO4H- were unreactive. In contrast, Cr2O4-, Cr2O5-, and Cr2O5H2- displayed a considerable tendency to react with H2O. Cr2O4- underwent sequential reactions with H2O, initially producing Cr2O5H2- at a rate that was ∼7% efficient. Cr2O5H2- then reacted with a second H2O by addition to form Cr2O6H4- (1.8% efficient) and by OH abstraction to form Cr2O6H3- (0.6% efficient). The reactions of Cr2O5- were similar to those of Cr2O5H2-: Cr2O5- underwent addition to form Cr2O6H2- (3% efficient) and OH abstraction to form Cr2O6H- (<1% efficient). By comparison, Cr2O6- was unreactive with H2O, and in fact, no further H2O addition could be observed for any of the Cr2O6Hz- anions. Hartree-Fock ab initio calculations showed that reactive CrxOyHz- species underwent nucleophilic attack by the incoming H2O molecules, which produced an initially formed adduct in which the water O was bound to a Cr center. The experimental and computational studies suggested that Cr2OyHz- species that have bi- or tricoordinated Cr centers are susceptible to attack by H2O; however, when the metal becomes tetracoordinate, reactivity stops. For the Cr2OyHz- anions the lowest energy structures all contained rhombic Cr2O2 rings with pendant O atoms and/or OH groups. The initially formed [Cr2Oy- + H2O] adducts underwent H rearrangement to a gem O atom to produce stable dihydroxy structures. The calculations indicated that

Adidas Suomi Oy: Brändikuvan rakentaminen markkinoinnin keinoin

OpenAIRE

Leinonen, Miira

2015-01-01

Tämä opinnäytetyö tehtiin toimeksiantona Adidas Suomi Oy:lle syksyllä 2014. Opinnäytetyön tavoitteena oli selvittää muotialan mielipidevaikuttajien mielikuvat Adidaksesta ja sen merkittävimmistä kilpailijoista. Vertailtaviksi brändeiksi valittiin kuusi tärkeintä kilpailijaa, jotka ovat Converse, Karhu, New Balance, Nike, Puma ja Reebok. Opinnäytetyön toimeksiantaja Adidas Suomi Oy on osa kansainvälistä Adidas Group konsernia. Yritys on yksi maailman tunnetuimmista urheilumerkeistä ja toim...

SIEVIN JALKINE OY:N AVAINASIAKKAIDEN KÄSITYKSIÄ YRITYKSEN TOIMINNASTA

OpenAIRE

Haapakoski, Sanna

2014-01-01

Opinnäytetyön toimeksiantaja on Sievin Jalkine Oy. Yritys on Pohjoismaiden johtava turva- ja ammattijalkineiden valmistaja. Opinnäytetyön tavoitteena oli selvittää, kuinka tyytyväisiä avainasiakkaat ovat Sievin Jalkine Oy:n toimintaan ja miten toimintaa voidaan kehittää asiakkaiden hyväksi. Opinnäytetyössä selvitettiin, miten tyytyväisiä avainasiakkaat ovat tuotetarjontaan, palvelujen tarjontaan, markkinointiviestintään, asiakaspalveluun ja henkilöstöön. Opinnäytetyön tietoperustassa...

Development and testing of VTT approach to risk-informed in-service inspection methodology. Final report of SAFIR INTELI INPUT Project RI-ISI

International Nuclear Information System (INIS)

Cronvall, O.; Maennistoe, I.; Simola, K.

2007-04-01

This report summarises the results of a research project on risk-informed in-service inspection (RI-ISI) methodology conducted in the Finnish national nuclear energy research programme SAFIR (2003-2006). The purpose of this work was to increase the accuracy of risk estimates used in RI-ISI analyses of nuclear power plant (NPP) piping systems, and to quantitatively evaluate the effects of different piping inspection strategies on risk. Piping failure occurrences were sampled by using probabilistic fracture mechanics (PFM) analyses. The PFM results for crack growth were used to construct transition matrices for a discrete-time Markov process model, which in turn was applied to examine the effects of various inspection strategies on the failure probabilities and risks. The applicability of the developed quantitative risk matrix approach was examined as a pilot study performed to the Shut-down cooling piping system 321 in NPP unit OL1 of Teollisuuden Voima Oy (TVO). The analysed degradation mechanisms were stress corrosion cracking (SCC) and thermal fatigue induced cracking (in the mixing points). Here a new and rather straightforward approach was developed to model thermal fatigue induced cracking, which degradation mechanism is much more difficult to model than SCC. This study further demonstrated the usefulness of Markov analysis procedure development by VTT in RI-ISI applications. The most important results are the quantified comparisons of different inspections strategies. It was shown in this study that Markov models are useful for this purpose, when combined with PFM analyses. While the numerical results could benefit from further considerations of inspection reliability, this does not affect the feasibility of the method itself. The approach can be used to identify an optimal inspection strategy for achieving a balanced risk profile of piping segments. (orig.)

Commensurability oscillations in NdBa2Cu3Oy single crystals

Indian Academy of Sciences (India)

gated by angular dependent magnetization in very pure twinned and twin-free NdBa2 Cu3 Oy single ... The layered structure and the c-axis coherence length, ξc ≈ 4 ˚A, smaller than the lattice ... The high quality of both crystals is demonstrated by ... Commensurability oscillations in NdBa2Cu3Oy single crystals. 2. 3. 4. 5. 6.

Tilinpäätösanalyysi : case Ilmatuote Oy

OpenAIRE

Luotola, Elina

2014-01-01

Opinnäytetyön tavoitteena oli saada selville Ilmatuote Oy:n taloudellinen tilanne tarkastellen tilinpäätösinformaatiota vuosien 2009-2012 väliseltä ajanjaksolta. Ilmatuote Oy:n erikoisalana on jo yli 40 vuoden ajan ollut talotekniikkajärjestelmien asennus, urakointi- ja huoltotoiminta. Tarkoituksena oli tehdä tilinpäätösanalyysi yhtiön tilinpäätöksistä ja selvittää, millä tasolla yritys taloudellisesti on ja mihin suuntaan yrityksen taloudellinen tila on kehittynyt. Teoreettisessa osassa t...

Taloushallintoprosessien kehittäminen Iisalmen Putkiasennus Oy:ssä

OpenAIRE

Juntunen, Tiia

2015-01-01

Tämä opinnäytetyö käsittelee taloushallintoprosessien kehittämistä Iisalmen Putkiasennus Oy:ssä. Kehittämistyötä päädyttiin rajaamaan keskittyen myynti- ja ostolaskuprosessien kehittämiseen, koska niissä oli havaittu olevan eniten kehitettävää. Iisalmen Putkiasennus Oy on LVI-alalla työskentelevä perheyritys, joka on ollut toiminnassa jo yli 35 vuotta. Yritys sijaitsee Iisalmessa ja työllistää noin 50 henkilöä. Tässä opinnäytetyössä taloushallintoprosessien kehittäminen alkoi tilanteesta...

OpenOffice.org -toimisto-ohjelmiston soveltuvuus Sastamalan Tukipalvelu Oy:lle : selvitys

OpenAIRE

Ojanen, Olli-Veikko

2009-01-01

Tässä opinnäytetyössä selvitettiin OpenOffice.org toimisto-ohjelmiston soveltuvuutta Sastamalan Tukipalvelu Oy:lle, joka huolehtii osakkaittensa tieto-, talous- ja henkilöstöhallinnon palveluista. Sastamalan Tukipalvelu Oy:n osakkaina ovat Kiikoisten, Lavian ja Punkalaitumen kunnat, Sastamalan kaupunki, Sastamalan perusturvakuntayhtymä sekä Sastamalan koulutuskuntayhtymä. Selvityksen tavoitteena oli tuoda esille OpenOffice.org -toimisto-ohjelmistoon siirtymisen hyötyjä, joi...

Markkinointisuunnitelma sosiaalista mediaa hyödyntäen : Case Branda Oy

OpenAIRE

Hämeenniemi, Henna-Riika

2016-01-01

Tämän opinnäytetyön tarkoituksena oli tehdä markkinointisuunnitelma toimintaansa aloittelevalle yritykselle nimeltä Branda Oy. Branda Oy perusti vuoden 2015 alussa verkkokaupan, jonka kautta se myy naisten urheiluvaatteita suomalaisille kuluttajille. Opinnäytetyön tavoitteena oli antaa yritykselle välineet markkinoida itseään sosiaalisessa mediassa parhaalla mahdollisella tavalla. Työ toteutettiin kahdessa vaiheessa, josta ensimmäisessä toteutettiin itse markkinointisuunnitelma Branda O...

Jatkuvan koulutuksen antama tuki myyntityölle : Case: Systemair Oy

OpenAIRE

Mattila, Jeremias

2017-01-01

Opinnäytetyössä pyritään selvittämään, kokevatko myyjät koulutuksen edistävän heidän itse-varmuuttaan työtä kohden tai kokevatko he koulutuksen antaman tuen jollain muulla tavalla? Tulokset perustuvat laadulliseen Systemair Oy:n myyntihenkilöstön teemahaastatteluun. Kaikki tulokset ovat siis subjektiivisia Systemair Oy:n toimialaa ja sisäistä yrityskulttuuria kos-kien. Sovellettavuus muihin yrityksiin ja toimialoihin vaatii uuden tutkimuksen, mutta työ voi antaa osviittaa siihen, millaiset ja...

Situated Word Learning: Words of the Year (WsOY) and Social Studies Inquiry

Science.gov (United States)

Heafner, Tina L.; Triplett, Nicholas; Handler, Laura; Massey, Dixie

2018-01-01

Current events influence public interest and drive Internet word searches. For over a decade, linguists and dictionary publishers have analyzed big data from Internet word searches to designate "Words of the Year" (WsOY). In this study, we examine how WsOY can foster critical digital literacy and illuminate essential aspects of inquiry…

Site specific information in site selection

International Nuclear Information System (INIS)

Aeikaes, T.; Hautojaervi, A.

1998-01-01

The programme for the siting of a deep repository for final disposal of spent nuclear fuel was started already in 1983 and is carried out today by Posiva Oy which continues the work started by Teollisuuden Voima Oy. The programme aims at site selection by the end of the year 2000. The programme has progressed in successive interim stages with defined goals. After an early phase for site identification, five sites were selected in 1987 for preliminary site characterisation. Three of these were selected and judged to be best suited for the more detailed characterisation in 1992. An additional new site was included into the programme based on a separate feasibility study in the beginning of 1997. Since the year 1983 several safety assessments together with technical plans of the facility have been completed. When approaching the site selection the needs for more detailed consideration of the site specific properties in the safety assessment have been increased. The Finnish regulator STUK has published a proposal for general safety requirements for the final disposal of spent nuclear fuel in Finland. This set of requirements has been projected to be used in conjunction of the decision making by the end 2000. Based on the site evaluation all sites can provide a stable environment and there is evidence that the requirements for the longevity of the canister can be fulfilled at each site. In this manner the four candidate sites do not differ too much from each other. The main difference between the sites is in the salinity of the deep groundwater. The significance of differences in the salinity for the long-term safety cannot be defined yet. The differences may contribute to the discussion of the longevity of the bentonite buffer and also to the modelling of the groundwater flow and transport. The use of the geosphere as a transport barrier is basically culminated on the questions about sparse but fast flow routes and 'how bad channeling can be'. To answer these questions

RESEARCH ON THE EFFECTIVENESS OF ADVERTISING CHANNELS AT VIITAMAA CARAVAN OY

OpenAIRE

Huumonen, Anna-Sofia

2012-01-01

The topic of this study is the effectiveness of advertising channels.The topic was chosen by the request of Viitamaa Caravan Oy. The company wants this study to give more information about the effectiveness of different advertising channels in their own advertising. Viitamaa Caravan Oy also wanted some insight into the fact how much money in the budget should be reserved for each channel. The research problem can be defined as: Which of the advertising channels already used in Viitamaa Carav...

Afrikkaviikko Antell Catering Oy:ssä

OpenAIRE

Bask, Tiina

2011-01-01

Ruokapalvelualalla erilaisten teemaviikkojen toteuttaminen on keino tarjota asiakkaille ainutkertaisia elämyksiä ja tuoda vaihtelua normaaliin arkiruokailuun. Tämän opinnäytetyön tavoitteena oli suunnitella Afrikka-aiheinen teemaviikko Antell Catering Oy:n lounasravintoloihin. Afrikka-teeman mukaisesti suunniteltiin vakioruokaohjeet yhden viikon lounasvaihtoehdoiksi sekä markkinointimateriaali somistuksineen. Opinnäytetyö on toiminnallinen työ, jossa Afrikka-viikon lounasruokaohjeet mu...

Results of monitoring at Olkiluoto in 2012. Environment

International Nuclear Information System (INIS)

Haapanen, A.

2014-04-01

In 2003, Posiva Oy presented a programme for monitoring at Olkiluoto during construction and operation of ONKALO. In 2012 the monitoring programme was updated to concern the years 2012-2018. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). This Working Report presents the main results of Posiva's environmental monitoring programme on Olkiluoto Island in 2012. Results are presented under five topics: 1. Evolution of geosphere, 2. Biosphere modelling input data, 3. Interaction between surface environment and groundwater in bedrock, 4. Environmental impact and 5. Baseline of monitoring of radioactive releases. Concerning the evolution of geosphere, LIDAR-scannings were done in the Olkiluoto area in 2012. The acquired data can be used for elevation and other modelling purposes. The soil solution quality in 2012 was quite comparable to that in earlier years. Proximity of the sea and the young age of soils are seen in soil solution results. Biosphere modelling input data in 2012 included e.g. continuous tree litterfall and transpiration data, as well as updated game statistics and population estimates of fauna, a fishery survey from the River Eurajoki (2011) and basic monitoring data from Olkiluoto offshore properties. Interaction between surface environment and groundwater in bedrock includes e.g. weather and surface water monitoring data. Environmental impact analyses included e.g. monitoring of noise, air quality, effluent waters and private drilled wells. Noise monitoring in the vicinity of ONKALO showed that in the case of raised noise levels the sources are mainly the traffic on Olkiluodontie road, the air conditioning of ONKALO and occasional sources such as springtime bird sounds. Construction activities in the area were seen in increased amount of NO 3 -N in the bulk deposition, and Al and Fe accumulating on needle surfaces in areas close to the rock piling and crushing area. Scots

Results of monitoring at Olkiluoto in 2012. Environment

Energy Technology Data Exchange (ETDEWEB)

Haapanen, A. (ed.) [Haapanen Forest Consulting, Vanhakylae (Finland)

2014-04-15

In 2003, Posiva Oy presented a programme for monitoring at Olkiluoto during construction and operation of ONKALO. In 2012 the monitoring programme was updated to concern the years 2012-2018. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). This Working Report presents the main results of Posiva's environmental monitoring programme on Olkiluoto Island in 2012. Results are presented under five topics: 1. Evolution of geosphere, 2. Biosphere modelling input data, 3. Interaction between surface environment and groundwater in bedrock, 4. Environmental impact and 5. Baseline of monitoring of radioactive releases. Concerning the evolution of geosphere, LIDAR-scannings were done in the Olkiluoto area in 2012. The acquired data can be used for elevation and other modelling purposes. The soil solution quality in 2012 was quite comparable to that in earlier years. Proximity of the sea and the young age of soils are seen in soil solution results. Biosphere modelling input data in 2012 included e.g. continuous tree litterfall and transpiration data, as well as updated game statistics and population estimates of fauna, a fishery survey from the River Eurajoki (2011) and basic monitoring data from Olkiluoto offshore properties. Interaction between surface environment and groundwater in bedrock includes e.g. weather and surface water monitoring data. Environmental impact analyses included e.g. monitoring of noise, air quality, effluent waters and private drilled wells. Noise monitoring in the vicinity of ONKALO showed that in the case of raised noise levels the sources are mainly the traffic on Olkiluodontie road, the air conditioning of ONKALO and occasional sources such as springtime bird sounds. Construction activities in the area were seen in increased amount of NO{sub 3}-N in the bulk deposition, and Al and Fe accumulating on needle surfaces in areas close to the rock piling and crushing area

R20 Programme: Grout setting and strength development in ONKALO. Literature review, observations and experiments

International Nuclear Information System (INIS)

Karttunen, P.; Raivio, P.

2008-12-01

ONKALO is an underground rock characterisation facility planned to be a part of nuclear waste repository in future. ONKALO is located in Olkiluoto Finland. Posiva Oy owned by Teollisuuden Voima Oy and Fortum Power and Heat Oy is responsible for the repository, research, construction and use of the ONKALO and closing of the underground facility after use. During construction of ONKALO it has been observed that the setting and strength of grouting materials have not sporadically developed as expected (in ONKALO). The phenomenon has been observed for the first time in the year 2005. The observations examined in this report are made in the grouting field tests and in ordinary grouting during the year 2007. The phenomenon has been observed with low pH and standard grouts and bolt grouting mortars. The reasons for this phenomenon are studied based on literature review, observations and tests in the field and laboratory. The effect of reactions between groundwater and grout, the effect of the raw materials as well as curing conditions, temperature and pressure are studied. There are several potential factors that can cause observed phenomenon. Some factors are more probable than others. Laboratory experiments for the samples of poor strength development were done. These samples were taken from the grouting holes or packers in which the strength of the grout was not developed as expected. The results of these experiments were compared to the results gained from the samples cast from the same grout batches and cured in the tunnel conditions. The purpose was to find out the factor causing slow strength development of the grouted mixes. One single reason, which can slow the setting of the grouts in ONKALO is the low temperature in the rock, but the temperature cannot cause the phenomenon alone. Locally groundwater contains compounds that can create chemically aggressive environment for (the Portland) cement based grouts. The groundwater chemistry in ONKALO has not been proved

B2B-uutiskirjeen visuaalisen ilmeen kehitys — Case Tamtron Solutions Oy

OpenAIRE

Salo, Sari

2014-01-01

Opinnäytetyön tarkoituksena oli kehittää Tamtron Solutions Oy:n uutiskirjeelle uusi visuaalinen ilme. Yrityksen lähettämästä uutiskirjeestä yritysasiakkaille puhutaan B2B-uutiskirjeenä. Tamtron Solutions Oy halusi B2B-uutiskirjeen avulla tehostaa markkinointia, kasvattaa myyntiä ja luoda uusia asiakassuhteita. Yritys halusi toteuttaa markkinointikampanjan B2B-uutiskirjeen muodossa rakennusalan yrityksille. Yritys valitsi kampanjan kohderyhmäksi rakennusalan yritykset, koska lakimuutos rakennu...

Ilmanpuhdistimen tuotekehitys : case: Mecastep Oy

OpenAIRE

Arasola, Aku

2015-01-01

Tämän opinnäytetyön tarkoituksena oli olla osana tuotekehitysprojektia, joka koskee Mecastep Oy:n ilmanpuhdistin innovaatiota. Kehitystä vaativia kohtia olivat komponenttien valinta ja mekaniikan saaminen toimivaksi. Edelläkävijän innovaatiosta tekee se, että samanlaista tuotetta ei ole vielä olemassa. Mekaniikan mallintaminen tapahtui 3D-ohjelmalla nimeltä KeyCreator. Ilmanpuhdistin tullaan sijoittamaan keittiön jätekaappiin. Puhdistuksella tässä tapauksessa tarkoitetaan epäpuhtaan ilman...

The effect of CO2 on the plasma remediation of NxOy

Science.gov (United States)

Gentile, Ann C.; Kushner, Mark J.

1996-04-01

Plasma remediation is being investigated for the removal of oxides of nitrogen (NxOy) from atmospheric pressure gas streams. In previous works we have investigated the plasma remediation of NxOy from N2/O2/H2O mixtures using repetitively pulsed dielectric barrier discharges. As combustion effluents contain large percentages of CO2, in this paper we discuss the consequences of CO2 in the gas mixture on the efficiency of remediation and on the end products. We find that there is a small increase in the efficiency of total NxOy remediation (molecules/eV) with increasing CO2 fraction, however the efficiency of NO remediation alone generally decreases with increasing CO2. This differential is more pronounced at low energy deposition per pulse. More remediation occurs through the reduction channel with increasing CO2 while less NO2 and HNOx are produced through the oxidation channel. CO is produced by electron impact of CO2 though negligible amounts of cyanides are generated.

Rock mechanical, thermomechanical and hydraulic behaviour of the near field for spent nuclear fuel

International Nuclear Information System (INIS)

Johansson, E.; Hakala, M.; Lorig, L.J.

1991-10-01

Teollisuuden Voima Oy (TVO) is investigating the feasibility of disposing high level nuclear waste in crystalline rock at depths of 400 to 600 meters below the ground surface. Two explicit distinct element computer codes UDEC and 3DEC were used to simulate the mechanical response associated with excavation and the thermomechanical response associated with waste emplacement. Model input data are mostly based on preliminary design of the repository and on field data from on-going site investigations in Finland. The results showed that the overall stability of the repository near-field appears to be good during the studied time period 0 - 900 years. The maximum displacements after excavation are about 2 mm on the walls of the disposal tunnel. Joint openings are only a few micrometers. The hydraulic conductivity increases by 4 to 6 times within the zone of 0,3 m around the tunnel and emplacement hole, and farther away the average increase in conductivity is 1,2 to 1,7 times. After 60 years the heating increases the stresses in the vicinity of the excavated rooms, and closes the joints decreasing the hydraulic conductivity by 93 - 99 % when assuming 10 μm in-situ hydraulic aperture. However, when assuming 50 μm in-situ hydraulic aperture the hydraulic conductivity increases 10 - 40 % because the change in dynamic viscosity of water has a larger effect than the joint aperture change. After 900 years in the cooling stage the stresses and displacements come back almost to the same level as after the excavation. Some permanent displacements remain in the joints due to the shearing. The hydraulic conductivity at 900 years is 10 - 70 % of the conductivity after the excavation. The comparisons between the 2-D and 3-D results show that the two-dimensional modeling, if sufficient cross-sections have been analyzed, is enough to describe mechanical behaviour of the near-field, whereas the three-dimensional modeling is needed in some cases to assess the thermomechanical behaviour

Superconducting transition temperature in the Y(1-x)M(x)Ba2Cu3O(y) system

Science.gov (United States)

Suzuki, Takeyuki; Yamazaki, Tsutomu; Sekine, Ryuuta; Koukitsu, Akinori; Seki, Hisashi

1989-04-01

Experimental results are presented for the inclusion of compositional additives, M, to the sintered high-temperature superconductor Y(1-x)M(x)Ba2Cu3O(y); M can be the oxides of Mg, Ce, Gd, Yb, Ti, Zr, V, Nb, Ta, Cr, Mo, W, Mn, Fe, Co, Ni, Zn, B, Al, Ga, In, Si, Ge, Sn, Pb, Sb, Bi, and Te, as well as Li, Na, K, Ca, Sr, and La carbonates. Temperature dependence of the electrical resistance was measured down to about 80 K. Attention is given to the influence of ionic radius and the valence of the M species.

Entering market in St. Petersburg, Russia– Kärävä Oy

OpenAIRE

Tsirkunov, Aleksandr

2013-01-01

The company commissioning this thesis is Kärävä Oy. This company was founded in 1988 and since then they focus on producing timber of different quality and size. Their clients are wholesalers of timber and wood products, along with sauna manufacturers. Produced products are used for interior finishing in commercial and public areas. More-over, Kärävä Oy is also producing interior materials for saunas. Main purpose for this thesis is to analyse if entering Russian market will be profitable...

Drillings at Kivetty in Konginkangas

International Nuclear Information System (INIS)

Hinkkanen, H.; Oehberg, A.

1990-05-01

According to Government's decision in principle Teollisuuden Voima Oy is obliged to make bedrock investigations for the final disposal of the spent fuel produced by its power plant in Olkiluoto. Areas in Kuhmo, Hyrynsalmi, Sievi, Konginkangas and Olkiluoto were selected for the preliminary site investigations to be carried out during years 1987-1992. In Kivetty, Konginkangas the investigation program was started in spring 1988. During years 1988-1989 a deep borehole (1019 m) and 4 about 500 m deep additional boreholes were core drilled in the area. The structure of the holes makes it possible to carry out many investigations in the holes. Various parameters were measured from the flushing water during the drilling. Corelogging included collecting detailed data of fractures and determining the weathering degree and petrographical properties. Rock mechanical properties, uniaxial compressive strength, Young's modulus and Poisson's ratio were measured from core samples. The flushing water needed in the drillings was pumped from 100 m deep borehole wells drilled with down-the-hole method in the vicinity of the borehole. The water was labeled with 2 tracers before use. 30 vertical holes were core drilled down to the depth of 10 m in bedrock with a light drilling unit. Drilling was carried out in order to determine the thickness of the overburden to investigate the geophysical anomaly sources and to support geological mapping in areas covered with overburden. Groundwater hydraulics is one of the main subjects during the preliminary site investigation phase. For that reason 7 multilevel piezometers were installed on the site to monitore hydraulic head in 3 levels in the uppermost part of bedrock. The work consisted of borehole drillings to the depth of 100 m, geophysical borehole loggings and installation of piezometers. In addition about 65 shotholes were drilled for VSP-, tubewave and seismic measurements

Drillings at Syyry in Sievi

International Nuclear Information System (INIS)

Hinkkanen, H.; Oehberg, A.

1990-10-01

According to Government's decision in principle Teollisuuden Voima Oy is obliged to make bedrock investigations for the final disposal of the spent fuel produced by its power plant in Olkiluoto. Areas in Kuhmo, Hyrynsalmi, Sievi, Konginkangas and Olkiluoto were selected for the preliminary site investigations to be carried out during years 1987-1992. In Syyry, Sievi the investigation program was started in spring 1988. During years 1988-1989 a deep borehole (1022 m) and 4 about 500-700 m deep additional boreholes were core drilled in the area. The structure of the holes makes it possible to carry out many investigations in the holes. Various parameters were measured from the flushing water during the drilling. Corelogging included collecting detailed data of fractures and determining the weathering degree and petrographical properties. Rock mechanical properties, uniaxial compressive strength, Young's modulus and Poisson's ratio were measured from core samples. The flushing water needed in the drillings was pumped from 100 m deep borehole wells drilled with down-the-hole method in the vicinity of the borehole. The water was labeled with 2 tracers before use. 35 vertical holes were core drilled down to the depth of 10-20 m in bedrock with a light drilling unit. Drilling was carried out in order to determine the thickness of the overburden, to investigate the geophysical anomaly sources and to support geological mapping in areas covered with overburden. Groundwater hydraulics is one of the main subjects during the preliminary site investigation phase. For that reason 7 multilevel piezometers were installed on the site to monitore hydraulic head in 3 levels in the uppermost part of bedrock. The work consisted of borehole drillings to the depth of 100 m, geophysical borehole loggings and installation of piezometers. In addition about 85 shotholes were drilled for VSP-, tubewave and seismic measurements

Drilling of deep boreholes and associated geological investigations. Final disposal of spent fuel

International Nuclear Information System (INIS)

Anttila, P.

1983-12-01

Teollisuuden Voima Oy (Industrial Power Company Ltd.) will take precautions for the final disposal of spent fuel in the Finnish bedrock. The first stage of the site selection studies includes drilling of a deep borehole down to approximately 1000 metres in the winter of 1984. The choice of drilling method and equipment depends on the geological circumstances and the target of the investigation. The most common drilling methods used with the investigations of nuclear waste disposal are diamond core drilling and percussion drilling. The Precambrian bedrock outcropping in Finland exists also in Sweden and Canada, where deep boreholes have been done down to more than 1000 metres using diamond core drilling. This method can be also used in Finland and equipment for the drilling are available. One of the main targets of the investigation is to clarify the true strike and dip of fractures and other discontinuities. The methods used abroad are taking of oriented cores, borehole television survey and geophysical measurements. TV-survey and geophysical methods seem to be most favourable in deep boreholes. Also the accurate position (inclination, bearing) of the borehole is essential to know and many techniques are used for measuring of it. Investigations performed on the core samples include core logging and laboratory tests. For the core logging there is no uniform practice concerning the nuclear waste investigations. Different counries use their own classifications. All of these, however, are based on the petrography and fracture properties of the rock samples. Laboratory tests (petrographical and rock mechanical tests) are generally performed according to the recommendations of international standards. The large volumes of data obtained during investigations require computer techniques which allow more comprehensive collection, storage and processing of data. This kind of systems are already used in Sweden and Canada, for instance, and they could be utilize in Finland

Equilibrium Structures and Absorption Spectra for SixOy Molecular Clusters using Density Functional Theory

Science.gov (United States)

2017-05-05

Naval Research Laboratory Washington, DC 20375-5320 NRL/MR/6390--17-9724 Equilibrium Structures and Absorption Spectra for SixOy Molecular Clusters...TELEPHONE NUMBER (include area code) b. ABSTRACT c. THIS PAGE 18. NUMBER OF PAGES 17. LIMITATION OF ABSTRACT Equilibrium Structures and Absorption...and electronic excited-state absorption spectra for eqilibrium structures of SixOy molecular clusters using density function theory (DFT) and time

Online video marketing plan for a product launch : Case company: Altal Oy

OpenAIRE

Ngo, Quan

2015-01-01

This bachelor’s thesis aims to create a detailed guideline for using marketing videos in various online channels for Altal Oy. The commissioning company, Altal Oy is a Finn-ish start-up founded by three employees in 2014. It operates in the smart home tech-nology sector. The thesis topic is based on the current needs of the company to pro-mote for the launch of its brand new products in the Finnish market. A real project of making a promotion video is conducted and reported in parallel with t...

Markkinointiviestintäsuunnitelma: Charlotta-Production Oy

OpenAIRE

Wikman, Carita

2015-01-01

Tämän opinnäytetyön tarkoituksena on luoda markkinointiviestintäsuunnitelma hollolalaiselle askartelutukulle ja vähittäismyymälälle Charlotta-Production Oy:lle. Suunnitelman tavoitteena on aktivoida etenkin vanhoja yritysasiakkaita, mutta myös yksityisasiakkaita, sekä tavoittaa uusia potentiaalisia asiakkaita erityisesti digitaalisiin markkinointikeinoihin painostaen. Opinnäytetyö jakaantuu teoreettiseen ja empiiriseen osuuteen. Teoriaosuudessa käsitellään markkinointiviestintää kokonaisu...

Viestintäsuunnitelma : Lippupalvelu Oy

OpenAIRE

Olin, Noora

2015-01-01

Tämän opinnäytetyön tavoitteena oli rakentaa viestintäsuunnitelma Lippupalvelu Oy:lle. Viestintäsuunnitelma alkaa ajallisesti siitä hetkestä, kun asiakas ostaa lipun verkkokaupasta, ja päättyy tapahtuman jälkimarkkinointiin. Tähän ajanjaksoon liittyvä uusi viestintäprosessi otettiin käyttöön vuoden 2015 aikana, mutta sitä haluttiin vielä kehittää eteenpäin. Tutkimuksessa selvitettiin tapahtumajärjestäjien mielipiteitä ja kehitysehdotuksia viestintäprosessista. Tavoitteena oli aikaansaada tark...

Small scale power production

Energy Technology Data Exchange (ETDEWEB)

Muoniovaara, M [IVO International Ltd, Vantaa (Finland)

1997-12-31

IVO International is a major constructor of biomass power plants in Finland and abroad. As a subsidiary of Imatran Voima Oy, the largest power utility in Finland, it has designed and constructed ten power plants owned by IVO Group or others capable of burning biomasses. Sizes of the plants vary from the world`s largest condensing peat-fired power plant of 155 MWe to a 6 MWe combined heat and power producing unit. This article describes the biomass power plants designed and constructed by IVO Group 3 refs.

Loviisa nuclear power plant analyzer

International Nuclear Information System (INIS)

Porkholm, K.; Nurmilaukas, P.; Tiihonen, O.; Haenninen, M.; Puska, E.

1992-12-01

The APROS Simulation Environment has been developed since 1986 by Imatran Voima Oy (IVO) and the Technical Research Centre of Finland (VTT). It provides tools, solution algorithms and process components for use in different simulation systems for design, analysis and training purposes. One of its main nuclear applications is the Loviisa Nuclear Power Plant Analyzer (LPA). The Loviisa Plant Analyzer includes all the important plant components both in the primary and in the secondary circuits. In addition, all the main control systems, the protection system and the high voltage electrical systems are included. (orig.)

Investigation of the submodels for combustion; Polton osamallien kaeytettaevyys

Energy Technology Data Exchange (ETDEWEB)

Kjaeldman, L.; Huttunen, M.; Kyttaelae, J. [VTT Energy, Espoo (Finland)

1997-10-01

The capability for numerical analysis of flow, combustion and heat transfer in furnaces has been developed by improving the knowledge of the sensitivity of computed results on submodels recently implemented to the computational environment Ardemus owned by VTT Energy and Imatran Voima Oy. The submodels studied include models for combustion of gaseous (pyrolysed) fuel and for nitric oxide. The cases investigated included a gas flame and pulverized coal and peat combustion in single burner furnaces. The effect of grid refinement on the results was investigated for a corner fired power station furnace. (orig.)

Small scale power production

Energy Technology Data Exchange (ETDEWEB)

Muoniovaara, M. [IVO International Ltd, Vantaa (Finland)

1996-12-31

IVO International is a major constructor of biomass power plants in Finland and abroad. As a subsidiary of Imatran Voima Oy, the largest power utility in Finland, it has designed and constructed ten power plants owned by IVO Group or others capable of burning biomasses. Sizes of the plants vary from the world`s largest condensing peat-fired power plant of 155 MWe to a 6 MWe combined heat and power producing unit. This article describes the biomass power plants designed and constructed by IVO Group 3 refs.

Mean sea level and change in the hydrological regime off Loviisa power plant around the year 2050

International Nuclear Information System (INIS)

Maelkki, P.; Voipio, A.

1985-03-01

On the request of Imatran Voima Oy, the Institute of Marine Research has made an estimate on the future sea level off Loviisa Power Plant. The estimate is based on observationsof mean sea level in the Gulf of Finland. The stations used are Helsinki (observations since 1904) and Hamina (observations since 1928). A litterature review was made in order to estimate impact of climate change on environmental conditions. The results presented are mainly based on various estimates of meterorological Global Circulation Models (GCM). Their usefulness in the connection is briefly discussed

Synthesis and Microstructure Properties of (Bi,Pb2Sr2Ca1Cu2Oy Ceramic Superconductor

Directory of Open Access Journals (Sweden)

nurmalita .

2015-11-01

Full Text Available Properties of (Bi, Pb2Sr2Ca1Cu2Oy ceramic superconductors were prepared by the melt textured growth methods in order to investigate the effects of the slow cooling time on the microstructur.  Phase analyses of the samples by X-ray diffraction (XRD has been carried out to assess the effects of the slow cooling time. From XRD analyses, the addition to the sample of  the slow cooling time degrades formation of the high-Tc Bi-2212 phase. The possible reasons for the observed degradation in the microstructure properties due to the slow cooling time addition were discussed.

Salon Patarouva Oy : kertomus lounasravintolan perustamisesta

OpenAIRE

Aronen, Miina

2011-01-01

Salon Patarouva Oy on Salossa Meriniityn teollisuusalueella toimiva lounasravintola. Yrityksen perustaminen ja toiminnan alkuunsaattaminen oli lähtökohta tämän toiminnallisen opinnäytetyön tekemiseen. Omat lähtökohdat yrittäjäksi ryhtymiseen olivat vahva ammattitaito ja kokemus suurkeittiöympäristöistä. Vuokrasimme toimitilat ja ostimme uudet laitteet. Yrityslainan saimme Finnverasta ja pankista. Lainopillisia ja muita neuvoja saimme Yrityssalosta. Salon Pararouvan liikeidea on palvella...

Turvajalkineiden vaikutus jalkaterveyteen Suur-Savon Sähkötyö Oy:ssä

OpenAIRE

Pulkkinen, Riikka; Tossavainen, Inka; Ryynänen, Elina

2014-01-01

Opinnäytetyön tarkoituksena oli selvittää, millaisia vaikutuksia turvajalkineilla voi olla jalkaterveyteen, minkälaisia jalkaongelmia turvajalkineiden käyttö voi aiheuttaa, voivatko työntekijät itse vaikuttaa turvajalkineiden hankintaan ja millainen on turvajalkineiden hankintaprosessi Suur-Savon Sähkötyö Oy:ssä. Opinnäytetyömme toimeksiantaja oli Suur-Savon Sähkötyö Oy. Tutkimusmenetelmänä käytettiin pääasiassa kvantitatiivista tutkimusta ja aineisto kerättiin puolistrukturoidulla kysely...

5S-MENETELMÄN KÄYTTÖÖNOTTO SERVICEPOINTILLA

OpenAIRE

Ovaskainen, Tatu-Pekka

2014-01-01

Opinnäytetyö on tehty Servicepoint Kuopio Oy:n toimeksiannosta. Servicepoint Kuopio on teollisuuden kunnossapitoon automaatio- ja sähköistysprojekteihin sekä robottisovelluksiin erikoistunut yritys. Yrityksen kahden toimipisteen yhdistyminen lisäsi toimipisteellä henkilöstön ja työkalujen määrää. Yrityksessä toteutetaan sovelletusti Lean-ajattelumallia. Yksi Leanin työkaluista on 5S, joka haluttiin ottaa käyttöön yrityksessä. Opinnäytetyön tavoitteena oli ottaa käyttöön 5S-menetelmä Servi...

Pienpanimon tuotekehitys : Mathildedalin Panimo Oy

OpenAIRE

Lilja, Henri

2014-01-01

Tässä opinnäytetyössä selvitettiin, minkälaisia asioita Mathildedalin Panimo Oy:n tulee tuotekehityksessään ottaa huomioon. Opinnäytetyön kirjallisuusosa käsittelee oluen määritelmää ja historiaa, valmistusprosessia pienpanimossa, sekä lainsäädäntöä ja myyntikanavia. Työn teoreettisena pohjana on käytetty Business Model Canvas -nimistä liiketoiminnan suunnittelutyökalua, joka toimii tuotekehityksen tukena. Verotus, tiukka lainsäädäntö ja kiristyvä kilpailu ovat pienpanimon toiminnan suuri...

Hoivia Oy:n ruokapalvelujen asiakaskunnan laajentaminen

OpenAIRE

Sipilä, Satu

2014-01-01

Tämä opinnäytetyö syntyi Hoivia Oy:n tarpeesta markkinoida omia ruokapalveluitaan talon ulkopuolisille ja samalla kehittää lounasravintola Ludvigin palveluliiketoimintaa. Keskusteluissa toimitusjohtajan kanssa päätettiin selvityksen kohderyhmäksi ottaa kokonaisia palveluyksiköitä eikä yksittäisiä henkilöitä. Markkinatutkimukseen haluttiin mukaan kehitysvammaisten asuntoloita, päivätoimintayksiköitä, yksityisiä vanhainkoteja ja palvelutaloja sekä päiväkoteja. Ludvigissa on resursseja valmistaa...

Balanced scorecard:Case ConnectedDay Oy

OpenAIRE

Alatalo, Teija

2009-01-01

Markkinoiden kasvaminen ja jatkuvasti koveneva kilpailu ovat luoneet yrityksille paineita tulevaisuuden kilpailukyvyn ylläpitämiselle, mikä edellyttää yrityksiltä uudenlaisia työkaluja liiketoiminnan seuraamiselle. Tämän opinnäytetyön aiheena oli soveltaa yritysmaailmassa yleisesti käytettyä seurantajärjestelmää, balanced scorecardia case –yrityksenä käytetyn ConnectedDay Oy:n liiketoimintaan. Robert Kaplan ja David Norton suunnittelivat 1990 –luvun alussa balanced scorecard -mallin eli tasap...

Drillings at Veitsivaara in Hyrynsalmi

International Nuclear Information System (INIS)

Hinkkanen, H.; Oehberg, A.

1990-04-01

According to Governmen's decision in principle Teollisuuden Voima Oy is obliged to make bedrock investigations for the final disposal of the spent fuel produced by its power plant in Olkiluoto. Areas in Kuhmo, Hyrynsalmi, Sievi, Konginkangas and Olkiluoto were selected for the preliminary site investigations to be carried out during years 1987-1992. In Veitsivaara, Hyrynsalmi the investigation program was started in April 1987. During years 1987-1988 a deep borehole (1002 m) and 4 and 500 m deep additional boreholes were core drilled in the area. Various parameters were measured from the flushing water during the drilling. Corelogging included collecting detailed data of fractures and determining the weathering degree and petrographical properties. Rock mechanical properties, uniaxial compressive strength, Young's modulus and Poisso's ratio were measured from core samples. The flushing water needed in the drillings was pumped from 100 m deep borehole wells drilled with down-the-hole method in the vicinity of the borehole. The water was labeled with 2 tracers before use. About 75 m deep hole was percussion drilled near the borehole KR1. The spreading of the flushing water in the upper part of bedrock and the quality off the ground of the groundwater were studied by taking watersamples from the hole. 30 vertical holes were core drilled down to the depth of 10 m in bedrock with a light drilling unit. Drilling was carried out in order to determine the thickness of the overburden, to investigate the geophysical anomaly sources and to support geological mapping in areas covered with overburden. Groundwater hydraulics is one of the main subjects during the preliminary site investigation phase. For that reason 7 multilevel piezometers were installed on the site to monitore hydraulic head in 3 levels in the uppermost part of bedrock. The work consisted of borehole drillings to the depth of 100 m, geophysical borehole loggings and installation of piezometers. In addition

Ohjelmapalveluiden tuotekortit Lahti Travel Oy:n kokouspalveluhakemistoon

OpenAIRE

Lahti, Kirsi; Lehtola, Senni

2010-01-01

Tämä toiminnallinen opinnäytetyö käsittelee matkailun ohjelmapalveluiden markkinointia ja tuotteistamista. Opinnäytetyön tuloksena syntyi ohjelmapalveluiden tuotekortteja toimeksiantajan uudistetuille Internet-sivuille. Toimeksiantajana on Lahti Travel Oy, ja työn produkti eli tuotekortit ovat osa toimeksiantajan Internet-sivujen uudistusta. Tuotekortit sijoittuvat Internet-sivuilla kokouspalveluiden palveluhakemistoon ja siellä tarkemmin oheispalveluiden osioon. Työssä on toiminnallisen työn...

Internetmarkkinoinnin mahdollisuudet : case NaNi Group Oy

OpenAIRE

Arvonen, Johanna

2014-01-01

Tämän opinnäytetyön tarkoituksena oli tutkia internetmarkkinoinnin mahdollisuuksia kolmessa internetpalvelussa pienten koirien vaatteita valmistavalle NaNi Group Oy:lle. Opinnäytetyö toimii hyödyllisenä oppaana toimeksiantajan internetmarkkinoinnin suunnittelussa. Lisäksi opinnäytetyössä arvioidaan toimeksiantajan Facebookissa ja YouTubessa suorittamaa mainontaa. Kampanjoiden tulosten arviointi ja vertailu antavat suuntaa sille, miten kampanjoita kannattaa toteuttaa tulevaisuudessa. Opinn...

Customer Orientation vs. Customer Orientation Perception : Case J & J Lakkapää Oy Tornio

OpenAIRE

Angeria, Heli

2011-01-01

Heli, Angeria 2011. Customer Orientation vs. Customer Orientation Perception. Case: J & J Lakkapää Oy Tornio. Kemi-Tornio University of Applied Sciences. Business and Culture. Pages 51. Appendices 5. The objective of this thesis is to study customer orientation with the help of a widely adapted Selling-Orientation-Customer Orientation (SOCO) scale, in order to find out what is the extent to which J & J Lakkapää Oy Tornio and its consumer customers agree or disagree about the company’s cus...

Laadun parantaminen jalkinetuotannossa : case: Reima Oy

OpenAIRE

Huurre, Helena

2014-01-01

Tämä opinnäytetyö käsittelee laatua ja laadun kehittämisen työkaluja yrityksissä. Opinnäytetyön tarkoituksena oli tehdä kotimaiselle lastenvaatevalmistajalle, Reima Oy:lle, laatukäsikirja jalkinetuotantoa varten sekä laatukäsikirjaan sisältyvä laatuvaatimustaulukko, mistä jalkineiden laadulliset vaatimukset on löydettävissä. Laatukäsikirjan tavoitteena oli yhdistää Reiman jalkineen tuotekehitysprosessin kuvaus ja yleiset jalkinevaatimukset koko tuotantoprosessin ajalta yhtenäiseksi dokume...

Determination of interstitial oxygen atom position in U2N3+xOy by near edge structure study

Science.gov (United States)

Jiang, A. K.; Zhao, Y. W.; Long, Z.; Hu, Y.; Wang, X. F.; Yang, R. L.; Bao, H. L.; Zeng, R. G.; Liu, K. Z.

2018-06-01

The determination of interstitial oxygen atom site in U2N3+xOy film could facilitate the understanding of the oxidation mechanism of α-U2N3 and the effect of U2N3+xOy on anti-oxidation. By comparing the similarities and variances between N K edge and O K edge electron energy loss spectra (EELS) for oxidized α-U2N3 and UO2, the present work looks at the local structure of nitrogen and oxygen atoms in U2N3+xOy film, identifying the most possible position of interstitial O atom.

Sosiaalisen median markkinoinnin vuosikello Weecos Oy:lle

OpenAIRE

Heinämäki, Lotta; Huuskonen, Leena

2015-01-01

Opinnäytetyön tarkoitus oli luoda kokonaisvaltainen ja selkeä suunnitelma Weecos Oy:n markkinointitoimenpiteille valituissa sosiaalisen median kanavissa. Weecos on vuonna 2012 perustettu ekologisia yrityksiä yhteen keräävä verkkokauppa-alusta. Pienestä koostaan johtuen se ei ole pystynyt toteuttamaan sosiaalisen median markkinointia toivomallaan tavalla ja markkinoinnin suunnittelu ja toteutus on ollut epäsäännöllistä. Markkinointisuunnitelman tavoitteena oli helpottaa yrityksen markkinoi...

Tuotannon layoutin suunnittelu Flinkenberg OY:lle

OpenAIRE

Puotiniemi, Olli

2013-01-01

Opinnäytetyön aiheena on layoutsuunnittelu Flinkenberg Oy:lle. Yrityksen on tarkoitus tulevaisuudessa hankkia uusi työstökone nykyisiin toimitiloihin. Siitä seurasi tarve saada uusi layoutsuunnitelma tuotantohallista vanhan tilalle. Myös vanha layout kaipasi päivitystä. Opinnäytetyössä on pyritty soveltamaan jo olemassa olevaa teoriaa ja käytäntöä layoutsuunnittelussa. Teoriaa oli tarjolla paljon, ja olikin tärkeää osata perehtyä vain olennaiseen. Siihen tässäkin tutkimuksessa on pyritty....

M Road Oy: Arvo-ja laatudokumentti

OpenAIRE

Röynä, Mira

2017-01-01

Opinnäytetyön aiheena on yrityksen arvot ja laatutekijät. Opinnäytetyön tutkimuksellinen näkökulma syntyy konstruktiivisesta tutkimuksesta sekä kyselystä ja tiimityöskentelystä. Työssä tutustutaan tarkasti arvojen ja laatutekijöiden teoriaan, joiden pohjalta analysoidaan työntekijäkyselyn ja tiimityöskentelyn tuloksia. Työn tavoitteena on saada yhdistettyä franchaising-yritys M Road Oy:n arvot koko M Room –ketjun arvoja vastaavaksi, sekä parantaa yrityksen tuottamaa laatua. Toimeksiantaja...

Hydrogeological modelling for assessment of radionuclide release scenarios for the repository system 2012

Energy Technology Data Exchange (ETDEWEB)

Hartley, L.; Hoek, J.; Swan, D.; Appleyard, P.; Baxter, S.; Roberts, D.; Simpson, T. [AMEC (United Kingdom)

2013-07-15

Posiva Oy is responsible for implementing the programme for geological disposal of spent nuclear fuel produced by its owners Teollisuuden Voima Oyj (TVO) and Fortum Power and Heat Oy in Finland. Olkiluoto in Eurajoki has been selected as the primary site for the repository, subject to further detailed investigation which is currently focused on the construction of an underground rock characterisation and research facility (the ONKALO). An essential part of the assessment of long-term safety of a repository is the analysis of groundwater flow since it is the only means of transport of radionuclides to the biosphere (besides human intrusion). The analysis of long-term safety for a KBS-3 concept requires as input a description of details of the groundwater flow around and through components of the engineered barrier system as well as details of the groundwater pathway to the biosphere during the current temperate climate period, as well as indications of behaviour under future climate periods such as glacial conditions. This report describes the groundwater flow modelling study performed to provide some of the necessary inputs required by Safety Assessment (i.e. radionuclide transport analysis). Underlying this study is the understanding of the site developed during the site investigations as summarised in the site descriptive model (SDM), and in particular the description of Olkiluoto Hydrogeological DFN model (Hydro-DFN). The main focus of this study is the temperate climate period, i.e. the evolution over the next 10,000 years, but the hydrogeological situation under various glacial climate conditions is also evaluated. Primary outputs of the study are repository performance measures relating to: the distributions of groundwater flow around the deposition holes; deposition tunnels and through the EDZ; flow-related transport resistance along groundwater pathways from the repository to the surface; and their the exit locations. Other analyses consider the

Hydrogeological modelling for assessment of radionuclide release scenarios for the repository system 2012

International Nuclear Information System (INIS)

Hartley, L.; Hoek, J.; Swan, D.; Appleyard, P.; Baxter, S.; Roberts, D.; Simpson, T.

2013-07-01

Posiva Oy is responsible for implementing the programme for geological disposal of spent nuclear fuel produced by its owners Teollisuuden Voima Oyj (TVO) and Fortum Power and Heat Oy in Finland. Olkiluoto in Eurajoki has been selected as the primary site for the repository, subject to further detailed investigation which is currently focused on the construction of an underground rock characterisation and research facility (the ONKALO). An essential part of the assessment of long-term safety of a repository is the analysis of groundwater flow since it is the only means of transport of radionuclides to the biosphere (besides human intrusion). The analysis of long-term safety for a KBS-3 concept requires as input a description of details of the groundwater flow around and through components of the engineered barrier system as well as details of the groundwater pathway to the biosphere during the current temperate climate period, as well as indications of behaviour under future climate periods such as glacial conditions. This report describes the groundwater flow modelling study performed to provide some of the necessary inputs required by Safety Assessment (i.e. radionuclide transport analysis). Underlying this study is the understanding of the site developed during the site investigations as summarised in the site descriptive model (SDM), and in particular the description of Olkiluoto Hydrogeological DFN model (Hydro-DFN). The main focus of this study is the temperate climate period, i.e. the evolution over the next 10,000 years, but the hydrogeological situation under various glacial climate conditions is also evaluated. Primary outputs of the study are repository performance measures relating to: the distributions of groundwater flow around the deposition holes; deposition tunnels and through the EDZ; flow-related transport resistance along groundwater pathways from the repository to the surface; and their the exit locations. Other analyses consider the

High-speed photometry of the eclipsing dwarf nova OY Carinae

Science.gov (United States)

Cook, M. C.

1985-01-01

High-speed photometry of the eclipsing dwarf nova OY Car in the quiescent state is presented. OY Car becomes highly reddened during eclipse, with minimum flux colours inconsistent with optically thick emission in the U and B bandpasses. Mass ratios in the range 6.5 to 12 are required to reconcile the eclipse structure with theoretical gas stream trajectories. Primary eclipse timings reveal a significant decrease in the orbital period and the duration of primary eclipse indicates the presence of a luminous ring about the white dwarf. The hotspot eclipse reveals a hotspot which is elongated along the rim of the accretion disc, with optical emission being non-uniformly distributed along the rim. The location of the hotspot in the accretion disc implies a disc radius larger than that of an inviscid disc, with variation in the position of the hotspot being consistent with a fixed stream trajectory.

Transpro Oy:n koulutustenhallintajärjestelmä

OpenAIRE

Pöntinen, Mika

2011-01-01

Opinnäytetyössä toteutetaan koulutustenhallintajärjestelmä tuusulalaiselle Transpro Oy:lle, joka on kuljettajien ammattipätevyyskoulutuksiin erikoistunut yritys. Järjestelmän tehtävänä on tarjota työkalu, jolla voidaan hallita tietoja koulutustapahtumista, koulutustapahtumiin osallistuvista oppilaista, kouluttajista ja asiakkaista. Järjestelmä on toteutettu WWW-sovelluksena. Pääohjelmointikieli on PHP ja järjestelmän dynaamiset toiminnot on toteutettu JavaScript-kielellä. Sivuston haku j...

Selvitys kulttuuriyrityksen laajentumis- mahdollisuuksista. Saiffa Oy:n tapaus

OpenAIRE

Sirviö, Jussi

2013-01-01

Opinnäytetyö selvittää kulttuuriyrityksen laajentumismahdollisuuksia. Teoreettinen viitekehys on franchisingtoimintamalli, mutta selvitys on avoin myös muille toimivaksi osoittuville malleille. Opinnäytetyö on tapaustutkimus katutanssikeskus Saiffa – Flow Mo Dance Schoolille, jota johtaa Saiffa oy. Vuonna 2010 perustettu Saiffa on helsinkiläinen tanssikoulu, joka on erikoistunut katutanssilajeihin, kuten breakdance, popping locking ja hip hop. Sen toimialaan kuuluu tanssiopetuksen lis...

Transfer of NPP technology from Finland fo Hungary

Energy Technology Data Exchange (ETDEWEB)

Varis, M. V.K. [Imatran Voima Oy, Vantaa (Finland); Frigyesi, F. [Paksi Atomeroemue Vallalat (Hungary)

1989-07-15

Imatran Voima Oy (IVO), which accounts for 45% of the total Finnish electricity supply, have their own architect-engineering capacity. This know-how is also available internationally (IVO International). This report explains how technology is transferred to the client's organisation using the advantages of the client's own organization culture, supplemented by IVO's experience. The technology transferred to the Hungarian Paks Nuclear Power Company (PAV) regarding project management services is a good example. A materials management example explains the method. The customer is familiarized via wall chart on which the useful features in IVO's system are added.

Miesten muodin verkkokauppakonsepti : case: FRENN Company Oy

OpenAIRE

Hautaniemi, Tapio

2015-01-01

Tämä opinnäytetyö käsittelee miesten muodin verkkokaupan perustamista ja kehittämistä. Työ on tehty toimeksiantona vuoden 2013 syksyllä lanseeratulle suomalaisella miesten vaatemerkille Frenn Company Oy:lle. Opinnäytetyön aihe valikoitui toimeksiantajan toiveiden pohjalta sekä omasta mielenkiinnostani ja kokemuksestani aiheeseen. Työn tavoitteena on selvittää, millainen on kansainvälinen miesten muodin verkkokauppa ja miten alan muut toimijat ovat verkkokauppansa toteuttaneet. Opinnäytet...

KOKEMUKSET ASIAKKUUKSIEN JOHTAMISESTA : Case: Buildercom Oy partneriasiakkaat

OpenAIRE

Porkka, Elina

2013-01-01

Tässä opinnäytetyössä tutkittiin, miten Buildercom Oy:n partneritason asiakkaat olivat kokeneet heihin kohdistetun asiakkuuden hoitomallin. Tavoitteena oli tutkia, miten asiakkaat oli tällä hetkellä jaettu erilaisiin ryhmiin, millaista lisäarvoa hoitomallilla on mahdollisesti kyetty asiakkaille tuottamaan, ja mitkä tekijät ovat vaikuttaneet asiakkaiden kokemusten laatuun. Tutkimus toteutettiin kokonaisuudessaan kevään 2012 ja kevään 2013 välisenä aikana. Tutkimus suoritettiin, koska toimeksia...

Markkinointiviestintäsuunnitelma Case: MK Kivipiha Oy

OpenAIRE

Ruohomaa, Sami

2011-01-01

Tämän opinnäytetyön tarkoituksena on ollut markkinointiviestintäsuunnitelman laatiminen MK Kivipiha Oy:lle. Opinnäytetyö toteutettiin projektityönä, jonka lisäksi benchmarkkaus osiossa hyödynnettiin kvalitatiivista eli laadullista analyysiä. Lähtökohtana pidettiin suunnitelman realistisuutta ja käytännön toteuttamisen mahdollisuutta. Opinnäytetyö rakentuu kahdesta eri osiosta: teoreettisesta viitekehyksestä sekä empiirisestä osuudesta. Teoriana käytettiin katsausta perinteisen markkinointivie...

Vähittäismyymälän markkinoinnin kehittäminen : case Mattomies Oy

OpenAIRE

Hellstén, Maren

2015-01-01

Opinnäytetyön tavoitteena oli löytää toimeksiantajana toimineelle Mattomies Oy Ruohola & Ruoholalle konkreettisia keinoja yrityksen vähittäismyymälän markkinoinnin kehittämiseksi. Teoriaosassa käytiin läpi 4P-mallin mukaiset markkinoinnin kilpailukeinot. Toteutusosassa analysoitiin Mattomies Oy Ruohola & Ruoholan myymälän nykytilaa, myymälän merkitystä liiketoiminnalle sekä koottiin myymälälle markkinointimix, jossa annettiin konkreettisia ehdotuksia markkinoinnin kehittämiseksi. Ehdo...

Työohjeistus Perälän Turve Oy

OpenAIRE

Haukka, Arto

2014-01-01

Perälän Turve Oy:n uusille työntekijöille laadittu työohjeistus ja siitä raportointi. Työhön kuuluu kaksi osaa, word-raportti sekä powerpoint-työohjeistuskansio. Powerpoint-tiedosto upotettuna tiedostona alkuperäisessä word-tiedostossa.

Asiakkuudenhallinnan avulla lisäarvoa asiakkaalle ja lisämyyntiä yritykselle : case Naaantalin Matkailu Oy

OpenAIRE

Korpiranta, Mirka

2012-01-01

Tässä opinnäytetyössä on selvitetty, miten Naantalin Matkailu Oy voi asiakkuudenhallinnan avulla luoda lisäarvoa asiakkaille ja tuottaa lisänmyyntiä yritykselle. Lisäksi on selvitetty, miten Winres-matkatoimistojärjestelmää voidaan hyödyntää asiakkuudenhallinnassa tavoitteiden saavuttamiseksi. Vertailukohteina käytettiin muita matkailutoimistoja, jotka muistuttavat Naantalin Matkailu Oy:tä ja Naantalia kohteena. Opinnäytetyön vertailukartoitus toteutettiin kyselynä, jonka tarkoituksena oli...

Työterveys- ja työturvallisuusjohtamisjärjestelmä : Case Tapojärvi Oy

OpenAIRE

Honkanen, Päivi

2011-01-01

Honkanen, Päivi. 2011. Työterveys- ja työturvallisuusjohtamisjärjestelmä. Case Tapo-järvi Oy. Opinnäytetyö. Kemi-Tornion ammattikorkeakoulu. Kaupan ja kulttuurin toimiala. Sivuja 33. Tämän opinnäytetyön tavoitteena on selvittää Tapojärvi Oy:n työterveys- ja työturvalli-suusjohtamisjärjestelmän nykytilaa ja arvioida kuinka se vastaa standardin OHSAS 18001:2007 vaatimuksia. Opinnäytetyö koostuu teoriaosuudesta ja empiirisestä tutkimuksesta. Teoriaosassa käsit-telen turvallisuusjohtamis...

Hissihuollon kehittäminen ThyssenKrupp hissit Oy

OpenAIRE

Nieminen, Jani

2013-01-01

Insinöörityössä kartoitettiin ThyssenKrupp Hissit Oy:n kunnossapidon tämänhetkinen toi-mintamalli ja sen pohjalta laadittiin kunnossapidon kehityssuunnitelman runko. Thyssen-Krupp Hissien huoltotoiminta on kasvanut voimakkaasti muutamassa vuodessa pienestä helposti johdettavasta yksiköstä usean henkilön johtamaksi organisaatioksi. Haastattelujen, vikatilastojen ja oman kokemukseni avulla päädyin siihen, että nykyinen hissien kunnossapito perustuu voimakkaasti korjaavaan kunnossapitoon ja ...

Organizational Challenge of Posiva’s Final Disposal Programme: From an R&D Organization to a Project Organization, and Further Towards an Operational Organization

International Nuclear Information System (INIS)

Mokka, J.

2016-01-01

Full text: Posiva Oy is an expert organization established in 1995 and responsible for the final disposal of the spent nuclear fuel of its owners. Posiva currently employs around 100 people and has a turnover of some 63 million (2015). The company headquarters are located in Olkiluoto in the municipality of Eurajoki, Finland. Posiva is owned by two Finnish NPP operators Teollisuuden Voima Oyj (60%) (TVO) and Fortum Power & Heat Oy (40%), both of which are responsible for their costs of nuclear waste management. The Finnish final disposal programme has a long history. When NPP unit Olkiluoto 1 renewed its operating licence for the first time in 1983, TVO presented a programme showing final disposal to commence in the 2020s. In the 1980s and 1990s, the programme concentrated on concept development and site selection activities. After 2003, when Posiva received the decision in principle from the Finnish Government, a new phase began in the programme. Since 2004, Posiva Oy has constructed an underground rock characterization facility on the repository site in Olkiluoto, in western Finland. This facility, called ONKALO, has provided an opportunity to carry out further site investigations, develop construction techniques, and test and demonstrate the engineered barrier system in an actual repository environment. As a result of these investigations and development efforts, the application for a licence to construct the encapsulation plant and the geological repository was submitted in 2012. The Radiation and Nuclear Safety Authority in Finland (STUK) first gave a positive review on the safety of the facility, and consequently the Finnish Government granted the construction licence in November 2015. After receiving the construction licence as the first disposal programme in the world, the next phase in the program will be the construction project of the final disposal facilities required for the disposal operations. A significant first-of-a-kind construction project like

Social Media Marketing : CASE: OY SUOMEN LYYRA AB

OpenAIRE

Eriksson, Irene

2012-01-01

This bachelor thesis was commissioned by Oy Suomen Lyyra Ab, the largest student online media and student card producer for higher education students in Finland. The the-sis objective was to understanding the current social media situation and activity among the students of higher education in Finland, the social media networks that the case company currently uses as well as understanding how to use these networks for successful marketing activities. The quantitative research was conducted in...

Integrated Brand Promotion – Advertisement for STADIUM OY

OpenAIRE

Mai, Tung

2014-01-01

This project-based thesis is an advertisement for Stadium Oy. In 23 years of leading marketing department, Stadium’s marketing manager had to say this is a pioneer time when Stadium’s outsources an advertising project to an external individual resource. The project, therefore, consists a number of business partners so that professional quality is guaranteed to deliver. STADIUM’s advertising strategy stays committed to the company’s business model and its mission. This directly affec...

5S-menetelmän käyttöönotto Case: Planmeca Oy

OpenAIRE

Velic, Adel

2014-01-01

Opinnäytetyön tavoitteena on tutkia Planmeca Oy:n panoraamaröntgentuotannossa syksyllä 2012 toteutetun 5S-projektin onnistuneisuutta. Työ kattaa sekä 5S-periaatteiden mukaisesti suunniteltujen ja toteutettujen panoraamaröntgentuotannon Elko-, Pystytys 1 -, Pystytys 2 - sekä Potilastuki- ja skannausmekanismitiimin työpisteiden että projektin toteutustavan onnistuneisuuden mittaamisen. Tutkimusmenetelmänä käytetään Elko-, Pystytys 1 -, Pystytys 2 - sekä Potilastuki- ja skannausmekanismitiim...

Henkilöstötilinpäätös Yritys Oy

OpenAIRE

Turunen, Tytti

2011-01-01

Tämän opinnäytetyön aiheena oli Yritys Oy:n henkilöstötilinpäätös vuodelta 2009. Henkilöstötilinpäätös jaetaan kahteen osaan, henkilöstötuloslaskelmaan ja henkilöstökertomukseen. Tavoitteena oli laatia Yritys Oy:lle henkilöstötilinpäätöksestä malli, jota yritys voi käyttää ja hyödyntää tulevaisuudessa henkilöstötilinpäätöstä laatiessa. Tavoitteena oli myös antaa kehittämisehdotuksia, minkälaista tietoa kannattaa kerätä seuraavia henkilöstötilinpäätöksiä varten. Henkilöstötilinpäätöksen tavoit...

Sisäisen viestinnän kehittäminen osana parempia kampanjatoteutuksia : Case: Nike Finland Oy

OpenAIRE

Kankkunen, Eeva

2014-01-01

Tämä opinnäytetyö tehtiin Nike Finland Oy:lle, ja sen aiheena oli sisäisen viestinnän kehittäminen osana parempia kampanjatoteutuksia. Nike Finland Oy on maailman tunnetuimman urheilubrändin Niken Suomen organisaatio, ja tällä hetkellä se on toisena vastaavien tuotteiden valmistajana Suomen markkinoilla. Yritys tunnetaan niin Suomessa kuin maailmallakin kuuluisasta ja uniikista Niken logosta, ja sloganista ”Just do it”. Koska yritys on aina enemmän kuin pelkästään sen hyvä yritysimag...

Creating strategic brand management manual : Case: Tukikallio Oy

OpenAIRE

Vepsäläinen, Sini

2010-01-01

The purpose of this Thesis was to create a Strategic Brand Management Manual for the use of a new company called Tukikallio Oy. The manual was composed of the elements that the company wanted to include in it. A qualitative research method was used in collecting information. The theoretical part of the thesis includes theories about brand building. Brand identity tells what the brand really is with its positive and negative sides, image reflects on what kind of things the consumer associa...

Structural and superconducting properties of YBa2Cu3-xMxOy (M=Ag, Al

Directory of Open Access Journals (Sweden)

S Falahati

2009-08-01

Full Text Available   Samples of YBa2Cu3-xAgxOy with x=0, 0.1, 0.15, 0.2, 0.3 and samples of YBa2Cu3-xAlxOy with x=0, 0.01, 0.02, 0.03 and 0.045 are prepared by the sol-gel method. Structural and superconducting properties of samples are studied by electrical resistivity (R-T, X-ray diffraction (XRD and scanning electron microscopy (SEM. All the samples show transition to superconducting state and the transition temperatures of the samples increased with increasing Ag doping up to x=0.15. R-T measurements show a small decrease of TC (zero with increasing Al doping up to x=0.02, and followed by a faster decrease with increasing doping concentration. YBCO grains are better linked with increasing Ag doping. So, Ag has positive effects in superconducting properties of YBCO. The crystal structure of samples was refined by MAUD. These results show tha, Ag is substituted for Cu(1 in YBCO. According to these analysis, we introduce x=0.15 as the optimum value for doping concentration .

Maintaining staff competence-a NPP operator viewpoint

International Nuclear Information System (INIS)

Patrakka, E.

2000-01-01

For a nuclear power plant operator, it is crucial to guarantee the safe and economic operation of the power plant as well as to look after the general acceptability of nuclear power. As to human resources management, this requires continuous maintenance and enhancement of the performance of the individuals and organisation. To this end, several development projects have recently been implemented by Teollisuuden Voima Oy (TVO) at the Olkiluoto nuclear power plant, which consists of twin 840 MWe BWR units that commenced their operation in 1978 and 1980. Systematic initial and continuing training programmes are needed to maintain the technical and managerial skills and know-how at a high level. The present stabile state of nuclear power, i.e. operation of ageing plants with personnel ageing as well, requires a variety of actions to reinforce the training efforts. At Olkiluoto NPP, we have carried out an extensive modernization programme that allowed the personnel to strengthen their knowledge and supplement it with the most recent results of development. We have also closely monitored the NPP development projects of the vendors, which has added to the preservation of know-how and understanding of advanced nuclear power technology. We have close contacts to the research institutes and universities, and have performed R and D activities to limited extent. In addition to the projects mentioned above, a co-ordinated development programme, 'TVO 2002', was initiated last year. The main objective of this programme is to ensure the functional preconditions and the competitiveness of the company in a changing environment. The management and operational procedures will be developed in such a way that the goals set for year 2002 will be achieved. The programme is organised as ten projects, which cover a variety of development subjects. One of the focal areas includes projects that can be characterised with the words 'Survey of competencies' and 'Preservation of know

Distribution strategy: : A case study of Plantui Oy

OpenAIRE

Korpinen, Sakari; Siltala, Roope

2015-01-01

Distribution strategy: A case study of Plantui Oy Year 2015 Pages 57 Plantui is a Finnish start-up company focusing on enabling customers to grow plants at home. Plantui operates in the field of design and food tech. Plantui’s product offering consists of the Smart Garden, a device in which the plants are grown. Another product which Plantui offers to its customers is the plant capsules from which the plants are grown, with the help of the Smart Garden device. Plantui’s selling propos...

RFID-tunnisteiden havaitseminen liikkuvasta ajoneuvosta : case: Fidera Oy

OpenAIRE

Artukka, Riku

2016-01-01

Tämän opinnäytetyön tarkoituksena on testata ja dokumentoida suoritettuja RFID- ajoneuvomittauksia eli ajoneuvojen ja henkilöiden automaattista tunnistusta hyödyntämällä RFID-tunnisteita. Opinnäytetyö on tehty toimeksiantona Fidera Oy:lle. Yrityksellä on jo käytössä automaattinen henkilötunnistusjärjestelmä, tarve olikin soveltaa samaa tekniikkaa ajoneuvojen ja niiden sisällä olevien henkilöiden tunnistukseen. Opinnäytetyön tavoitteena on luoda kuva RFID-tekniikan perusteista ja toimia s...

Mainonnan huomioarvotutkimus. Case Nelipyörä Oy

OpenAIRE

Survonen, Juha

2013-01-01

Tämä opinnäytetyö käsittelee mainontaa markkinointiviestinnän keinona. Toimeksiantajana tällä opinnäytetyöllä on Hämeenlinnassa ja Hyvinkäällä toimiva autoliike, Nelipyörä Oy. Opinnäytetyön tarkoituksena on antaa toimeksiantajalle tietoa heidän mainontansa huomioarvoista käytettyjen mainosmedioiden osalta. Opinnäytetyön teoriaosuus koostuu markkinointiviestinnästä sekä mainonnasta. Markkinointiviestinnän osuus keskittyy markkinointiviestinnän suunnitteluun sekä tavoitteisiin. Mainonnan os...

Mazda kiintotyövaiheiden perustaminen : Delta Auto Oy

OpenAIRE

Schreck, Ville

2012-01-01

Täyden palvelun autoliikeketju Delta Auto myy ja huoltaa Kia-, Mitsubishi- ja Mazda-merkkisiä autoja paikkakuntakohtaisesti kahdessakymmenessäviidessä toimipisteessä. Opinnäytetyön tarkoituksena oli tehdä toimiva ratkaisu Mazdan työvaiheiden sekä työpakettien myyntiin Automaster-ohjelmistoon. Työvaiheet sekä ohjeajat tulevat käyttöön kaikkiin Delta Auton toimipisteisiin ympäri Suomea. Työn lähdemateriaalin sain Inchcape Motor Finland Oy:ltä, joka toimii Suomessa Mazdan maahantuojana. Tarve tä...

Insta Trust Oy:n tuottamien kriisiharjoitusten kehittäminen

OpenAIRE

Väinölä, Marko

2016-01-01

Insta Trust Oy toteuttaa asiakkaidensa kanssa kymmeniä kriisiharjoituksia vuosittain. Kriisiharjoitusten avulla pyritään kehittämään harjoittelevien tahojen kriisijohtamisen ja kriisiviestinnän osaamista, tunnistamaan kehittämistä vaativia toimintamalleja ja ohjeita sekä lisäämään organisaation avainhenkilöiden motivaatiota ja tietoisuutta kriisijohtamisesta ja ennakoivaa turvallisuustyötä kohtaan. Kriisiharjoitusten kehittämisessä on osattava kuunnella asiakkaiden tarpeita ja pysyttävä mukan...

Results of Monitoring at Olkiluoto in 2011. Environment

Energy Technology Data Exchange (ETDEWEB)

Haapanen, A. [Haapanen Forest Consulting, Vanhakylae (Finland)

2012-11-15

This Working Report presents the main results of Posiva Oy's environmental monitoring programme on Olkiluoto Island in 2011. These summary reports have been published since 2005. The environmental monitoring system supervised by Posiva Oy produces input for biosphere modelling for long-term safety purposes as well as for monitoring the state of the environment during the construction (and later operation) of ONKALO underground rock characterization facility. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). Monitoring has been carried out for varying periods of time depending on the sector: some monitoring activities performed by TVO originate from the 1970s and the repository-related environmental monitoring of Olkiluoto from the early 2000s. The monitoring programme evolves according to experiences gained from the modelling work and increased understanding of the site. Monitoring activities in 2011 proceeded according to the plans. The land-use of the island continues to change due to the construction work of OL3, ONKALO and related infrastructure, but the remaining natural environment resembles other coastal locations. The amount of nitrogen in the bulk deposition increased in 2011, whereas that of sulphur decreased. Some litterfall fractions showed higher Al and Fe values than earlier, likely caused by soil dust. Proximity of the sea is seen in wet deposition and soil solution results. Soil solution also reflects the young age of soils. Undestorey vegetation has shown no essential changes during the monitoring period. Mammalian fauna on the island is typical of coastal areas in Southwestern Finland. Game catches vary according to hunting pressure and natural variation in populations. The condition of the nearby sea is affected by the continuous land uplift, the shallowness of the area, the weather conditions, the general condition of the Bothnian Sea, the nutrient and sediment loads

Results of Monitoring at Olkiluoto in 2011. Environment

International Nuclear Information System (INIS)

Haapanen, A.

2012-11-01

This Working Report presents the main results of Posiva Oy's environmental monitoring programme on Olkiluoto Island in 2011. These summary reports have been published since 2005. The environmental monitoring system supervised by Posiva Oy produces input for biosphere modelling for long-term safety purposes as well as for monitoring the state of the environment during the construction (and later operation) of ONKALO underground rock characterization facility. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). Monitoring has been carried out for varying periods of time depending on the sector: some monitoring activities performed by TVO originate from the 1970s and the repository-related environmental monitoring of Olkiluoto from the early 2000s. The monitoring programme evolves according to experiences gained from the modelling work and increased understanding of the site. Monitoring activities in 2011 proceeded according to the plans. The land-use of the island continues to change due to the construction work of OL3, ONKALO and related infrastructure, but the remaining natural environment resembles other coastal locations. The amount of nitrogen in the bulk deposition increased in 2011, whereas that of sulphur decreased. Some litterfall fractions showed higher Al and Fe values than earlier, likely caused by soil dust. Proximity of the sea is seen in wet deposition and soil solution results. Soil solution also reflects the young age of soils. Undestorey vegetation has shown no essential changes during the monitoring period. Mammalian fauna on the island is typical of coastal areas in Southwestern Finland. Game catches vary according to hunting pressure and natural variation in populations. The condition of the nearby sea is affected by the continuous land uplift, the shallowness of the area, the weather conditions, the general condition of the Bothnian Sea, the nutrient and sediment loads

Results of Monitoring at Olkiluoto in 2011. Environment

Energy Technology Data Exchange (ETDEWEB)

Haapanen, A. (ed.) [Haapanen Forest Consulting, Vanhakylae (Finland)

2012-11-15

This Working Report presents the main results of Posiva Oy's environmental monitoring programme on Olkiluoto Island in 2011. These summary reports have been published since 2005. The environmental monitoring system supervised by Posiva Oy produces input for biosphere modelling for long-term safety purposes as well as for monitoring the state of the environment during the construction (and later operation) of ONKALO underground rock characterization facility. Part of the monitoring is performed by the company running the nuclear power plants on the island, Teollisuuden Voima Oy (TVO). Monitoring has been carried out for varying periods of time depending on the sector: some monitoring activities performed by TVO originate from the 1970s and the repository-related environmental monitoring of Olkiluoto from the early 2000s. The monitoring programme evolves according to experiences gained from the modelling work and increased understanding of the site. Monitoring activities in 2011 proceeded according to the plans. The land-use of the island continues to change due to the construction work of OL3, ONKALO and related infrastructure, but the remaining natural environment resembles other coastal locations. The amount of nitrogen in the bulk deposition increased in 2011, whereas that of sulphur decreased. Some litterfall fractions showed higher Al and Fe values than earlier, likely caused by soil dust. Proximity of the sea is seen in wet deposition and soil solution results. Soil solution also reflects the young age of soils. Undestorey vegetation has shown no essential changes during the monitoring period. Mammalian fauna on the island is typical of coastal areas in Southwestern Finland. Game catches vary according to hunting pressure and natural variation in populations. The condition of the nearby sea is affected by the continuous land uplift, the shallowness of the area, the weather conditions, the general condition of the Bothnian Sea, the nutrient and sediment

Selvitys HR House Oy:n vuokratyöntekijöiden työtyytyväisyydestä

OpenAIRE

Kaskela, Leeni

2011-01-01

Opinnäytetyön tarkoituksena oli selvittää HR House Oy:n palveluksessa olevien vuokratyöntekijöiden työtyytyväisyyteen vaikuttavia asioita. Opinnäytetyö on laadullinen tutkielma, jossa käytän tutkimusmenetelmänä teemahaastattelua. Tutkimuskysymykseni selvittävät, mitkä asiat vaikuttavat työntekijöiden työ- tyytyväisyyteen ja mitä he kertovat työtyytyväisyyteen vaikuttavista tekijöistä. Toimeksianto opinnäytetyön tekemiseen on tullut HR House Oy Henkilöstöpalveluilta. Tavoitteena oli löytää kei...

Feed water distribution pipe replacement at Loviisa NPP

Energy Technology Data Exchange (ETDEWEB)

Savolainen, S.; Elsing, B. [Imatran Voima Loviisa NPP (Finland)

1995-12-31

Imatran Voima Oy operates two WWER-440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of feed water distribution (FWD) pipe were observed in 1989. The FWD-pipe T-connection had suffered from severe erosion corrosion damages. Similar damages have been been found also in other WWER-440 type NPPs. In 1989 the nozzles of the steam generator YB11 were inspected. No signs of the damages or signs of erosion were detected. The first damaged nozzles were found in 1992 in steam generators of both units. In 1992 it was started studying different possibilities to either repair or replace the damaged FWD-pipes. Due to the difficult conditions for repairing the damaged nozzles it was decided to study different FWD-pipe constructions. In 1991 two new feedwater distributors had been implemented at Dukovany NPP designed by Vitckovice company. Additionally OKB Gidropress had presented their design for new collector. In spring 1994 all the six steam generators of Rovno NPP unit 1 were replaced with FWD-pipes designed by OKB Gidropress. After the implementation an experimental program with the new systems was carried out. Due to the successful experiments at Rovno NPP Unit 1 it was decided to implement `Gidropress solution` during 1994 refueling outage into the steam generator YB52 at Loviisa 2. The object of this paper is to discuss the new FWD-pipe and its effects on the plant safety during normal and accident conditions. (orig.).

Feed water distribution pipe replacement at Loviisa NPP

Energy Technology Data Exchange (ETDEWEB)

Savolainen, S; Elsing, B [Imatran Voima Loviisa NPP (Finland)

1996-12-31

Imatran Voima Oy operates two WWER-440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of feed water distribution (FWD) pipe were observed in 1989. The FWD-pipe T-connection had suffered from severe erosion corrosion damages. Similar damages have been been found also in other WWER-440 type NPPs. In 1989 the nozzles of the steam generator YB11 were inspected. No signs of the damages or signs of erosion were detected. The first damaged nozzles were found in 1992 in steam generators of both units. In 1992 it was started studying different possibilities to either repair or replace the damaged FWD-pipes. Due to the difficult conditions for repairing the damaged nozzles it was decided to study different FWD-pipe constructions. In 1991 two new feedwater distributors had been implemented at Dukovany NPP designed by Vitckovice company. Additionally OKB Gidropress had presented their design for new collector. In spring 1994 all the six steam generators of Rovno NPP unit 1 were replaced with FWD-pipes designed by OKB Gidropress. After the implementation an experimental program with the new systems was carried out. Due to the successful experiments at Rovno NPP Unit 1 it was decided to implement `Gidropress solution` during 1994 refueling outage into the steam generator YB52 at Loviisa 2. The object of this paper is to discuss the new FWD-pipe and its effects on the plant safety during normal and accident conditions. (orig.).

Kanta-asiakasohjelman kehittäminen : case Crocs Stores Oy

OpenAIRE

Manninen, Mirka

2014-01-01

Kanta-asiakkuuden tavoitteena on molemminpuolinen arvon tuottaminen asiakkaan ja yrityksen välillä. Tämän tutkimuksen tavoitteena on selvittää, millainen kanta-asiakasohjelma olisi toimeksiantajayrityksen kannalta toimivin. Tutkimus on tapaus- eli case -tutkimus, jonka toimeksiantaja on Crocs Stores Oy. Toimeksiantajalla on tällä hetkellä käytössään kanta-asiakasohjelma, joka ei palvele yrityksen tarpeita. Paremman kanta-asiakasohjelman kehittämisen lisäksi tavoitteina on selvittää asiakkaide...

Sosiaalisen median merkitys mikroyrityksille - Case: TallFits Oy

OpenAIRE

Nousiainen, Ari; Koskivuori, Timo

2011-01-01

Tämän opinnäytetyön aiheena on sosiaalinen media mikroyritysten näkökulmasta. Työssä käsi-tellään sosiaalista mediaa ja markkinoinnissa tapahtunutta muutosta sekä niitä toimintatapoja, joita interaktiivinen mediaympäristö yrityksille ja sen asiakkaille tarjoaa. Työn tavoitteena on tuottaa tietoa sosiaalisen median hyödyistä ja haasteista mikroyrityksille ja lisätä koh-deyrityksemme TallFits Oy:n myyntiä ja löydettävyyttä. Tavoitteiden saavuttamiseksi opinnäytetyömme tarkoituksena oli tehd...

Kankaan tuotekehittäminen erikoisolosuhteisiin K&H Annala Oy:lle

OpenAIRE

Koski, Marjo

2017-01-01

Opinnäytetyö tehtiin yhteistyössä Suomen ainoan huonekalukankaita valmistavan yrityksen K&H Annala Oy:n kanssa. Työn aiheena oli suunnitella ja tuotteistaa kangasmallisto erikoisolosuhteisiin innovatiivisesta, Italiassa valmistettavasta Flyer-langasta. Projektin lähtökohtana oli opinnäytetyöntekijän kasvava kiinnostuneisuus kudottuja tekstiilejä kohtaan ja kankaan suunnitteluprosessin vieminen teollisen tuotannon puolelle. Projektissa tähdättiin uudentyyppiseen kankaaseen ilmeen ja materiaali...

The using of the control room automation against human errors

International Nuclear Information System (INIS)

Kautto, A.

1993-01-01

The control room automation has developed very strongly during the 80's in IVO (Imatran Voima Oy). The former work expanded strongly with building of the full scope training simulator to the Loviisa plant. The important milestones has been, for example the testing of the Critical Function Monitoring System, a concept developed by Combustion Eng. Inc., in Loviisa training simulator 1982, the replacing of the process and simulator computers in Loviisa 1989, and 1990 and the presenting the use of the computer based procedures in training of operators 1993. With developing of automation and procedures it is possible to minimize the probability of human error. However, it is not possible totally eliminate the risks caused by human errors. (orig.)

Development of a new WWER-440 fuel design

International Nuclear Information System (INIS)

Coucil, D.; Totev, T.

1998-01-01

In March 1996 British Nuclear Fuel Limited signed a contract with Imatran Voima and Paks Nuclear Power Plant to design, develop, license and supply 5 Lead Test Assemblies to the WWER-440 reactor at Loviisa in Finland. In June 1998 the manufacture of these 5 assemblies (4 fixed assemblies and 1 follower assembly) was completed. The fuel is expected to be loaded into Loviisa Unit 2 reactor during the shutdown scheduled for September of this year. (Authors)

Period changes of cataclysmic variables below the period gap: V2051 Oph, OY Car and Z Cha

Science.gov (United States)

Pilarčík, L.; Wolf, M.; Zasche, P.; Vraštil, J.

2018-04-01

We present our results of a long-term monitoring of cataclysmic variable stars (CVs). About 40 new eclipses were measured for the three southern SU UMa-type eclipsing CVs: V2051 Oph, OY Car and Z Cha. Based on the current O - C diagrams we confirmed earlier findings that V2051 Oph and OY Car present cyclic changes of their orbital periods lasting 25 and 29 years, respectively. In case of Z Cha we propose the light-time effect caused probably by a presence of the third component orbiting the eclipsing CV with the period of 43.5 years. The minimal mass of this companion results about 15 MJup.

Managing Customer Relationships in the Social Media : Case: Diamo oy

OpenAIRE

Laakso, Heidi

2013-01-01

The purpose of this study was to increase the amount of new likes of Diamo Oy in the social media network site Facebook, eventually aiming for the creation of new customer relationships, increased visibility of the company and into strictly increasing purchasing of their products. The theoretical part of the study consists of the role of content production in the social media field and customer relationship management, of which particularly customer acquisition and retention are discussed mor...

Enhanced thermoelectric properties of nano SiC dispersed Bi2Sr2Co2Oy Ceramics

Science.gov (United States)

Hu, Qiujun; Wang, Kunlun; Zhang, Yingjiu; Li, Xinjian; Song, Hongzhang

2018-04-01

The thermoelectric properties of Bi2Sr2Co2Oy + x wt% nano SiC (x = 0.00, 0.025, 0.05, 0.1, 0.2, and 0.3) prepared by the solid-state reaction method were investigated from 300 K to 923 K. The resistivity can be reduced effectively by adding a small amount of SiC nano particles, which is attributed to the increase of the carrier concentration. At the same time, the Seebeck coefficients can be improved effectively due to the energy filtering effect that low energy carriers are strongly dispersed at the interface between the SiC nano particles and the matrix. The decrease of thermal conductivity is due to the increase of the scattering ability of the phonons by the SiC nanoparticles distributed at the boundary of the matrix. As a result, the Bi2Sr2Co2Oy + x wt% SiC composites exhibit better thermoelectric properties. The maximum ZT value 0.24 is obtained when x = 0.05 at 923 K. Compared with the sample without SiC nano particles, the ZT value is increased by about 59.7%.

Valmistalokauppa : Toimintatapa ja omavalvonnan kehitystarpeet Muurametalot Oy:ssä

OpenAIRE

Kantola, Jussi

2012-01-01

Valmistalokauppa on kehittynyt paljon viimeisten vuosien aikana. Taloja valmistavia yrityksiä on perustettu runsaasti ja valmistalojen kysyntä on kasvanut. Työn tarkoituksena oli päivittää Muurametalot Oy:n omavalvontajärjestelmä vastaamaan paremmin tämän päivän tarpeita. Tavoitteena oli muokata omavalvonnassa käytettävät tarkastuspöytäkirjat nykypäivän asetusten tasolle. Ideaalitilanne olisi, että jokainen työntekijä osallistuu omavalvonnan käyttöön. Järjestelmän periaatteena on tarjota ...

Yritys X Oy:n myyntijohtolankojen hallintaprosessin kehittäminen

OpenAIRE

Jokinen, Mika

2014-01-01

Tässä kehittämistehtävässä tutkittiin miten Yritys X Oy:n myyntijohtolankojen hallintaprosessia voidaan kehittää niin, että se tuottaisi enemmän ja laadukkaampia myyntijohtolankoja myynnin käsiteltäväksi. Yritys X on kansainvälisiä logistiikkapalveluja tuottava yritys ja myyntijohtolankojen avulla voidaan hankkia uusia asiakkaita ja lisämyyntiä. Tutkimuksen lähtöaineisto kerättiin kyselytutkimuksella kuljettajilta ja ajojärjestelijöiltä. Kehittämistyön tueksi aineistoa kerättiin myös myy...

Todellista asiakasarvoa luomassa – myynnistä arvomyyntiin : case Mediamaisteri Oy

OpenAIRE

Brander, Heli

2017-01-01

Tämän opinnäytetyön tavoite oli case-yritys Mediamaisteri Oy:n B2B-myyntiprosessin kehittäminen. Tarkoitus oli hyödyntää palvelumuotoilua lisäämään asiakasymmärrystä ja tukemaan asiakkaiden kokeman arvon muodostumista sekä positiivisten asiakaskokemusten syntymistä myyntiprosessin alkuvaiheen asiakaskohtaamisissa. Lisäksi tarkoitus oli kiteyttää empiirisen aineiston pohjalta saatu tieto asiakasprofiileiksi, joita voidaan hyödyntää asiakaslähtöisten ratkaisujen suunnittelussa heti asiakkuuden ...

Toimintolaskennan soveltaminen : Case Hyvönen Yhtiöt Oy

OpenAIRE

Hyvönen, Krista

2014-01-01

Tässä opinnäytetyössä kehitetään toimeksiantajayrityksenä toimivalle Hyvönen Yhtiöt Oy:lle toimintolaskentaa hyödyntävä kustannuslaskentamalli. Tehdyn kehitystyön tavoitteena on luoda kohdeyritykselle täysin uudenlainen kustannuslaskentamalli, joka näyttää kustannukset uudesta näkökulmasta erilaisen ryhmittelyn ansiosta sekä selvittää toimintolaskennan soveltuvuutta yrityksen palvelukohtaisten kustannusten laskemiseen. Tutkimustehtävänä on selvittää, miten toimintolaskentaa voidaan soveltaa H...

Loviisa starts low-level operating waste disposal in 1997

International Nuclear Information System (INIS)

Snellman, J.

1996-01-01

At an early stage Imatran Voima Oy (IVO) decided to construct a waste repository for Loviisa NPP. The suitability of the power plant site for final disposal of low- and intermediate- level operating waste was studied. In the site report in 1982 the plant site was found to be geologically suitable and economically feasible for construction. The necessary preparations started in 1992. The repository will be constructed in three phases. The first phase will cover the transport tunnel, construction of one maintenance waste tunnel and the excavation of another maintenance waste tunnel together with a hall for solidified wastes. This phase will be finished by the end of 1996. During the second phase in the beginning of next century the remaining already excavated rooms will be furnished. Finally in the third phase the repository will be extended for the decommissioning waste somewhere around years 2020-2025. (3 figs., 1 tab.)

Electronic structure and fine structural features of the air-grown UNxOy on nitrogen-rich uranium nitride

Science.gov (United States)

Long, Zhong; Zeng, Rongguang; Hu, Yin; Liu, Jing; Wang, Wenyuan; Zhao, Yawen; Luo, Zhipeng; Bai, Bin; Wang, Xiaofang; Liu, Kezhao

2018-06-01

Oxide formation on surface of nitrogen-rich uranium nitride film/particles was investigated using X-ray photoelectron spectroscopy (XPS), auger electron spectroscopy (AES), aberration-corrected transmission electron microscopy (TEM), and high-angle annular dark-field scanning transmission electron microscopy (HAADF-STEM) coupled with electron energy-loss spectroscopy (EELS). XPS and AES studies indicated that the oxidized layer on UN2-x film is ternary compound uranium oxynitride (UNxOy) in 5-10 nm thickness. TEM/HAADF-STEM and EELS studies revealed the UNxOy crystallizes in the FCC CaF2-type structure with the lattice parameter close to the CaF2-type UN2-x matrix. The work can provide further information to the oxidation mechanism of uranium nitride.

Toimenpide-ehdotuksia sosiaaliseen mediaan : case: Sony Music Entertainment Finland Oy

OpenAIRE

Marttila, Noora

2016-01-01

Tämä opinnäytetyö toteutettiin toimeksiantona Sony Music Entertainment Finland Oy levy-yhtiölle. Toimeksiantaja on kansainvälinen yritys joka on yksi Suomen suurimmista levy-yhtiöistä. Yritys käyttää sosiaalista mediaa osana digitaalista markkinointiaan. Sitä käytetään erityisesti artistien sekä julkaisujen tunnettuuden lisäämiseen. Sosiaalinen media on kasvava markkinoinnin keino, joka oikein hyödynnettynä voi johtaa hyviin lopputuloksiin. Tämän työn tarkoituksena on antaa yrityksell...

Synthesis of vanadium oxides 5 wt.%VO2–MxOy by sol–gel process ...

Indian Academy of Sciences (India)

Experimental results indicated that the VO2–SiO2 catalysts .... crucible, which was supported by the beam of a balance in the oven. ... Epoxidation of cyclohexene on VO2–Mx Oy (M = Si, Al, Ti). 1189 ... tially amorphous nature of silica.

Markkinointi murroksessa: Mistä on toimiva Facebook-markkinointi tehty? : Case: Infokone Oy

OpenAIRE

Korhonen, Taneli

2010-01-01

Opinnäytetyön tavoitteena oli kartoittaa Facebook-markkinoinnin toimivia käytänteitä B2B-yritykselle. Tutkimuksessa saatuja tuloksia on tarkoitus käyttää apuna toimeksiantaja Infokone Oy:n Facebook-strategian suunnittelussa. Käytetty tutkimusote oli kvalitatiivinen eli laadullinen tutkimus ja tutkimusmenetelmä teemahaastattelu. Tutkimukseen haastateltiin syys–lokakuussa 2010 kolmea B2B-yrityksen edustajaa, jotka olivat olleet mukana toteuttamassa edustamansa yrityksen Facebook-markkinoint...

Kanta-asiakkuuksien hankinta paikallisessa yö-kerhossa, Case: Giggling Marlin Oy

OpenAIRE

Ylärakkola, Emmi

2016-01-01

Tämän opinnäytetyön tarkoituksena oli saada käsitys siitä, saadaanko työssä toteutettujen keinojen avulla uusia kanta-asiakkaita ja aiempia kanta-asiakkaita uusimaan jäsenyytensä paikallisessa yökerhossa. Työn toimeksiantaja oli Giggling Marlin Oy, joka kuuluu Night People Group -ravintolayhtiöön. Giggling Marlin sijaitsee Lappeenrannan keskustassa ja on perustettu alkukeväällä 2006. Toiminnallisena osana suunniteltiin ja toteutettiin mainosmateriaalia kampanja-ajankohdalle sekä valmisteltiin...

A visible and infrared study of the eclipsing dwarf nova OY Carinae

International Nuclear Information System (INIS)

Berriman, G.

1984-01-01

This paper presents four visible light curves of the highly inclined, short-period cataclysmic binary star OY Carinae in quiescence. These light curves show that the red dwarf eclipses both its white dwarf companion and the accretion disc and hotspot, which originate from material transferred from the red dwarf to the white dwarf. The consequences of the findings are discussed in the light of current ideas about the evolution of cataclysmic variable stars. (author)

Electrochemically Obtained TiO2/CuxOy Nanotube Arrays Presenting a Photocatalytic Response in Processes of Pollutants Degradation and Bacteria Inactivation in Aqueous Phase

Directory of Open Access Journals (Sweden)

Magda Kozak

2018-06-01

Full Text Available TiO2/CuxOy nanotube (NT arrays were synthesized using the anodization method in the presence of ethylene glycol and different parameters applied. The presence, morphology, and chemical character of the obtained structures was characterized using a variety of methods—SEM (scanning electron microscopy, XPS (X-ray photoelectron spectroscopy, XRD (X-ray crystallography, PL (photoluminescence, and EDX (energy-dispersive X-ray spectroscopy. A p-n mixed oxide heterojunction of Ti-Cu was created with a proved response to the visible light range and the stable form that were in contact with Ti. TiO2/CuxOy NTs presented the appearance of both Cu2O (mainly and CuO components influencing the dimensions of the NTs (1.1–1.3 µm. Additionally, changes in voltage have been proven to affect the NTs’ length, which reached a value of 3.5 µm for Ti90Cu10_50V. Degradation of phenol in the aqueous phase was observed in 16% of Ti85Cu15_30V after 1 h of visible light irradiation (λ > 420 nm. Scavenger tests for phenol degradation process in presence of NT samples exposed the responsibility of superoxide radicals for degradation of organic compounds in Vis light region. Inactivation of bacteria strains Escherichia coli (E. coli, Bacillus subtilis (B. subtilis, and Clostridium sp. in presence of obtained TiO2/CuxOy NT photocatalysts, and Vis light has been studied showing a great improvement in inactivation efficiency with a response rate of 97% inactivation for E. coli and 98% for Clostridium sp. in 60 min. Evidently, TEM (transmission electron microscopy images confirmed the bacteria cells’ damage.

Content Marketing Plan for Logistics Company : Case: NetLogistic JVM Oy

OpenAIRE

Riabochkina, Elizaveta

2017-01-01

This project aim is to create a Content Marketing Strategy for a Finnish logistics company. The aim of the thesis is to develop an action plan that will help the commissioning company increase sales and gain new customers. The commissioner for the study is NetLogistic JVM Oy. The Company specializes in handling trade of transit and export shipments to Russia and CIS-countries via Finland. The company does not have huge resources to run large campaign, but is looking for ways to reach new...

Eclipse studies of the dwarf nova Oy Carinae in quiescence

International Nuclear Information System (INIS)

Wood, J.H.; Horne, K.; Berriman, G.; Wade, R.A.

1989-01-01

High-speed photometry of OY Car have been obtained which cover 20 eclipses in white light and seven eclipses in UBR. The results show the red dwarf to have a mass of 0.070 + or - 0.002 solar masses and a radius of 0.127 + or - 0.002 solar radii, and the white dwarf to have a temperature of several thousand degrees below 15,000 K. The bright spot is found to have a compact 15,000-K core and a tail that extends along the rim but does not penetrate far into the disk. 31 refs

Establishing a pricing structure for software products : Case study: Viope Solutions Oy

OpenAIRE

Nguyen, Tram

2013-01-01

This thesis is a case study that explores how to establish a pricing structure for software products. The objective is to provide a guideline to establish a pricing structure for Viope Solutions Oy. A new pricing structure is crucial for the company due to recent changes in its business such as internationalisation and new product launches. The literature review introduces five attributes of a pricing structure. They are the unit definition, price determination, price segmentation, versio...

Synthesis and photoluminescence properties of CaSixOy:Tb3+ phosphors prepared using solution-combustion method

CSIR Research Space (South Africa)

Dejene, FB

2011-07-01

Full Text Available Effect of Tb3+ ion concentrations on the structural and persistence luminescence properties of CaSixOy:Tb3+ crystals were evaluated using powders grown by the solution combustion technique. The XRD study indicates the change of phase from CaSiO3...

5S-MENETELMÄN KÄYTTÖÖNOTTO: LUVATA PORI OY

OpenAIRE

Rantanen, Suvi

2015-01-01

Opinnäytetyön aiheena oli 5S-menetelmän käyttöönotto Luvata Pori Oy:n tuotannos-sa. Tutkimuksen lähtökohtana ja ongelmana oli siisteyden ja järjestyksen puute. Ta-voitteena oli aikaansaada valittuun pilottikohteeseen toimivat, siistit ja turvalliset tuotantotilat sekä luoda järjestelmä, jonka avulla ylläpidetään saavutettu taso. Lisäksi tavoiteltiin hukan poistamista ja Luvatan Lean toimintatavan syventämistä. Projekti toteutettiin toimintatutkimuksena syksyn 2015 aikana. Tutkimuksen teor...

Endoscopic inspection of steam turbines

International Nuclear Information System (INIS)

Maliniemi, H.; Muukka, E.

1990-01-01

For over ten years, Imatran Voima Oy (IVO) has developed, complementary inspection methods for steam turbine condition monitoring, which can be applied both during operation and shutdown. One important method used periodically during outages is endoscopic inspection. The inspection is based on the method where the internal parts of the turbine is inspected through access borings with endoscope and where the magnified figures of the internal parts is seen on video screen. To improve inspection assurance, an image-processing based pattern recognition method for cracks has been developed for the endoscopic inspection of turbine blades. It is based on the deduction conditions derived from the crack shape. The computer gives an alarm of a crack detection and prints a simulated image of the crack, which is then checked manually

The development of Facebook marketing utilizing Content marketing. Case: Pirjon Pakari Oy.

OpenAIRE

Lehtikangas, Pauliina

2015-01-01

The purpose of this thesis was to learn how to improve Pirjon Pakari Oy’s brand visibility and overall visibility on Facebook. This was done by trying to add value to the end customer by producing interesting and engaging posts to Pirjon Pakari Oy’s Facebook page. This case study utilized theory from content marketing in attempts to improve the marketing of “Pirjon” Facebook page and therefore a Facebook content marketing strategy was created for Pirjon Pakari Oy. This strategy was implemente...

Training courses at VR-1 reactor

International Nuclear Information System (INIS)

Sklenka, L.; Kropik, M.

2006-01-01

This paper describes one of the main purposes of the VR-1 training reactor utilization - i.e. extensive educational program. The educational program is intended for the training of university students and selected nuclear power plant personnel. The training courses provide them experience in reactor and neutron physics, dosimetry, nuclear safety and operation of nuclear facilities. At present, the training course participants can go through more than 20 standard experimental exercises; particular exercises for special training can be prepared. Approximately 200 university students become familiar with the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. The VR-1 reactor takes also part in Eugene Wigner Course on Reactor Physics Experiments in the framework of European Nuclear Educational Network (ENEN) association. Recently, training courses for Bulgarian research reactor specialists supported by IAEA were carried out. An attractive program including demonstration of reactor operation is prepared also for high school students. Every year, more than 1500 high school students come to visit the reactor, as do many foreigner visitors. (author)

Entering Chinese market for Finnish fashion jewellery company : case: Ninja Finland Oy

OpenAIRE

Wang, Yujue

2014-01-01

As one of the fastest-growing economies in the world, China is expected to become the largest fashion market in the world in a few years. As a result, more and more foreign companies have entered the Chinese market and the market has been more competitive than ever. This requires any fashion company to adopt a strategic development plan when entering the Chinese market. Ninja Finland Oy is a fashion jewellery company which offers a wide range of fashion jewellery and accessories. The comp...

Current status of the Thai Research Reactor (TRR-1/M1)

International Nuclear Information System (INIS)

Chueinta, Siripone; Julanan, Mongkol; Charncanchee, Decharchai

2006-01-01

The first Thai Research Reactor, TRR-1 went critical on 27 October 1962 at the maximum power of 1 MW. It was located at Office of Atoms for Peace (OAP) in Bangkok. Since then, TRR-1 was continuously operated and eventually shut down in 1975. Plate type, high-enriched uranium (HEU) and U 3 O 8 A1 cladding were used as the reactor fuel. Light water was used as moderator and coolant as well. In 1975, because of the problem from fuel supplier and also to supporting the Treaty of Non Proliferation of Nuclear Weapon or NPT, TRR-1 was shut down for modification. The reactor core and control system were disassembled and replaced by TRIGA Mark III. A new core was a hexagonal core shape designed by General Atomics (GA). Afterwards, TRR-1 was officially renamed to the Thai Research Reactor-1/Modification 1 (TRR-1/M1). TRR-1/M1 is a multipurpose swimming pool type reactor with nominal power of 2 MW. The TRR-1/M1 uses uranium enriched at 20% in U-235 (LEU) and ZrH alloy as fuel. Light water is also used as coolant and moderator. At present, the reactor is operating with core No.14. The reactor has been serving for various kinds of utilization namely, radioisotope production, neutron activation analysis, beam experiments and reactor physics experiments. (author)

Integrated production of merchantable wood and wood fuels in industry; Teollisuuden ainespuun ja puupolttoaineen integroitu tuotanto

Energy Technology Data Exchange (ETDEWEB)

Kuvaja, K [Enso Oy, Imatra (Finland). Forest Dept.

1997-12-01

The aim of this project is the economically profitable integrated harvesting of industrial wood and firewood especially in harvesting of small-diameter first thinning wood. The research in 1994 was concentrated on improvement of the quality of the chipping methods based on chain-flail debarking chipping method, and on determination of the possible utilisation targets for the fuel fraction. A reasonably large drum debarking test was also carried out at the industrial scale debarking station of the Enocell Oy. More than 80 000 m{sup 3} of first thinning wood was delivered by Enocell during this project. The quality of wood chips, produced using the chain-flail delimbing method, could be improved in the case of pine nearly to the required quality level, but additional measures are still needed in the case of birch. The fuel fraction deliveries to different points of utilisation was started. The particle size of the fuel fraction appeared to be good after crushing. In 1995 a chain-flail-drum debarking chipping unit was developed to improve and homogenise the quality of chips. (orig.)

Annual report on JEN-1 reactor; Informe periodico del Reactor JEN-1 correspondiente al ano 1971

Energy Technology Data Exchange (ETDEWEB)

Montes, J

1972-07-01

In the annual report on the JEN-1 reactor the main features of the reactor operations and maintenance are described. The reactor has been critical for 1831 hours, what means 65,8% of the total working time. Maintenance and pool water contamination have occupied the rest of the time. The maintenance schedule is shown in detail according to three subjects. The main failures and reactor scrams are also described. The daily maximum values of the water activity are given so as the activity of the air in the reactor hall. (Author)

Cadmium free high efficiency Cu2ZnSn(S,Se4 solar cell with Zn1−xSnxOy buffer layer

Directory of Open Access Journals (Sweden)

Md. Asaduzzaman

2017-06-01

Full Text Available We have investigated the simulation approach of a one-dimensional online simulator named A Device Emulation Program and Tool (ADEPT2.1 and the device performances of a thin film solar cell based on Cu2ZnSn(S,Se4 (CZTSSe absorber have been measured. Initiating with a thin film photovoltaic device structure consisting of n-ZnO:Al/i-ZnO/Zn1-xSnxOy (ZTO/CZTSSe/Mo/SLG stack, a graded space charge region (SCR and an inverted surface layer (ISL were inserted between the buffer and the absorber. The cadmium (Cd free ZTO buffer, a competitive substitute to the CdS buffer, significantly contributes to improve the open-circuit voltage, Voc without deteriorating the short-circuit current density, Jsc. The optimized solar cell performance parameters including Voc, Jsc, fill factor (FF, and efficiency (η were calculated from the current density-voltage curve, also known as J–V characteristic curve. The FF was determined as 73.17%, which in turns, yields a higher energy conversion efficiency of 14.09%.

Tuotteiden ohjeistaminen osana hankintatoimintaa ja tuotetiedonhallintaa : case: Seppälä Oy

OpenAIRE

Heikkonen, Veera

2010-01-01

Tuoteohjeistusten tekeminen on arkipäivää suomalaisissa vaatetusalan yrityksissä. Tuotteiden hankinta ulkomailta on yleistynyt huomattavasti, joka taas on tehnyt tuoteohjeistuksista tärkeitä työkaluja yrityksen toiminnassa. Tuoteohjeistusten avulla suunnittelijan ideat ja ajatukset toteutetaan oikeaksi tuotteeksi. Tämän opinnäytetyön tarkoitus oli kehittää Seppälä Oy:lle yhtenäinen tuoteohjeis-tuspohja, joka on selkeä ja toimiva. Projektin lähtökohtainen tarkoitus on, että Seppälä voi hy...

Electronic states of SiO2-MxOy (MxOy=P205, TiO2 and ZrO2) glasses

Energy Technology Data Exchange (ETDEWEB)

Kowada, Y [Hyogo Univ. of Teacher Education, Hyogo (Japan); Adachi, H [Kyoto Univ. (Japan). Faculty of Engineering; Minami, T [Univ. of Osaka Prefecture, Osaka (Japan). Faculty of Engineering

1993-12-01

Using the sol-gel method the surface of metal and glass substrates can be modified. For example, stainless steel sheets coated with the SiO2-ZrO2 glass films have higher resistance to corrosion and oxidation. The coating films contain high concentration of alkali ions diffusing from the glass substrates. It suggests that the sodium ions are trapped strongly within the coating films and are blocked to further diffuse to the surface. This behavior must be associated with the chemical bonding around the sodium ions in the SiO2-TiO2 and SiO2-ZrO2 films. For better understanding of the chemical bonding in the glasses, the electronic states of the SiO2-MxOy glasses were calculated by means of the DV-Xa cluster method. In this paper, the calculation method is explained, the results are discussed and the conclusion is stated. 17 refs., 6 figs.

Digitaalinen markkinointi pk-yrityksessä inbound-markkinoinnin keinoin CASE: Customer Intelligence Finland Oy

OpenAIRE

Lassila, Anna-Sofia

2016-01-01

Tämän opinnäytetyön tarkoituksena oli tutkia kuinka digitaalista markkinointia kannattaa tehdä inbound-markkinoinnin keinoin. Tutkimuksen ensisijaisena tavoitteena oli löytää tehokkaimmat keinot inbound-markkinoinnin toteuttamiseen. Toisena tavoitteena oli antaa tuloksiin pohjautuen suosituksia digitaalisen markkinoinnin jatkotoimenpiteistä inbound-metodia hyödyntäen. Tämän opinnäytetyön toimeksiantajana toimi Customer Intelligence Finland Oy (CIFI). Tämän opinnäytetyön tutkimusmenetelmän...

Annual report on JEN-1 reactor

International Nuclear Information System (INIS)

Montes, J.

1972-01-01

In the annual report on the JEN-1 reactor the main features of the reactor operations and maintenance are described. The reactor has been critical for 1831 hours, what means 65,8% of the total working time. Maintenance and pool water contamination have occupied the rest of the time. The maintenance schedule is shown in detail according to three subjects. The main failures and reactor scrams are also described. The daily maximum values of the water activity are given so as the activity of the air in the reactor hall. (Author)

Corporate Social Responsibility: A Case Study of BSCI Implementation at Best Friend Group Oy

OpenAIRE

Qi, Yuan

2012-01-01

With the current polarized debate over CSR issues worldwide, ever increasing number of companies believe that incorporating ethical values into the business operation is an attractive option to upgrade the brand value, maintain the competitive advantage and cater for the social demand of various stakeholders. Business Social Compliance Initiative, a division of FTA, serves as a platform to assist companies in achieving the goal. The study was commissioned by Best Friend Group Oy, a medium...

Safety operation of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.

2001-01-01

There are three nuclear research reactors in the Czech Republic in operation now: light water reactor LVR-15, maximum reactor power 10 MW t , owner and operator Nuclear Research Institute Rez; light water zero power reactor LR-0, maximum reactor power 5 kW t , owner and operator Nuclear Research Institute Rez and training reactor VR-1 Sparrow, maximum reactor power 5 kW t , owner and operate Faculty of Nuclear Sciences and Physical Engineering, CTU in Prague. The training reactor VR-1 Vrabec 'Sparrow', operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly it is designed for training the students of Czech universities, preparing the experts for the Czech nuclear programme, as well as for certain research work, and for information programmes in the nuclear programme, as well as for certain research work, and for information programmes in sphere of using the nuclear energy (public relations). (author)

A/B Testing in Improving Conversion on a Website : Case: Sanoma Entertainment Oy

OpenAIRE

Arento, Thomas

2010-01-01

The purpose of this thesis is to study marketing possibilities of improved conversion rates on websites. The study was made for Sanoma Entertainment Oy’s Gaming & Online unit. The main objective was to explore A/B testing as a tool to improve conversion rates by increasing click-through rates. The secondary objective was to test Google Website Optimizer as an A/B testing tool in comparison to current methods of A/B testing in Sanoma Entertainment Oy. The results of this study will be used as ...

Assessing demand for physical objects among marketing agencies : market research for Alphaform RPI Oy

OpenAIRE

Popova, Oxana

2012-01-01

The market for 3D printing services is projected to grow significantly. A service provider of 3D printing and rapid prototyping services, Alphaform RPI Oy recognizes that there are numerous growth opportunities that can be exploited. A market research was initiated by the case company to look for any emerging trends to use physical objects. The study was focused on exploring marketing agencies and their vision on 3D printing and rapid prototyping services. Theoretical framework was built ...

Neste Oy starts the production of extra high viscosity index lubricating oil in Porvoo

International Nuclear Information System (INIS)

Kilander, H.

1997-01-01

Neste Oy is starting the manufacture of basic oil, used in advanced motor lubricants, in Finland. The plant will start the manufacture of the EHVI (Extra High Viscosity) by the end of 1997. The EHVI basic oil is a synthetic-like oil product, suitable for manufacture of high-quality lubricants. In the beginning the production of the basic oil will be about 50 000 tons/a. The investment costs of the plants are 180 million FIM

Markkinoinnin kehittäminen, Verkkomarkkinointi ja sosiaalinen media : JA-KI Muutto Oy

OpenAIRE

Kahanpää, Timo

2015-01-01

Tämän opinnäytetyön tavoitteena oli kehittää ja tehostaa helsinkiläisen muuttoalan yrityksen JA-KI Muutto Oy:n markkinointia verkossa ja siellä nimenomaan sosiaalisessa mediassa. Työn tavoitteena oli löytää ja tuoda esille keinoja ja kehittämisehdotuksia, joiden avulla markkinointia verkossa voitaisiin tehostaa entisestään. Opinnäytetyö tehtiin kehittämistehtävänä ja se jakautuu kahteen osaan: teoriaosaan ja kehittämisosaan. Teoriaosiossa käydään läpi eri lähteiden kautta ensin markkinoin...

Effects of Ni-5%RExOy Composite Additives on Electrochemical Hydrogen Storage Performances of Mg2Ni

Directory of Open Access Journals (Sweden)

ZHANG Guo-fang

2017-11-01

Full Text Available The Ni-5%RExOy (CeO2, La2O3, Eu2O3 as composite additives, Mg2Ni-Ni-5%RExOy composites were prepared by the ball milling method. The effects of different additives on the structure, morphology, electrochemistry and kinetic properties of Mg2Ni alloy were studied systematically. The results show that composite additives can improve the proportion of amorphous and nanocrystalline structure of Mg2Ni alloy. The particle size is homogeneous but the agglomeration is observed in the sample with Ni-5%CeO2 additives. The composites with additives show higher maximum discharge capacity and better cycle stabilities. All of these three kinds of composite additives can improve the kinetic properties of the composites effectively, including optimizing the charge-transfer ability, the reversibility of the electrochemical reaction on the alloy surface, and enhancing the diffusion coefficients of H atoms in the bulk of alloy. Among these three kinds of additives, Ni-5%CeO2 additive shows the best catalysis effect on promoting the kinetic properties of the composites.

Integrated production of merchantable wood and wood fuels in industry; Teollisuuden ainespuun ja puupoltto-aineen integroitu tuotanto

Energy Technology Data Exchange (ETDEWEB)

Kuvaja, K [Enso-Gutzeit Oy, Imatra (Finland). Forest Dept.

1997-12-31

The aim of this project is the economically profitable integrated harvesting of industrial wood and firewood especially in harvesting of small-diameter first thinning wood. The research in 1994 was concentrated on improvement of the quality of the chipping methods based on chain-flail debarking chipping method, and on determination of the possible utilization targets for the fuel fraction. A reasonably large drum debarking test was also carried out at the industrial scale debarking station of the Enocell Oy. More than 80 000 m{sup 3} of first thinning wood was delivered by Enocell during this project. The quality of wood chips, produced using the chain-flail delimbing method, could be improved in the case of pine nearly to the required quality level, but additional measures are still needed in the case of birch. The fuel fraction deliveries to different points of utilization was started. The particle size of the fuel fraction appeared to be good after crushing. In 1995 a chain-flail-dry drum debarking chipping unit was developed to improve and homogenize the quality of chips

Integrated production of merchantable wood and wood fuels in industry; Teollisuuden ainespuun ja puupoltto-aineen integroitu tuotanto

Energy Technology Data Exchange (ETDEWEB)

Kuvaja, K. [Enso-Gutzeit Oy, Imatra (Finland). Forest Dept.

1996-12-31

The aim of this project is the economically profitable integrated harvesting of industrial wood and firewood especially in harvesting of small-diameter first thinning wood. The research in 1994 was concentrated on improvement of the quality of the chipping methods based on chain-flail debarking chipping method, and on determination of the possible utilization targets for the fuel fraction. A reasonably large drum debarking test was also carried out at the industrial scale debarking station of the Enocell Oy. More than 80 000 m{sup 3} of first thinning wood was delivered by Enocell during this project. The quality of wood chips, produced using the chain-flail delimbing method, could be improved in the case of pine nearly to the required quality level, but additional measures are still needed in the case of birch. The fuel fraction deliveries to different points of utilization was started. The particle size of the fuel fraction appeared to be good after crushing. In 1995 a chain-flail-dry drum debarking chipping unit was developed to improve and homogenize the quality of chips

Extensive utilization of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, Karel; Sklenka, Lubomir

2003-01-01

Full text: The training reactor VR-1 Vrabec ('Sparrow'), operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly, it is designed and operated for training of students from Czech universities, preparing of experts for the Czech nuclear programme, as well as for certain research and development work, and for information programmes in the sphere of non-military nuclear energy use (public relation). The VR-1 training reactor is a pool-type light-water reactor based on enriched uranium with maximum thermal power 1kWth and short time period up to 5kW th . The moderator of neutrons is light demineralized water (H 2 O) that is also used as a reflector, a biological shielding, and a coolant. Heat is removed from the core with natural convection. The reactor core contains 14 to 18 fuel assemblies IRT-3M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The core is accommodated in a cylindrical stainless steel vessel - pool, which is filled with water. UR-70 control rods serve the reactor control and safe shutdown. Training of the VR-1 reactor provides students with experience in reactor and neutron physics, dosimetry, nuclear safety, and nuclear installation operation. Students from technical universities and from natural sciences universities come to the reactor for training. Approximately 200 university students are introduced to the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. Practical Course on Reactor Physics in Framework of European Nuclear Engineering Network has been newly introduced. Currently, students can try out more than 20 experimental exercises. Further training courses have been included

Spin-Glass Transition and Giant Paramagnetism in Heavily Hole-Doped Bi2Sr2Co2Oy

Science.gov (United States)

Hsu, Hung Chang; Lee, Wei-Li; Lin, Jiunn-Yuan; Young, Ben-Li; Kung, Hsiang-Hsi; Huang, Jian; Chou, Fang Cheng

2014-02-01

Hole-doped single crystals of misfit-layered cobaltate Bi2-xPbxSr2-zCo2Oy (x = 0-0.61, y = 8.28-8.62, and z = 0.01-0.22) have been successfully grown using the optical floating-zone method. Heavier hole doping has been achieved through both Pb substitution in the Bi site and the more effective Sr vacancy formation. The Co4+ : Co3+ ratio can be raised significantly from its original ˜1 : 1 to 4.5 : 1, as confirmed by iodometric titration. A spin-glass transition temperature of Tg ˜ 70 K is confirmed by ac susceptibility measurement when the Co4+ : Co3+ ratio becomes higher than 2 : 1, presumably owing to the significantly increased probability of triangular geometrical frustration among antiferromagnetically coupled localized Co4+ spins.

Ostotoiminnan laadunvarmistus ja toiminnanohjauksen kehittäminen Mantsinen Group Ltd Oy:ssä

OpenAIRE

Hiltunen, Jarmo

2012-01-01

Opinnäytetyön aiheena oli ostotoiminnan laadunvarmistuksen ja toiminnanohjauksen kehittäminen Mantsinen Group Ltd Oy:ssä. Työssä on perehdytty erityisesti niihin ostotoiminnan laadun kehittämisen haasteisiin mitkä liittyvät alihankintaostamisen osa-alueeseen. Opinnäytetyön päätavoitteena oli luoda työkaluja hankinnan laadun jatkuvan parantamisen avuksi. Lisäksi tavoitteena oli perehtyä hankintojen mittaamisen teoriaan. Opinnäytetyön tutkimusmenetelmänä on käytetty käytännön tietoa ostam...

Ympäristöjärjestelmän rakentaminen : Case: Inno Interior Oy

OpenAIRE

Pirinen, Liisa

2009-01-01

Tavoitteena oli rakentaa huonekalualalla toimivalle Inno Interior Oy:lle, joka valmistuttaa tuotteet alihankkijoilla, sertifiointikelpoinen ympäristönhallintajärjestelmä. Yrityksellä ei ollut ympäristösertifikaattia. Asiakkaat vaativat yritykseltä ympäristöasioiden hoitamisen tason osoittamista. Ympäristöhallintajärjestelmän rakentaminen ja sertifiointi oli sopivin ratkaisu ongelmaan. Ympäristöjärjestelmän rakentamisen lähtökohtana olivat toiminnan aiheuttamat ympäristö-vaikutukset ja...

Moving ring reactor 'Karin-1'

International Nuclear Information System (INIS)

1983-12-01

The conceptual design of a moving ring reactor ''Karin-1'' has been carried out to advance fusion system design, to clarify the research and development problems, and to decide their priority. In order to attain these objectives, a D-T reactor with tritium breeding blanket is designed, a commercial reactor with net power output of 500 MWe is designed, the compatibility of plasma physics with fusion engineering is demonstrated, and some other guideline is indicated. A moving ring reactor is composed mainly of three parts. In the first formation section, a plasma ring is formed and heated up to ignition temperature. The plasma ring of compact torus is transported from the formation section through the next burning section to generate fusion power. Then the plasma ring moves into the last recovery section, and the energy and particles of the plasma ring are recovered. The outline of a moving ring reactor ''Karin-1'' is described. As a candidate material for the first wall, SiC was adopted to reduce the MHD effect and to minimize the interaction with neutrons and charged particles. The thin metal lining was applied to the SiC surface to solve the problem of the compatibility with lithium blanket. Plasma physics, the engineering aspect and the items of research and development are described. (Kako, I.)

Biomass CFB gasifier connected to a 350 MW{sub t}h steam boiler fired with coal and natural gas - THERMIE demonstration project in Lahti in Finland

Energy Technology Data Exchange (ETDEWEB)

Palonen, J. [Foster Wheeler Energia Oy, Varkaus (Finland). Varkaus Global New Products

1997-12-31

The successful experience in developing the advanced Foster Wheeler Energi Oy`s (former Ahlstroem Pyropower) Circulating Fluidized Bed combustion system subsequently led to the development of the CFB gasification technology in the early 1980s. The driving force for the developing work was the dramatic increase in oil price during the oil crises. The primary advantage of CFB gasification technology is that the it enables the substitution of expensive fuels e.g. oil or gas with cheap solid fuels. These cheap fuels are typically different types of waste woods, bark or other biofuels. In the CFB gasifier these solid fuels are converted to gaseous fuel which can be used instead of other expensive fuels. In some cases this also solves a waste disposal problem, providing a secondary economic and environmental benefit. Foster Wheeler Energia Oy has supplied four commercial scale atmospheric CFB gasifiers in the mid 80s to the pulp and paper industry with capacities from 17 to 35 MW based on fuel input. These applications utilize waste wood as feedstock and the units are still successfully operation today. Lahden Laempoevoima Oy is a Finnish power company producing power and district heat for the city of Lahti. The company is 50 % owned by the city of Lahti and 50 % by Imatran Voima Oy, which is the largest utility power company in Finland. Lahden Laempoevoima Oy operates the Kymijaervi power plant locating nearby the city of Lahti in Southern Finland. To keep the energy prices as low as possible, Lahden Laempoevoima is continuously looking for the most economical fuel sources, and simultaneously, trying to improve the environmental acceptability of the energy production. At the moment, about 300 GWh/a different type of biofuels and refuse fuels are available in the Lahti area. On an annual basis, the available amount of biofuels and refuse fuels is enough to substitute for about 15 % of the fuels burned in the main boiler equalling max 30 % of coal. The aim in this Lahden

Biomass CFB gasifier connected to a 350 MW{sub t}h steam boiler fired with coal and natural gas - THERMIE demonstration project in Lahti in Finland

Energy Technology Data Exchange (ETDEWEB)

Palonen, J [Foster Wheeler Energia Oy, Varkaus (Finland). Varkaus Global New Products

1998-12-31

The successful experience in developing the advanced Foster Wheeler Energi Oy`s (former Ahlstroem Pyropower) Circulating Fluidized Bed combustion system subsequently led to the development of the CFB gasification technology in the early 1980s. The driving force for the developing work was the dramatic increase in oil price during the oil crises. The primary advantage of CFB gasification technology is that the it enables the substitution of expensive fuels e.g. oil or gas with cheap solid fuels. These cheap fuels are typically different types of waste woods, bark or other biofuels. In the CFB gasifier these solid fuels are converted to gaseous fuel which can be used instead of other expensive fuels. In some cases this also solves a waste disposal problem, providing a secondary economic and environmental benefit. Foster Wheeler Energia Oy has supplied four commercial scale atmospheric CFB gasifiers in the mid 80s to the pulp and paper industry with capacities from 17 to 35 MW based on fuel input. These applications utilize waste wood as feedstock and the units are still successfully operation today. Lahden Laempoevoima Oy is a Finnish power company producing power and district heat for the city of Lahti. The company is 50 % owned by the city of Lahti and 50 % by Imatran Voima Oy, which is the largest utility power company in Finland. Lahden Laempoevoima Oy operates the Kymijaervi power plant locating nearby the city of Lahti in Southern Finland. To keep the energy prices as low as possible, Lahden Laempoevoima is continuously looking for the most economical fuel sources, and simultaneously, trying to improve the environmental acceptability of the energy production. At the moment, about 300 GWh/a different type of biofuels and refuse fuels are available in the Lahti area. On an annual basis, the available amount of biofuels and refuse fuels is enough to substitute for about 15 % of the fuels burned in the main boiler equalling max 30 % of coal. The aim in this Lahden

The determination of neutron energy spectrum in reactor core C1 of reactor VR-1 Sparrow

Energy Technology Data Exchange (ETDEWEB)

Vins, M. [Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University, V Holesovickach 2, 180 00 Prague 8 (Czech Republic)], E-mail: vinsmiro@seznam.cz

2008-07-15

This contribution overviews neutron spectrum measurement, which was done on training reactor VR-1 Sparrow with a new nuclear fuel. Former nuclear fuel IRT-3M was changed for current nuclear fuel IRT-4M with lower enrichment of 235U (enrichment was reduced from former 36% to 20%) in terms of Reduced Enrichment for Research and Test Reactors (RERTR) Program. Neutron spectrum measurement was obtained by irradiation of activation foils at the end of pipe of rabit system and consecutive deconvolution of obtained saturated activities. Deconvolution was performed by computer iterative code SAND-II with 620 groups' structure. All gamma measurements were performed on Canberra HPGe. Activation foils were chosen according physical and nuclear parameters from the set of certificated foils. The Resulting differential flux at the end of pipe of rabit system agreed well with typical spectrum of light water reactor. Measurement of neutron spectrum has brought better knowledge about new reactor core C1 and improved methodology of activation measurement. (author)

Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

International Nuclear Information System (INIS)

Henry, A.F.

1980-01-01

Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

Imaging the risks - risking the image: Social impact assessment of the final disposal facility

International Nuclear Information System (INIS)

Avolahti, J.; Vira, J.

1999-01-01

Preparations for the final disposal of spent nuclear fuel in Finland started about twenty years ago. At present the work is carried out by Posiva Oy, which in 1996 took over the programme managed earlier by Teollisuuden Voima Oy, one of the country's nuclear power companies. From 1996 on the preparations have been made for all the spent fuel from Finnish nuclear power stations. The site for the final disposal facility will be selected among four alternatives by the end of 2000 and - assuming that the technical approach proposed by Posiva is accepted by the Government and the Parliament - the construction of the repository will start in the 2010s. The disposal operations are planned to be started in 2020. The alternative four sites have gone through a systematic site selection process based on geologic siting criteria and on environmental and cultural considerations. One of the objectives of the process was to avoid inhabited areas, agricultural fields, valuable groundwater or preservation areas as well as areas which might draw interest as regards the potential for ore deposits. The idea was that the field investigations and later the possible disposal facility should not cause any harm to local people. Two of the candidate sites are at present nuclear power plant sites situated at the coast, the two other candidates are inland sites with no nuclear activities. The geologic siting investigations were started in 1987. Interim assessments of the results so far have been made in 1992 and 1996 and a final report of all the investigations will be published before the end of 2000. The present view is that all four candidates are geologically suitable for siting the repository. Posiva's EIA for the final disposal of spent fuel in Finland is nearing completion. A considerable effort was made to involve local groups and individuals in the assessment process. Yet the participation remained limited and consisted mainly of active opponents of the project and of those who were

Imaging the risks - risking the image: Social impact assessment of the final disposal facility

Energy Technology Data Exchange (ETDEWEB)

Avolahti, J.; Vira, J. [Posiva Oy, Helsinki (Finland)

1999-12-01

Preparations for the final disposal of spent nuclear fuel in Finland started about twenty years ago. At present the work is carried out by Posiva Oy, which in 1996 took over the programme managed earlier by Teollisuuden Voima Oy, one of the country's nuclear power companies. From 1996 on the preparations have been made for all the spent fuel from Finnish nuclear power stations. The site for the final disposal facility will be selected among four alternatives by the end of 2000 and - assuming that the technical approach proposed by Posiva is accepted by the Government and the Parliament - the construction of the repository will start in the 2010s. The disposal operations are planned to be started in 2020. The alternative four sites have gone through a systematic site selection process based on geologic siting criteria and on environmental and cultural considerations. One of the objectives of the process was to avoid inhabited areas, agricultural fields, valuable groundwater or preservation areas as well as areas which might draw interest as regards the potential for ore deposits. The idea was that the field investigations and later the possible disposal facility should not cause any harm to local people. Two of the candidate sites are at present nuclear power plant sites situated at the coast, the two other candidates are inland sites with no nuclear activities. The geologic siting investigations were started in 1987. Interim assessments of the results so far have been made in 1992 and 1996 and a final report of all the investigations will be published before the end of 2000. The present view is that all four candidates are geologically suitable for siting the repository. Posiva's EIA for the final disposal of spent fuel in Finland is nearing completion. A considerable effort was made to involve local groups and individuals in the assessment process. Yet the participation remained limited and consisted mainly of active opponents of the project and of those

Occupational analysis for the Angra-1 reactor

International Nuclear Information System (INIS)

Moraes, A.

1991-01-01

Due to several modifications which were imposed to its time schedule during construction, the Angra-1 reactor did not enter to the grid in 1982 as it was initially foreseen. These modifications occurred due to an unforeseen scenario that was verified in steam generators (serie D-3, Westinghouse) of power stations with similar configurations which had been installed in other countries such as Ringhals-3 (Sweden), Almaraz-1 (Spain) and McGuine-1 (USA). So, among the main events that occurred in the Angra-1 reactor, which were of interest from the point of view of radiation protection, it could be pointed out the personnel monitoring, and the occupational exposure measurements at different reactor power, during the reactor fueling and during modification and tests performed at the steam generators and at ducts of the primary coolant circuit. (author)

Internationalization Strategies for Multinational Companies (MNCs) : In the case of KWH Mirka Oy to Ethiopia

OpenAIRE

Yigzaw, Tamirat

2015-01-01

This thesis is done for the fulfilment of Masters of Business Administration (MBA) degree program in Business Management and Entrepreneurship at Häme University of Applied Sciences (HAMK). The main focus of the study is internationalization of companies to a new market as a development task for the company. The commissioner of the thesis is Mirka Oy, a Finnish multinational company. The purpose of the thesis was to study factors that should be considered in internationalization strategies...

Environmentally friendly, high-performance generation

International Nuclear Information System (INIS)

Kalmari, A.

2003-01-01

The project developer, owner, and operator of the new 45 MWth BFB-based cogeneration plant in Iisalmi is Termia Oy, part of the Atro Group (formerly Savon Voima Oy). Fired on peat and wood waste and handed over to the customer in November 2002, the plant's electrical output is sold to the parent company and heat locally to customers in Iisalmi. When the construction decision was made, one of the main objectives was to utilise as high a level of indigenous fuels (peat and biomass) as possible, at a high level of efficiency. An environmental impact analysis was carried out, taking into account the impact of various fuels and emissions in terms of combustion and logistics. One main benefit of the type of plant ultimately selected was that the bulk of the fuel can be supplied from the surrounding area. This is very important in terms of fuel supply security and local employment. The government provided a EUR 2.7 million grant for the project, equivalent to 13% of the total EUR 21 million investment budget. Before the plant was built, Termia used approximately 95 GWh of indigenous fuels annually. Today, this figure is 220 GWh. The main fuel used is milled peat. Up to 30% green chips from logging residues can be used. Recycled waste fuel can cover up to 3% of the total fuel requirement

Inter- and intragranular properties of bismuth calcium strontium copper oxide (Bi2CaSr2Cu2Oy) superconductors

NARCIS (Netherlands)

Emmen, J.H.P.M.; Brabers, V.A.M.; Steen, van der C.; Dalderop, J.H.J.; Lenczowski, S.K.J.; Jonge, de W.J.M.

1989-01-01

The granular behaviour of sintered bulk Bi2CaSr2Cu2Oy superconductor is investigated by resistivity and ¿ac measurements. The observed temperature and magnetic field dependence is discussed within the framework of a granular model. The frequency dependence of the intragranular losses leads to a flux

Reactor operations at SAFARI-1

International Nuclear Information System (INIS)

Vlok, J.W.H.

2003-01-01

A vigorous commercial programme of isotope production and other radiation services has been followed by the SAFARI-1 research reactor over the past ten years - superimposed on the original purpose of the reactor to provide a basic tool for nuclear research, development and education to the country at an institutional level. A combination of the binding nature of the resulting contractual obligations and tighter regulatory control has demanded an equally vigorous programme of upgrading, replacement and renovation of many systems in order to improve the safety and reliability of the reactor. Not least among these changes is the more effective training and deployment of operations personnel that has been necessitated as the operational demands on the reactor evolved from five days per week to twenty four hours per day, seven days per week, with more than 300 days per year at full power. This paper briefly sketches the operational history of SAFARI-1 and then focuses on the training and structuring currently in place to meet the operational needs. There is a detailed step-by-step look at the operator?s career plan and pre-defined milestones. Shift work, especially the shift cycle, has a negative influence on the operator's career path development, especially due to his unavailability for training. Methods utilised to minimise this influence are presented. The increase of responsibilities regarding the operation of the reactor, ancillaries and experimental facilities as the operator progresses with his career are discussed. (author)

Olkiluoto surface hydrological modelling: Update 2012 including salt transport modelling

International Nuclear Information System (INIS)

Karvonen, T.

2013-11-01

Posiva Oy is responsible for implementing a final disposal program for spent nuclear fuel of its owners Teollisuuden Voima Oyj and Fortum Power and Heat Oy. The spent nuclear fuel is planned to be disposed at a depth of about 400-450 meters in the crystalline bedrock at the Olkiluoto site. Leakages located at or close to spent fuel repository may give rise to the upconing of deep highly saline groundwater and this is a concern with regard to the performance of the tunnel backfill material after the closure of the tunnels. Therefore a salt transport sub-model was added to the Olkiluoto surface hydrological model (SHYD). The other improvements include update of the particle tracking algorithm and possibility to estimate the influence of open drillholes in a case where overpressure in inflatable packers decreases causing a hydraulic short-circuit between hydrogeological zones HZ19 and HZ20 along the drillhole. Four new hydrogeological zones HZ056, HZ146, BFZ100 and HZ039 were added to the model. In addition, zones HZ20A and HZ20B intersect with each other in the new structure model, which influences salinity upconing caused by leakages in shafts. The aim of the modelling of long-term influence of ONKALO, shafts and repository tunnels provide computational results that can be used to suggest limits for allowed leakages. The model input data included all the existing leakages into ONKALO (35-38 l/min) and shafts in the present day conditions. The influence of shafts was computed using eight different values for total shaft leakage: 5, 11, 20, 30, 40, 50, 60 and 70 l/min. The selection of the leakage criteria for shafts was influenced by the fact that upconing of saline water increases TDS-values close to the repository areas although HZ20B does not intersect any deposition tunnels. The total limit for all leakages was suggested to be 120 l/min. The limit for HZ20 zones was proposed to be 40 l/min: about 5 l/min the present day leakages to access tunnel, 25 l/min from

Olkiluoto surface hydrological modelling: Update 2012 including salt transport modelling

Energy Technology Data Exchange (ETDEWEB)

Karvonen, T. [WaterHope, Helsinki (Finland)

2013-11-15

Posiva Oy is responsible for implementing a final disposal program for spent nuclear fuel of its owners Teollisuuden Voima Oyj and Fortum Power and Heat Oy. The spent nuclear fuel is planned to be disposed at a depth of about 400-450 meters in the crystalline bedrock at the Olkiluoto site. Leakages located at or close to spent fuel repository may give rise to the upconing of deep highly saline groundwater and this is a concern with regard to the performance of the tunnel backfill material after the closure of the tunnels. Therefore a salt transport sub-model was added to the Olkiluoto surface hydrological model (SHYD). The other improvements include update of the particle tracking algorithm and possibility to estimate the influence of open drillholes in a case where overpressure in inflatable packers decreases causing a hydraulic short-circuit between hydrogeological zones HZ19 and HZ20 along the drillhole. Four new hydrogeological zones HZ056, HZ146, BFZ100 and HZ039 were added to the model. In addition, zones HZ20A and HZ20B intersect with each other in the new structure model, which influences salinity upconing caused by leakages in shafts. The aim of the modelling of long-term influence of ONKALO, shafts and repository tunnels provide computational results that can be used to suggest limits for allowed leakages. The model input data included all the existing leakages into ONKALO (35-38 l/min) and shafts in the present day conditions. The influence of shafts was computed using eight different values for total shaft leakage: 5, 11, 20, 30, 40, 50, 60 and 70 l/min. The selection of the leakage criteria for shafts was influenced by the fact that upconing of saline water increases TDS-values close to the repository areas although HZ20B does not intersect any deposition tunnels. The total limit for all leakages was suggested to be 120 l/min. The limit for HZ20 zones was proposed to be 40 l/min: about 5 l/min the present day leakages to access tunnel, 25 l/min from

Measurement of reinforcement corrosion in concrete structures. Betonirakenteiden raudoituksen korroosion tutkiminen

Energy Technology Data Exchange (ETDEWEB)

Meuronen, A

1992-03-01

Ageing and aggressive enviromental conditions of concrete structures will result in deterioration of concrete and corrosion of steel in concrete. Corrosion of steel will in time result in the end of the service life or expensive renovations, unless corrosion of steel is noticed and renovated in time. Corrosion of steel in concrete can be found out by the present corrosion measurement methods, so that renovation can be started in right time. The report presents mainly on the basis of the literature references the following corrosion measurement methods: polarisation resistance, AC-impedance, electrical resistance probe, electrochemical noice and half-cell potential mapping. The half-cell potential mapping will be presented more precisely than the other corrosion measurement methods, for the potential mapping is the most used method. Concrete and Soils Laboratory of Imatran Voima Oy uses in the measurement of reinforcement corrosion the English, eight channel potential measuring equipment.

Measurement of reinforcement corrosion in concrete structures; Betonirakenteiden raudoituksen korroosion tutkiminen

Energy Technology Data Exchange (ETDEWEB)

Meuronen, A

1992-03-01

Ageing and aggressive enviromental conditions of concrete structures will result in deterioration of concrete and corrosion of steel in concrete. Corrosion of steel will in time result in the end of the service life or expensive renovations, unless corrosion of steel is noticed and renovated in time. Corrosion of steel in concrete can be found out by the present corrosion measurement methods, so that renovation can be started in right time. The report presents mainly on the basis of the literature references the following corrosion measurement methods: polarisation resistance, AC-impedance, electrical resistance probe, electrochemical noice and half-cell potential mapping. The half-cell potential mapping will be presented more precisely than the other corrosion measurement methods, for the potential mapping is the most used method. Concrete and Soils Laboratory of Imatran Voima Oy uses in the measurement of reinforcement corrosion the English, eight channel potential measuring equipment.

Extensive utilization of training reactor VR-1

International Nuclear Information System (INIS)

Karel, Matejka; Lubomir, Sklenka

2005-01-01

This paper describes one of the main purposes of the VR-1 training reactor utilisation - i.e. extensive educational programme. The educational programme is intended for the training of university students (all technical universities in Czech Republic) and selected nuclear power plant personnel. At the present, students can go through more than 20 different experimental exercises. An attractive programme including demonstration of reactor operation is prepared also for high school students. Moreover, research and development works and information programmes proceed at the VR-1 reactor as well

Ecosystem characterization strategy at a repository site - Olkiluoto as a case study

Energy Technology Data Exchange (ETDEWEB)

Pere, Tuomas [Posiva Oy, Olkiluoto, 27160 Eurajoki (Finland); Kangasniemi, Ville [Environmental Research and Assessment EnviroCase, Ltd., Hallituskatu 1 D 4, 28100 Pori (Finland); Lahdenperae, Anne-Maj [Saanio and Riekkola Oy, Laulukuja 4, 00420 Helsinki (Finland); Aro, Lasse [Finnish Forest Research Institute, Kaironiementie 15, 39700 Parkano (Finland)

2014-07-01

Posiva Oy is constructing an underground research facility ONKALO in Olkiluoto, located in the municipality of Eurajoki, Finland. This is part of the plan for final disposal of spent nuclear fuel produced by Posiva's owners: Teollisuuden Voima Oyj and Fortum Power and Heat Oyj. Posiva has applied for construction license for an underground repository, which is planned to start its operation around the year 2020. The final disposal of high-level radioactive waste poses questions of long-term safety and possible processes of radionuclide release in the EBS (Engineered Barrier System) and the geosphere are also modelled as well as possible transport routes in the bedrock. Posiva has also established a monitoring program for the environment and is also conducting modelling of the surface environment and biosphere in Olkiluoto and the surrounding reference area. These serve the purpose of both, site description and modelling of the transport and accumulation of possible radionuclide releases in the surface environment and biosphere. The process of modelling used by Posiva requires the division of the surface environment and biosphere into several categories. In Posiva's classification, ecosystems are divided to two categories: terrestrial and aquatic with terrestrial divided to forests and agricultural areas. These categories are further divided to ecosystem types which include: lake, river, forest, cropland and sea (with coastal sea as a separate type). These types are even further divided to 14 ecosystem sub-types and behind these sub-types, a total of 24 biotopes exist. Soil and sediment types are also classified to 7 classes. The methodology behind the selection of these biotopes and their connection to the modelling of radionuclide transport in the surface environment is further described in the text. Some of the ecosystem types and biotopes are absent in present-day Olkiluoto area, which necessitates the use of reference targets, such as lakes, rivers

Signs of growth in the industry

International Nuclear Information System (INIS)

Taipale, Tellervo

2002-01-01

Full scale of methods in use - long-term work is the basis. Long-term work in communication has been proved to be an excellent basis for a nuclear power company. Teollisuuden Voima Oy (TVO), which has been producing electricity by nuclear power for the Finnish society for 23 years, bears its responsibilities for environmental issues and as member of society. Maintaining good relations to the local municipalities and reporters is one of our strengths. Nuclear power is a way to produce electricity in an environmentally friendly, safe and economical way. TVO, as a modem nuclear power company, acknowledges its responsibilities for the environment and the entire society. In dealing with these responsibilities, a culture of effective, open and honest communication is crucial. The concept of our communication work was already laid down in the 70's We do our best to inform our neighbours and interest groups openly about all that happens at Olkiluoto NPP. We do not only tell the good news, we also tell if there are any problems, e.g. in the production. We apply several different methods to allow everyone to choose their favourite way of finding the information they want. We produce annual publications and videos, organise visits to the plant, participate in fairs and have an up-to-date www-site. A lot of information is available and the doors are open for visitors. Annually, we produce almost 60 publications, e.g. magazines, newspapers, environmental and economical reports and different kinds of brochures. A lot of people visit Olkiluoto NPP - we receive about 16,000 guests each year. We have four basic arguments in our messages to promote the new NPP unit: it covers additional electricity demand and replaces old fossil-fuel power plants, it enables Finland to meet the Kyoto commitments, it secures a stable and predictable electricity price and reduces the dependency on imported electricity. All these messages are included in the printing materials and www-sites, as well as

Stability analysis of the Ghana Research Reactor-1 (GHARR-1)

International Nuclear Information System (INIS)

Della, R.; Alhassan, E.; Adoo, N.A.; Bansah, C.Y.; Nyarko, B.J.B.; Akaho, E.H.K.

2013-01-01

Highlights: • We developed a theoretical model to study the stability of the Ghana Research Reactor-1. • The neutronics transfer function was described by the point kinetics model for a single group of delayed neutrons. • The thermal hydraulics transfer function was based on the modified lumped parameter concept. • A computer code, RESA (REactor Stability Analysis) was developed. • Results show that the closed-loop transfer function was stable and well damped for variable operating power levels. - Abstract: A theoretical model has been developed to study the stability of the Ghana Research Reactor one (GHARR-1). The closed-loop transfer function of GHARR-1 was established based on the model, which involved the neutronics and the thermal hydraulics transfer functions. The reactor kinetics was described by the point kinetics model for a single group of delayed neutrons, whilst the thermal hydraulics transfer function was based on the modified lumped parameter concept. The inherent internal feedback effect due to the fuel and the coolant was represented by the fuel temperature coefficient and the moderator temperature coefficient respectively. A computer code, RESA (REactor Stability Analysis), entirely in Java was developed based on the model for systems analysis. Stability analysis of the open-loop transfer function of GHARR-1 based on the Nyquist criterion and Bode diagrams using RESA, has shown that the closed-loop transfer function was marginally stable for variable operating power levels. The relative stability margins of GHARR-1 were also identified

Array-level stability enhancement of 50 nm AlxOy ReRAM

Science.gov (United States)

Iwasaki, Tomoko Ogura; Ning, Sheyang; Yamazawa, Hiroki; Takeuchi, Ken

2015-12-01

ReRAM's low voltage and low current programmability are attractive features to solve the scaling issues of conventional floating gate Flash. However, read instability in ReRAM is a critical issue, due to random telegraph noise (RTN), sensitivity to disturb and retention. In this work, the array-level characteristics of read stability in 50 nm AlxOy ReRAM are investigated and a circuit technique to improve stability is proposed and evaluated. First, in order to quantitatively assess memory cell stability, a method of stability characterization is defined. Next, based on this methodology, a proposal to improve read stability, called ;stability check loop; is evaluated. The stability check loop is a stability verification procedure, by which, instability improvement of 7×, and read error rate improvement of 40% are obtained.

Mixed pinning landscape in nanoparticle-introduced YGdBa2Cu3Oy films grown by metal organic deposition

Science.gov (United States)

Miura, M.; Maiorov, B.; Baily, S. A.; Haberkorn, N.; Willis, J. O.; Marken, K.; Izumi, T.; Shiohara, Y.; Civale, L.

2011-05-01

We study the field (H) and temperature (T) dependence of the critical current density (Jc) and irreversibility field (Hirr) at different field orientations in Y0.77Gd0.23Ba2Cu3Oy with randomly distributed BaZrO3 nanoparticles (YGdBCO+BZO) and YBa2Cu3Oy (YBCO) films. Both MOD films have large RE2Cu2O5 (225) nanoparticles (˜80 nm in diameter) and a high density of twin boundaries (TB). In addition, YGdBCO+BZO films have a high density of BZO nanoparticles (˜25 nm in diameter). At high temperatures (T > 40 K), the superconducting properties, such as Jc, Hirr, and flux creep rates, are greatly affected by the BZO nanoparticles, while at low temperatures the superconducting properties of both the YBCO and YGdBCO+BZO films show similar field and temperature dependencies. In particular, while the Jc of YBCO films follow a power-law dependence (∝H-α) at all measured T, this dependence is only followed at low T for YGdBCO+BZO films. As a function of T, the YGdBCO+BZO film shows Jc(T,0.01T)~[1-(T/Tc)2]n with n ˜ 1.24 ± 0.05, which points to “δTc pinning.” We analyze the role of different types of defects in the different temperature regimes and find that the strong pinning of the BZO nanoparticles yields a higher Hirr and improved Jc along the c axis and at intermediate orientations at high T. The mixed pinning landscapes due to the presence of disorder of various dimensionalities have an important role in the improvement of in-field properties.

Estimation of radioactivity in structural materials of ETRR-1 reactor

Energy Technology Data Exchange (ETDEWEB)

Imam, M [National Center for Nuclear Safety and Radiation Control Atomic Energy Authority, Cairo (Egypt)

1997-12-31

Precise knowledge of the thermal neutron flux in the different structural materials of a reactor is necessary to estimate the radioactive inventory in these materials that are needed in any decommissioning study of the reactor. ETRR-1 is a research reactor that went critical on 2/1691. In spite of this long age of the reactor, the effective operation time of this reactor is very short since the reactor was shutdown for long periods. Because of this long age one may think of reactor decommissioning. For this purpose, the radioactivity of the reactor structural materials was estimated. Apart from the reactor core, the important structural materials in the ETRR-1 are the reactor tank, shielding concrete, and the graphite thermal column. The thermal neutron flux was determined by the monte Carlo method in these materials and the isotope inventory and the radioactivity were calculated by the international code ORIGEN-JR. 1 fig.

Olkiluoto 1 and 2 - Plant efficiency improvement and lifetime extension-project (PELE) implemented during outages 2010 and 2011

Energy Technology Data Exchange (ETDEWEB)

Kosonen, M.; Hakola, M. [Teollisuuden Voima Oyj, F- 27160 Eurajoki (Finland)

2012-07-01

Teollisuuden Voima Oyj (TVO) is a non-listed public company founded in 1969 to produce electricity for its stakeholders. TVO is the operator of the Olkiluoto nuclear power plant. TVO follows the principle of continuous improvement in the operation and maintenance of the Olkiluoto plant units. The PELE project (Plant Efficiency Improvement and Lifetime Extension), mainly completed during the annual outages in 2010 and 2011, and forms one part of the systematic development of Olkiluoto units. TVO maintains a long-term development program that aims at systematically modernizing the plant unit systems and equipment based on the latest technology. According to the program, the Olkiluoto 1 and Olkiluoto 2 plant units are constantly renovated with the intention of keeping them safe and reliable, The aim of the modernization projects is to improve the safety, reliability, and performance of the plant units. PELE project at Olkiluoto 1 was done in 2010 and at Olkiluoto 2 in 2011. The outage length of Olkiluoto 1 was 26 d 12 h 4 min and Olkiluoto 2 outage length was 28 d 23 h 46 min. (Normal service-outage is about 14 days including refueling and refueling-outage length is about seven days. See figure 1) The PELE project consisted of several single projects collected into one for coordinated project management. Some of the main projects were as follows: - Low pressure turbines: rotor, stator vane, casing and turbine instrumentation replacement. - Replacement of Condenser Cooling Water (later called seawater pumps) pumps - Replacement of inner isolation valves on the main steam lines. - Generator and the generator cooling system replacement. - Low voltage switchgear replacement. This project will continue during future outages. PELE was a success. 100 TVO employees and 1500 subcontractor employees participated in the project. The execution of the PELE projects went extremely well during the outages. The replacement of the low pressure turbines and seawater pumps improved the

Olkiluoto 1 and 2 - Plant efficiency improvement and lifetime extension-project (PELE) implemented during outages 2010 and 2011

International Nuclear Information System (INIS)

Kosonen, M.; Hakola, M.

2012-01-01

Teollisuuden Voima Oyj (TVO) is a non-listed public company founded in 1969 to produce electricity for its stakeholders. TVO is the operator of the Olkiluoto nuclear power plant. TVO follows the principle of continuous improvement in the operation and maintenance of the Olkiluoto plant units. The PELE project (Plant Efficiency Improvement and Lifetime Extension), mainly completed during the annual outages in 2010 and 2011, and forms one part of the systematic development of Olkiluoto units. TVO maintains a long-term development program that aims at systematically modernizing the plant unit systems and equipment based on the latest technology. According to the program, the Olkiluoto 1 and Olkiluoto 2 plant units are constantly renovated with the intention of keeping them safe and reliable, The aim of the modernization projects is to improve the safety, reliability, and performance of the plant units. PELE project at Olkiluoto 1 was done in 2010 and at Olkiluoto 2 in 2011. The outage length of Olkiluoto 1 was 26 d 12 h 4 min and Olkiluoto 2 outage length was 28 d 23 h 46 min. (Normal service-outage is about 14 days including refueling and refueling-outage length is about seven days. See figure 1) The PELE project consisted of several single projects collected into one for coordinated project management. Some of the main projects were as follows: - Low pressure turbines: rotor, stator vane, casing and turbine instrumentation replacement. - Replacement of Condenser Cooling Water (later called seawater pumps) pumps - Replacement of inner isolation valves on the main steam lines. - Generator and the generator cooling system replacement. - Low voltage switchgear replacement. This project will continue during future outages. PELE was a success. 100 TVO employees and 1500 subcontractor employees participated in the project. The execution of the PELE projects went extremely well during the outages. The replacement of the low pressure turbines and seawater pumps improved the

Main messages for the new nuclear unit in Finland

International Nuclear Information System (INIS)

Nikula, Anneli

2001-01-01

Teollisuuden Voima Oy (TVO) submitted last year, on 15th November, to the Council of State an application for a decision in principle concerning the construction of additional nuclear capacity. In this presentation, the main messages to decision makers for the new unit are discussed. Also the studies, which the messages are based on, are described. According to the Finnish Nuclear Energy Act, a company considering a nuclear plant project must apply for a decision in principle from the Government beforehand. The Government then decides whether the project is in accordance with the overall good of the society. If the decision is positive, it needs ratification by the Parliament. Before the Government decision, various interested parties are heard, including the municipality of location and the Radiation and Nuclear Safety Authority. The phase of statements is underway and they all will be ready by the end of March 2001. The entire application process takes approximately 1-2 years. The main messages arguing for more nuclear power in Finland were as follows. The new nuclear power plant unit replaces old fossil power plants and satisfies the need for additional demand of electricity; makes possible to meet the requirements of the Kyoto agreement; reduces the dependence on the imported energy and assures a stable and predictable electricity price. Messaging concerning a new nuclear power plant unit is made in co-operation with several organisations. The most important of them, in addition to the company shareholders, are the companies which have shown interested in the new project as well as the Finnish Energy Industries Federation (Finergy) and the Confederation of Finnish Industry and Employers. A transparency folder 'Nuclear electricity 2000' was put together of the messages in collaboration with the organisations. The folder was distributed to about 400 opinion leaders in the energy field. To ensure the consistency of the messages, several interest group meetings

Lasten ulkovaatteiden kevät-kesämalliston seinäesillepano-ohje : case: Reima Oy

OpenAIRE

Järvenoja, Annika

2014-01-01

Opinnäytetyö tehtiin Reima Oy:lle. Työn tavoitteena oli kerätä asiakkaiden mielipiteitä lasten ulkovaatteiden seinäesillepanoista. Tutkimuksen pohjalta tehtiin seinäesillepano-ohje kevät-kesämallistolle. Reiman omat myymälät sijaitsevat pääosin Kiinassa, Suomessa ja Venäjällä. Kevät-kesämalliston tuotteiden vaihtelevuus välikausivaatteista ohuisiin aurinkosuojavaatteisiin koettiin myymälässä haasteelliseksi. Tavoitteena on tutkia lisäksi, mistä maiden kulttuurien eroavaisuudet johtuvat, ja mi...

HENKILÖSTÖVUOKRAUSPALVELUN SÄHKÖISEN MARKKINOINTIVIESTINNÄN KEHITTÄMINEN : Case Nordic JobCentre Oy

OpenAIRE

Salmela, Heli

2016-01-01

Vuokratyön käyttö on ollut kasvussa jo pitkään. Erityisesti rakennus- ja teollisuusaloilla vuokratyön käyttö on hyvin yleistä, vaikka edelleen toimialan maine on joiltain osin negatiivinen. Kilpailu on kuitenkin kovaa, ja erityisesti Etelä-Suomen alueella vuokratyöfirmoja on syntynyt viime vuosikymmenen aikana runsaasti. Opinnäytetyöni on sähköisen markkinointiviestinnän kehitystehtävä, jonka toimeksiantajana on oululaislähtöinen henkilöstövuokrausyritys Nordic JobCentre Oy. Kehitystehtäv...

A visible and infrared study of the eclipsing dwarf nova Oy Carinae

International Nuclear Information System (INIS)

Berriman, G.

1984-01-01

This paper presents three simultaneous visible (V) and infrared (J,H,K) light curves of the eclipsing dwarf nova binary system OY Carinae in quiescence. The infrared light curves show a secondary minimum, not seen in the visible, which is the ellipsoidal variations of the red dwarf and its eclipse by the accretion disc surrounding the white dwarf companion. The red star, an M dwarf, supplies between 30 and 60 per cent of the total light at J,H and K. This requires that the system is between 100 and 300 pc away. The infrared continuum of the accretion disc around the white dwarf companion comes largely from the optically thin gas giving rise to the emission lines seen in the visible and ultraviolet. (author)

Operation characteristics and conditions of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.; Kolros, A.; Polach, S.; Sklenka, L.

1994-01-01

The first 3 years of operation of the VR-1 training reactor are reviewed. This period includes its physical start-up (preparation, implementation, results) and operation development as far as the current operating configuration of the reactor core. The physical start-up was commenced using a reactor core referred to as AZ A1, whose physical parameters had been verified by calculation and whose configuration was based on data tested experimentally on the SR-0 reactor at Vochov. The next operating core, labelled AZ A2, was already prepared during the test operation of the VR-1 reactor. Its configuration was such that both of the main horizontal channels, radial and tangential, could be employed. The configuration that followed, AZ A3, was an intermediate step before testing the graphite side reflector. The current reactor core, labelled AZ A3 G, was obtained by supplementing the previous core with a one-sided graphite side reflector. (Z.S.). 2 tabs., 11 figs., 2 refs

Burnup measurements at the RECH-1 research reactor

International Nuclear Information System (INIS)

Henriquez, C.; Navarro, G.; Pereda, C.; Torres, H.; Pena, L.; Klein, J.; Calderon, D.; Kestelman, A.J.

2002-01-01

The Chilean Nuclear Energy Commission has decided to produce LEU fuel elements for the RECH-1 research reactor. During December 1998, the Fuel Fabrication Plant delivered the first four fuel elements, called leaders, to the RECH-1 reactor. The set was introduced into the reactor's core, following the normal routine, but performing a special follow-up on their behavior inside and outside the core. In order to measure the burn-up of the leader fuel elements, it was decided to develop a burn-up measurements system to be installed into the RECH-1 reactor pool, and to decline the use of a similar system, which operates in a hot cell. The main reason to build this facility was to have the capability to measure the burn-up of fuel elements without waiting for long decay period. This paper gives a brief description of the facility to measure the burn-up of spent fuel elements installed into the reactor pool, showing the preliminary obtained spectra and briefly discussing them. (author)

Maa-analyysi liiketoiminnallisesta näkökulmasta tukemassa kansainvälistymisstrategiaa : Case: SuperApp Oy, Yhdysvallat

OpenAIRE

Laiho, Tea

2016-01-01

Tämä opinnäytetyö toteutettiin toimeksiantona lahtelaisen KIBS-palveluja eli osaamisintensiivisiä liike-elämän palveluja tarjoavan SuperApp Oy:n käyttöön. Tutkimuksen tavoitteena oli kartoittaa kohdemaan potentiaali kansainvälisen liiketoiminnan ja palveluyrityksen näkökulmasta. Tarkoituksena oli antaa case-yritykselle työkaluja ja avaimia, sen laajentaessa liiketoimintaansa tulevaisuudessa ulkomaille, erityisesti Yhdysvaltoihin. Tämä tutkimus käsittelee osaa kansainvälistymisstrategiaa varte...

Yrittäjyyden myytit ja möröt : case: Yritystakomo Oy, Oulu

OpenAIRE

Merentie, Elisa

2012-01-01

Tämän tutkimuksen tarkoituksena on selvittää mitkä yrittäjyyden myytit ja möröt vaikuttavat aloittavan yrittäjän uskallukseen aloittaa yrittäjänä. Ilmiötä tarkastelin tapausyrityksen, Yritystakomo Oy:n kautta. Ovatko vuosia kestäneet yrittäjyyden myytit, uskomukset aiheellisia ja sovellettavissa tämän päivän aloittelevan yrittäjän ajatusmaailmaan? Aihe on valittu, koska yrittäjyydestä ja sen edistämisestä puhutaan paljon, myös sen helppoudesta, mutta siitä huolimatta yrittäjyysidea jää usein...

Quasiparticle Scattering off Defects and Possible Bound States in Charge-Ordered YBa_{2}Cu_{3}O_{y}.

Science.gov (United States)

Zhou, R; Hirata, M; Wu, T; Vinograd, I; Mayaffre, H; Krämer, S; Horvatić, M; Berthier, C; Reyes, A P; Kuhns, P L; Liang, R; Hardy, W N; Bonn, D A; Julien, M-H

2017-01-06

We report the NMR observation of a skewed distribution of ^{17}O Knight shifts when a magnetic field quenches superconductivity and induces long-range charge-density-wave (CDW) order in YBa_{2}Cu_{3}O_{y}. This distribution is explained by an inhomogeneous pattern of the local density of states N(E_{F}) arising from quasiparticle scattering off, yet unidentified, defects in the CDW state. We argue that the effect is most likely related to the formation of quasiparticle bound states, as is known to occur, under specific circumstances, in some metals and superconductors (but not in the CDW state, in general, except for very few cases in 1D materials). These observations should provide insight into the microscopic nature of the CDW, especially regarding the reconstructed band structure and the sensitivity to disorder.

Pienyrityksen B2B-myyntiprosessi Venäjän markkinoilla: Case Perfect Getaway Oy

OpenAIRE

Prokkola, Joni

2014-01-01

Opinnäytetyön tavoitteena oli luoda Perfect Getaway Oy:lle B2B myyntiprosessi suoramyyntiä varten Venäjän markkinoille. Yritys on luksuselämyksiä tarjoava matkailualan yritys, jonka pääkohderyhmänä ovat suomalaiset sekä venäläiset yksityis- ja yritysasiakkaat. Tavoitteena oli selvittää miten kylmäsoittoja voitaisiin käyttää hyväksi suoramyynnissä. Toimeksiantajana toimi yrityksen toimitusjohtaja. Opinnäytetyön kirjoittaja on myös työsuhteessa kyseiseen yritykseen. Tuotoksena toimisivat kaksi ...

Training and research on the nuclear reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.

1998-01-01

The VR-1 training reactor is a light water reactor of the pool type using enriched uranium as the fuel. The moderator is demineralized light water, which also serves as the neutron reflector, biological shielding, and coolant. Heat evolved during the fission process is removed by natural convection. The reactor is used in the education of students in the field of reactor and neutron physics, dosimetry, nuclear safety, and instrumentation and control systems for nuclear facilities. Although primarily intended for students in various branches of technology (power engineering, nuclear engineering, physical engineering), this specialized facility is also used by students of faculties educating future natural scientists and teachers. Typical tasks trained at the VR-1 reactor include: measurement of delayed neutrons; examination of the effect of various materials on the reactivity of the reactor; measurement of the neutron flux density by various procedures; measurement of reactivity by various procedures; calibration of reactor control rods by various procedures; approaching the critical state; investigation of nuclear reactor dynamics; start-up, control and operation of a nuclear reactor; and investigation of the effect of a simulated nucleate boil on reactivity. In addition to the education of university-level students, training courses are also organized for specialists in the Czech nuclear programme

ABB Oy Motors and Generators -yksikön energiansyöttöjen erotus- ja lukitusohjeet

OpenAIRE

Chi, Henri

2017-01-01

Tämä insinöörityö toteutettiin Quant Finland Oy:lle, joka vastaa Helsingin Pitäjänmäen ABB Motors and Generators -tehtaan kunnossapidosta. Insinöörityön tavoitteena oli luoda energiansyöttöjen lukitus- ja erotusohjeet tehtaan koneistoille, laitteille ja järjestelmille. Tehtaalla on isoja koneita ja laitteita, jonka erotus- ja lukitustoimenpiteitä kaikki eivät osaa. Näin ollen on haluttu mahdollistaa turvallinen työskentely tarjoamalla selkeät erotus- ja lukitusohjeet. ABB Motors and Gene...

Massaräätälöityjen tuotteiden prosessin hallinta ja konfigurointi : Selvitystyö yritykselle Kera Group Oy

OpenAIRE

Saares, Sanna

2017-01-01

Opinnäytetyön aiheena oli selvittää, mikä ohjelmistokokonaisuus soveltuisi parhaiten terassituotteiden suunnittelun ja myynnin tueksi. Opinnäytetyö tehtiin Orimattilassa sijaitsevalle muovi- ja lasituotteisiin erikoistuneelle Kera Group Oy:lle. Tuotealueena olivat lasitetut valmisterassit, joita toimitetaan pientalojen yhteyteen. Vaikka valmiita terassityyppejä on rajattu määrä, joudutaan suurin osa tuotteista suunnittelemaan ja valmistamaan yksilöllisesti. Uuden tuotteen suunnittelu on ...

Thermal and hydraulic characteristics of the JEN-1 Reactor; Caracteristicas hidraulicas y termicas del Reactor JEN-1

Energy Technology Data Exchange (ETDEWEB)

Otra Otra, F; Leira Rey, G

1971-07-01

In this report an analysis is made of the thermal and hydraulic performances of the JEN-1 reactor operating steadily at 3 Mw of thermal power. The analysis is made separately for the core, main heat exchanger and cooling tower. A portion of the report is devoted to predict the performances of these three main components when and if the reactor was going to operate at a power higher than the maximum 3 Mw attainable today. Finally an study is made of the unsteady operation of the reactor, focusing the attention towards the pumping characteristics and the temperatures obtained in the fuel elements. Reference is made to several digital calculation programmes that nave been developed for such purpose. (Author) 21 refs.

IEA-R1 reactor - Spent fuel management

International Nuclear Information System (INIS)

Mattos, J.R.L. De

1996-01-01

Brazil currently has one Swimming Pool Research Reactor (IEA-R1) at the Instituto de Pesquisas Energeticas e Nucleares - Sao Paulo. The spent fuel produced is stored both at the Reactor Pool Storage Compartment and at the Dry Well System. The present situation and future plans for spent fuel storage are described. (author). 3 refs, 2 figs, 2 tabs

TR-EDB: Test Reactor Embrittlement Data Base, Version 1

Energy Technology Data Exchange (ETDEWEB)

Stallmann, F.W.; Wang, J.A.; Kam, F.B.K. [Oak Ridge National Lab., TN (United States)

1994-01-01

The Test Reactor Embrittlement Data Base (TR-EDB) is a collection of results from irradiation in materials test reactors. It complements the Power Reactor Embrittlement Data Base (PR-EDB), whose data are restricted to the results from the analysis of surveillance capsules in commercial power reactors. The rationale behind their restriction was the assumption that the results of test reactor experiments may not be applicable to power reactors and could, therefore, be challenged if such data were included. For this very reason the embrittlement predictions in the Reg. Guide 1.99, Rev. 2, were based exclusively on power reactor data. However, test reactor experiments are able to cover a much wider range of materials and irradiation conditions that are needed to explore more fully a variety of models for the prediction of irradiation embrittlement. These data are also needed for the study of effects of annealing for life extension of reactor pressure vessels that are difficult to obtain from surveillance capsule results.

TR-EDB: Test Reactor Embrittlement Data Base, Version 1

International Nuclear Information System (INIS)

Stallmann, F.W.; Wang, J.A.; Kam, F.B.K.

1994-01-01

The Test Reactor Embrittlement Data Base (TR-EDB) is a collection of results from irradiation in materials test reactors. It complements the Power Reactor Embrittlement Data Base (PR-EDB), whose data are restricted to the results from the analysis of surveillance capsules in commercial power reactors. The rationale behind their restriction was the assumption that the results of test reactor experiments may not be applicable to power reactors and could, therefore, be challenged if such data were included. For this very reason the embrittlement predictions in the Reg. Guide 1.99, Rev. 2, were based exclusively on power reactor data. However, test reactor experiments are able to cover a much wider range of materials and irradiation conditions that are needed to explore more fully a variety of models for the prediction of irradiation embrittlement. These data are also needed for the study of effects of annealing for life extension of reactor pressure vessels that are difficult to obtain from surveillance capsule results

Franchising - liiketoiminnan käynnistämiseen vaadittavat toimenpiteet ja haasteet organisaatiossa : case: Touring Cars Finland Oy

OpenAIRE

Aaltonen, Suvi

2013-01-01

Tämän opinnäytetyön tavoitteena oli selvittää franchise-liiketoiminnan käynnistämiseen liittyviä toimenpiteitä ja haasteita organisaatiossa. Opinnäytetyön teoriaosuus selvittää niitä asioita, joita franchise-antajan ja –ottajan on huomioitava franchise-liiketoimintaa aloittaessaan. Case-yrityksenä on suomalainen Touring Cars Finland Oy. Case-yritys siirtyy käyttämään franchise-liiketoimintamallia vuosien 2013–2018 aikana yrityksen kaikissa toimipisteissä Suomessa ja ulkomailla. Touring Ca...

Modernization and Refurbishment of the RECH-1 Reactor

Energy Technology Data Exchange (ETDEWEB)

Daie, J. [Nuclear Application Department, Chilean Nuclear Energy Commission (CCHEN), Santiago (Chile)

2014-08-15

The Chilean Nuclear Energy Commission (Comisión Chilena de Energía Nuclear, or CCHEN) has operated the RECH-1 research reactor since 1974. This reactor is located at La Reina Nuclear Centre in Santiago, Chile. It is a pool type reactor using LEU MTR fuel assemblies, light water as moderator and coolant, and beryllium as reflector. The reactor has been operated at the nominal power of 5 MW in a continuous shift of 20 hours per week, 48 weeks per year. The main utilizations of the RECH-1 reactor are radioisotope production and neutron activation analysis. Among the most relevant refurbishment and modernization campaigns undertaken at the reactor are: full core conversion to the use of LEU fuel, replacement of the cooling tower, improvement of the containment building by changing the doors and gates and by a better sealant for the penetrations, introduction of an additional source of water by connecting the raw water supply system to the emergency cooling system, improvement of the emergency ventilation system, introduction of a fire detection and alarm system for detection and mitigation to protect the I&C racks, introduction of a radioactive liquid release for those generated at the reactor, introduction of a delay tank degasification system and renewal of the environmental monitoring system. At present we are assessing the possibility of replacing the old analog electronics of control for new digital systems. Detailed descriptions of these diverse activities are presented in the paper. (author)

Extensive utilisation of VR-1 reactor for nuclear education and training

International Nuclear Information System (INIS)

Rataj, J.

2010-01-01

The paper presents utilisation of the VR-1 reactor for nuclear education and training at national and international level. VR-1 reactor has been operating by the Czech Technical University since December 1990. The reactor is a pool-type light water reactor based on enriched uranium (19.7% 235 U) with maximum thermal power 1kW and for short time period up to 5kW. The moderator of neutrons is light water, which is also used as a reflector, a biological shielding and a coolant. Heat is removed from the core by natural convection. The pool disposition of the reactor facilitates access to the core, setting and removing of various experimental samples and detectors, easy and safe handling of fuel assemblies. The reactor core can contain from 17 to 21 fuel assemblies IRT-4M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The reactor is equipped with several experimental devices; e.g. horizontal, radial and tangential channels used to take out a neutron beam, reactivity oscillator for dynamics study and bubble boiling simulator. The reactor has been used very efficiently especially for education and training of university students and NPP's specialists for more than 18 years. The VR-1 reactor is utilised within various national and international activities such as Czech Nuclear Education Network (CENEN), European Nuclear Education Network and also Eastern European Research Reactor Initiative (EERRI). The reactor is well equipped for education and training not only by the experimental facility itself but also by incessant development of training methods and improvement of education experiments. The education experiments can be combined into training courses attended by students according to their study specialization and knowledge level. The training programme is aimed to the reactor and neutron physics, dosimetry, nuclear safety, and control of nuclear installations. Every year, approximately 250 university students undergo

Annual report on JEN-1 and JEN-2 Reactors; Informe periodico de Reactores JEN-1 y JEN-2 correpondiente al ano 1972

Energy Technology Data Exchange (ETDEWEB)

Montes Ponce de Leon, J.

1974-07-01

In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

Rotary Bed Reactor for Chemical-Looping Combustion with Carbon Capture. Part 1: Reactor Design and Model Development

KAUST Repository

Zhao, Zhenlong

2013-01-17

Chemical-looping combustion (CLC) is a novel and promising technology for power generation with inherent CO2 capture. Currently, almost all of the research has been focused on developing CLC-based interconnected fluidized-bed reactors. In this two-part series, a new rotary reactor concept for gas-fueled CLC is proposed and analyzed. In part 1, the detailed configuration of the rotary reactor is described. In the reactor, a solid wheel rotates between the fuel and air streams at the reactor inlet and exit. Two purging sectors are used to avoid the mixing between the fuel stream and the air stream. The rotary wheel consists of a large number of channels with copper oxide coated on the inner surface of the channels. The support material is boron nitride, which has high specific heat and thermal conductivity. Gas flows through the reactor at elevated pressure, and it is heated to a high temperature by fuel combustion. Typical design parameters for a thermal capacity of 1 MW have been proposed, and a simplified model is developed to predict the performances of the reactor. The potential drawbacks of the rotary reactor are also discussed. © 2012 American Chemical Society.

Use of the VR-1 ''Vrabec'' training reactor

International Nuclear Information System (INIS)

Matejka, K.; Kolros, A.; Krops, S.; Polach, S.; Sklenka, L.

1994-01-01

An overview is presented of the extent and ways of using the VR-1 training reactor, which is operated by the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague. A list and the characteristics of 16 problems developed for teaching purposes is given, and the 14 faculties and 2 research institutes participating in the teaching activities are listed. The reactor is used in the education and training of nuclear scientists and engineers. The instrumentation, experimental, handling and operating tools, as well as documentation and texts relating to the reactor are described. The following examples of the teaching activities are included: a guided visit to the operating reactor site, reactor dynamics study and delayed neutron measurement, training course, and the basic criticality experiment. Nuclear safety aspects (hypothetical accidents, quality control and system qualification demonstration, safety culture) are stressed during the education. The reactor department is involved in international cooperation projects. (J.B.). 3 refs

Electrical system regulations of the IEA-R1 reactor

International Nuclear Information System (INIS)

Mello, Jose Roberto de; Madi Filho, Tufic

2013-01-01

The IEA-R1 reactor of the Nuclear and Energy Research Institute (IPEN-CNEN/SP), is a research reactor open pool type, designed and built by the U.S. firm Babcock and Wilcox, having, as coolant and moderator, deionized light water and beryllium and graphite, as reflectors. Until about 1988, the reactor safety systems received power from only one source of energy. As an example, it may be cited the control desk that was powered only by the vital electrical system 220V, which, in case the electricity fails, is powered by the generator group: no-break 220V. In the years 1989 and 1990, a reform of the electrical system upgrading to increase the reactor power and, also, to meet the technical standards of the ABNT (Associacao Brasileira de Normas Tecnicas) was carried out. This work has the objective of showing the relationship between the electric power system and the IEA-R1 reactor security. Also, it demonstrates that, should some electrical power interruption occur, during the reactor operation, this occurrence would not start an accident event. (author)

Modernization of control instrumentation and security of reactor IAN - R1

International Nuclear Information System (INIS)

Gonzalez, J. M.

1993-01-01

The program to modernize IAN-R1 research reactor control and safety instrumentation has been carried out considering two main aspects: updating safety philosophy requirements and acquiring the newest reactor control instrumentation controlled by computer, following the present criteria internationally recognized, for safety and reliable reactor operations and the latest developments of nuclear electronic technology. The new IAN-R1 reactor instrumentation consist of two wide range neutron monitoring channels, commanded by microprocessor a data acquisition system and reactor control, (controlled by computers). The reactor control desk is providing through two displays; all safety and control signals to the reactor operators; furthermore some signals like reactor power, safety and period signals are also showed on digital bar graphics, which are hard wired directly from the neutron monitoring channels

Operation and maintenance of 1MW PUSPATI TRIGA reactor

International Nuclear Information System (INIS)

Adnan Bokhari; Mohammad Suhaimi Kassim

2006-01-01

The Malaysian Research Reactor, Reactor TRIGA PUSPATI (RTP) has been successfully operated for 22 years for various experiments. Since its commissioning in June 1982 until December 2004, the 1MW pool-type reactor has accumulated more than 21143 hours of operation, corresponding to cumulative thermal energy release of about 14083 MW-hours. The reactor is currently in operation and normally operates on demand, which is normally up to 6 hours a day. Presently the reactor core is made up of standard TRIAGA fuel element consists of 8.5 wt%, 12 wt% and 20 wt% types; 20%-enriched and stainless steel clad. Several measures such as routine preventive maintenance and improving the reactor support systems have been taken toward achieving this long successful operation. Besides normal routine utilization like other TRIGA reactors, new strategies are implemented for effective increase in utilization. (author)

Perspectives on reactor safety. Revision 1

International Nuclear Information System (INIS)

Haskin, F.E.; Hodge, S.A.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

Perspectives on reactor safety. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

Annual report on JEN-1 and JEN-2 Reactors

International Nuclear Information System (INIS)

Montes Ponce de Leon, J.

1974-01-01

In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

Advances in Reactor Physics, Mathematics and Computation. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

These proceedings of the international topical meeting on advances in reactor physics, mathematics and computation, volume one, are divided into 6 sessions bearing on: - session 1: Advances in computational methods including utilization of parallel processing and vectorization (7 conferences) - session 2: Fast, epithermal, reactor physics, calculation, versus measurements (9 conferences) - session 3: New fast and thermal reactor designs (9 conferences) - session 4: Thermal radiation and charged particles transport (7 conferences) - session 5: Super computers (7 conferences) - session 6: Thermal reactor design, validation and operating experience (8 conferences).

Stationary low power reactor No. 1 (SL-1) accident site decontamination ampersand dismantlement project

International Nuclear Information System (INIS)

Perry, E.F.

1995-01-01

The Army Reactor Area (ARA) II was constructed in the late 1950s as a test site for the Stationary Low Power Reactor No. 1 (SL-1). The SL-1 was a prototype power and heat source developed for use at remote military bases using a direct cycle, boiling water, natural circulation reactor designed to operate at a thermal power of 3,000 kW. The ARA II compound encompassed 3 acres and was comprised of (a) the SL-1 Reactor Building, (b) eight support facilities, (c) 50,000-gallon raw water storage tank, (d) electrical substation, (e) aboveground 1,400-gallon heating oil tank, (f) underground 1,000-gallon hazardous waste storage tank, and (g) belowground power, sewer, and water systems. The reactor building was a cylindrical, aboveground facility, 39 ft in diameter and 48 ft high. The lower portion of the building contained the reactor pressure vessel surrounded by gravel shielding. Above the pressure vessel, in the center portion of the building, was a turbine generator and plant support equipment. The upper section of the building contained an air cooled condenser and its circulation fan. The major support facilities included a 2,500 ft 2 two story, cinder block administrative building; two 4,000 ft 2 single story, steel frame office buildings; a 850 ft 2 steel framed, metal sided PL condenser building, and a 550 ft 2 steel framed decontamination and laydown building

Reactor utilization, Part 1

International Nuclear Information System (INIS)

Martinc, R.; Stanic, A.

1981-01-01

The reactor operating plan for 1981 was subject to the needs of testing operation with the 80% enriched fuel and was fulfilled on the whole. This annex includes data about reactor operation, review of shorter interruptions due to demands of the experiments, data about safety shutdowns caused by power cuts. Period of operation at low power levels was used mostly for activation analyses, and the operation at higher power levels were used for testing and regular isotope production. Detailed data about samples activation are included as well as utilization of the reactor as neutron source and the operating plan for 1982 [sr

The benefits of Outsourcing facility services when selecting right service provider for a hotel:Case Kämp Group Oy

OpenAIRE

Paudyal, Manoj; Acharya, Saroj

2015-01-01

This research paper examines about the outsourcing of facility services in the Kämp group of hotels. The scope of the study includes Facility Management, outsourcing facilities services, and the selection process of the service providers for a hotel. The research was carried at the hotels of Kämp group Oy in the Metropolitan Area of Helsinki. Facility management includes wide ranges of non-core functions such as Property management, real estates, design and technology. Activities such as secu...

Refurbishment of Pakistan research reactor (PARR-1) for stainless steel lining of the reactor pool

International Nuclear Information System (INIS)

Salahuddin, A.; Israr, M.; Hussain, M.

2002-01-01

Pakistan Research Reactor-1 (PARR-1) is a pool-type research reactor. Reactor aging has resulted in the increase of water seepage from the concrete walls of the reactor pool. To stop the seepage, it was decided to augment the existing pool walls with an inner lining of stainless steel. This could be achieved only if the pool walls could be accessed unhindered and without excessive radiation doses. For this purpose a partial decommissioning was done by removing all active core components including standard/control fuel elements, reflector elements, beam tubes, thermal shield, core support structure, grid plate and the pool's ceramic tiles, etc. An overall decommissioning program was devised which included procedures specific to each item. This led to the development of a fuel transport cask for transportation, and an interim fuel storage bay for temporary storage of fuel elements (until final disposal). The safety of workers and the environment was ensured by the use of specially designed remote handling tools, appropriate shielding and pre-planned exposure reduction procedures based on the ALARA principle. During the implementation of this program, liquid and solid wastes generated were legally disposed of. It is felt that the experience gained during the refurbishment of PARR-1 to install the stainless steel liner will prove useful and better planning and execution for the future decommissioning of PARR-1, in particular, and for other research reactors like PARR-2 (27 kW MNSR), in general. Furthermore, due to the worldwide activities on decommissioning, especially those communicated through the IAEA CRP on 'Decommissioning Techniques for Research Reactors', the importance of early planning has been well recognized. This has made possible the implementation of some early steps like better record keeping, rehiring of trained manpower, and creation of interim and final waste storage. (author)

RA research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1985

International Nuclear Information System (INIS)

Sotic, O.; Martinc, R.; Cupac, S.; Sulem, B.; Badrljica, R.; Majstorovic, D.; Sanovic, V.

1985-01-01

According to the plan, RA reactor was to be in operation in mid September 1985. But, since the building of the emergency cooling system, nor the reconstruction of the existing special ventilation system were not finished until the end of August reactor was not operated during 1985. During the previous four years reactor operation was limited by the temporary operating license issued by the Committee of Serbian ministry for health and social care, which was cancelled in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. This temporary license has limited the reactor power to 2 MW from 1981-1984. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. In order to enable future reliable operation of the RA reactor, according to new licensing regulations, during 1984, three major tasks have started: building of the new emergency system, reconstruction of the existing ventilation system, and renewal of the reactor instrumentation. IAEA has approved the amount of 1,300,000 US dollars for the renewal of the instrumentation [sr

New instrumentation for the IPR-R1 reactor of CDTN

International Nuclear Information System (INIS)

Carvalho, P.V.R. de.

1992-01-01

The Nuclear Engineering Institute reactor instrumentation area has developed systems and equipment for reactor operation and safety. In such way, the new I and C for IEN Argonauta reactor and the nuclear instrumentation for IPEN critical facility were built. This paper describes our real work, the new I and C systems for IPR-R1, a Triga type reactor, located at CDTN (Belo Horizonte - MG). (author)

Major update of Safety Analysis Report for Thai Research Reactor-1/Modification 1

Energy Technology Data Exchange (ETDEWEB)

Tippayakul, Chanatip [Thailand Institute of Nuclear Technology, Bangkok (Thailand)

2013-07-01

Thai Research Reactor-1/Modification 1 (TRR-1/M1) was converted from a Material Testing Reactor in 1975 and it had been operated by Office of Atom for Peace (OAP) since 1977 until 2007. During the period, Office of Atom for Peace had two duties for the reactor, that is, to operate and to regulate the reactor. However, in 2007, there was governmental office reformation which resulted in the separation of the reactor operating organization from the regulatory body in order to comply with international standard. The new organization is called Thailand Institute of Nuclear Technology (TINT) which has the mission to promote peaceful utilization of nuclear technology while OAP remains essentially the regulatory body. After the separation, a new ministerial regulation was enforced reflecting a new licensing scheme in which TINT has to apply for a license to operate the reactor. The safety analysis report (SAR) shall be submitted as part of the license application. The ministerial regulation stipulates the outlines of the SAR almost equivalent to IAEA standard 35-G1. Comparing to the IAEA 35-G1 standard, there were several incomplete and missing chapters in the original SAR of TRR1/M1. The major update of the SAR was therefore conducted and took approximately one year. The update work included detail safety evaluation of core configuration which used two fuel element types, the classification of systems, structures and components (SSC), the compilation of detail descriptions of all SSCs and the review and evaluation of radiation protection program, emergency plan and emergency procedure. Additionally, the code of conduct and operating limits and conditions were revised and finalized in this work. A lot of new information was added to the SAR as well, for example, the description of commissioning program, information on environmental impact assessment, decommissioning program, quality assurance program and etc. Due to the complexity of this work, extensive knowledge was

Thermal hydraulic analysis of the IPR-R1 TRIGA reactor

International Nuclear Information System (INIS)

Veloso, Marcelo Antonio; Fortini, Maria Auxiliadora

2002-01-01

The subchannel approach, normally employed for the analysis of power reactor cores that work under forced convection, have been used for the thermal hydraulic evaluation of a TRIGA Mark I reactor, named IPR-R1, at 250 kW power level. This was accomplished by using the PANTERA-1P subchannel code, which has been conveniently adapted to the characteristics of natural convection of TRIGA reactors. The analysis of results indicates that the steady state operation of IPR-R1 at 250 kW do not imply risks to installations, workers and public. (author)

New human machine interface for VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Sklenka, L.; Chab, V.

2002-01-01

The contribution describes a new human machine interface that was installed at the VR-1 training reactor. The human machine interface update was completed in the summer 2001. The human machine interface enables to operate the training reactor. The interface was designed with respect to functional, ergonomic and aesthetic requirements. The interface is based on a personal computer equipped with two displays. One display enables alphanumeric communication between a reactor operator and the control and safety system of the nuclear reactor. Messages appear from the control system, the operator can write commands and send them there. The second display is a graphical one. It is possible to represent there the status of the reactor, principle parameters (as power, period), control rods' positions, the course of the reactor power. Furthermore, it is possible to set parameters, to show the active core configuration, to perform reactivity calculations, etc. The software for the new human machine interface was produced in the InTouch developing environment of the WonderWare Company. It is possible to switch the language of the interface between Czech and English because of many foreign students and visitors at the reactor. The former operator's desk was completely removed and superseded with a new one. Besides of the computer and the two displays, there are control buttons, indicators and individual numerical displays of instrumentation there. Utilised components guarantee high quality of the new equipment. Microcomputer based communication units with proper software were developed to connect the contemporary control and safety system with the personal computer of the human machine interface and the individual displays. New human machine interface at the VR-1 training reactor improves the safety and comfort of the reactor utilisation, facilitates experiments and training, and provides better support of foreign visitors.(author)

Reactor Engineering Department annual report (April 1, 1987 - March 31, 1988)

International Nuclear Information System (INIS)

1988-11-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1987 (April 1, 1987 - March 31, 1988). The major activities in the Department concerns the programs of the high temperature gas-cooled reactor, the high conversion light water reactor, the advanced fission reactor system and the fusion reactor at JAERI and the fast breeder reactor at PNC. The report contains the latest progress in nuclear data and group constants, theoretical methods and code development, reactor physics experiments and analyses, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control/diagnosis and robotics, as well as the new topics from this fiscal year on advanced reactors system design studies and technique developments related the facilities in the Department. Also described are the activities of the Research Committee on Reactor Physics. (author)

Energiantuotannon ratkaisut Penttilän Puu Oy:n höyläämön sivuvirrasta

OpenAIRE

Kortelainen, Toni

2017-01-01

Tässä teknistaloudellisessa opinnäytetyössä selvitettiin Penttilän Puu Oy:n Joensuun höyläämölle taloudellisesti kannattavin energiantuotantoratkaisu. Käyttöikänsä päähän tulleen nykyisen ruuvisyötteisen arinakattilan tilalle on harkittu pienen kokoluokan sähkön ja lämmön yhteistuotantoa (pien-CHP), mikäli sellainen osoittautuu kannattavaksi. Muussa tapauksessa arinakattila vaihdetaan uuteen biokattilaan lähivuosina. Opinnäytetyön teknisessä osiossa esitellään korvaavat lämmitysvaih...

Department of Reactor Technology annual progress report 1 January -31 December 1977

International Nuclear Information System (INIS)

1978-04-01

The work of the Department of Reactor Technology within the following fields is described: reactor engineering, reactor operation, structural reliability, system reliability, reactor physics, fuel management, reactor accident analysis for LOCA and ECC, containment analysis, experimental heat transfer, reactor core dynamics and power plant simulators, experimental activation measurements and neutron radiography at the DR 1 reactor, underground storage of gas, solar heating and underground heat storage, wind power. (author)

Reactor Engineering Department annual report (April 1, 1988 - March 31, 1989)

International Nuclear Information System (INIS)

1989-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1988 (April 1, 1988 - March 31, 1989). The Department has promoted cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and also to PNC's fast reactor project. Other major Department's programs are the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Application of a high energy accelerator to the nuclear engineering is also preliminarily assessed. The report also contains the latest progress in various basic researches as nuclear data and group constants, theoretical methods and code development, reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/ diagnosis and technical developments related to the reactor physics facilities. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Thai Research Reactor (TRR-1/M1) Neutron Beam Measurements

International Nuclear Information System (INIS)

Ratanatongchai, Wichian

2009-07-01

Full text: Neutron beam tube of neutron radiography facility at Thai Research Reactor (TRR-1/M1) Thailand Institute of Nuclear Technology (public organization) is a divergent beam. The rectangular open-end of the beam tube is 16 cm x 17 cm while the inner-end is closed to the reactor core. The neutron beam size was measured using 20 cm x 40 cm neutron imaging plate. The measurement at the position 100 cm from the end of the collimator has shown that the beam size was 18.2 cm x 19.0 cm. Gamma ray in neutron the beam was also measured by the identical position using industrial X ray film. The area of gamma ray was 27.8 cm x 31.1 cm with the highest intensity found to be along the neutron beam circumference

New measuring and protection system at VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Jurickova, M.

2006-01-01

The contribution describes the new measuring and protection system of the VR-1 training reactor. The measuring and protection system upgrade is an integral part of the reactor I and C upgrade. The new measuring and protection system of the VR-1 reactor consists of the operational power measuring and the independent power protection systems. Both systems measure the reactor power and power rate, initiate safety action if safety limits are exceeded and send data (power, power rate, status, etc.) to the reactor control system. The operational power measuring system is a full power range system that receives signal from a fission chamber. The signal is evaluated according to the reactor power either in the pulse or current mode. The current mode utilizes the DC current and Campbell techniques. The new independent power protection system operates in the two highest reactor power decades. It receives signals from a boron chamber and evaluates it in the pulse mode. Both systems are computer based. The operational power measuring and independent power protection systems are diverse - different types and location of chambers, completely different hardware, software algorithms for the power and power rate calculations, software development tools and teems for the software manufacturing. (author)

Reactor Engineering Department annual report (April 1, 1990 - March 31, 1991)

International Nuclear Information System (INIS)

1991-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1990 (April 1, 1990 - March 31, 1991). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Reactor Engineering Department annual report (April 1, 1991-March 31, 1992)

International Nuclear Information System (INIS)

1992-08-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1991 (April 1, 1991-March 31, 1992). The major Department's programs promoted in the year are assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researchers on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative work to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Reinforced fluropolymer nanocomposites with high-temperature superconducting Bi2Sr2CaCu2Oy

Science.gov (United States)

Jayasree, T. K.

2014-10-01

Bismuth Strontium Calcium Copper Oxide (Bi2Sr2CaCu2Oy)/Polyvinylidene fluoride (PVDF) nanocomposite was prepared and their thermal properties were analyzed. The composite consists of the polyvinylidene fluoride (PVDF) as an insulating polymer matrix, and homogenously distributed Bismuth strontium calcium copperoxide (2212) nanoparticles. SEM data shows flaky grains of the superconductor coated and linked by polymer. Differential scanning calorimetry (DSC) results indicated that the melting point was not affected significantly by the addition of BSCCO. However, the addition of superconducting ceramic resulted in an extra melting peak at a lower temperature (145°C). Thermogravimetric analysis of the samples shows that the onset decomposition temperature of the PVDF matrix was decreased by the addition of SC filler.

The visual illustration of complex process information during abnormal incidents

International Nuclear Information System (INIS)

Heimbuerger, H.; Kautto, A.; Norros, L.; Ranta, J.

1985-01-01

One of the proposed solutions to the man-process interface problem in nuclear power plants is the integration of a system in the control room that can provide the operator with a display of a minimum set of critical plant parameters defining the safety status of the plant. Such a system has been experimentally validated using the Loviisa training simulator during the fall of 1982. The project was a joint effort between Combustion Engineering Inc., the Halden Reactor Project, Imatran Voima Oy and VTT. Alarm systems are used in nuclear power plants to tell the control room operators that an unexpected change in the plant operation state has occurred. One difficulty in using the alarms for checking the actions of the operator is that the conventional way of realizing the alarm systems implies that several alarms are active also during normal operation. The coding and representation of alarm information will be discussed in the paper. An important trend in control room design is the move away from direct, concrete indication of process parameters towards use of more abstract/logical representation of information as a basis for plant supervision. Recent advances in computer graphics provide the possibility that, in the future, visual information will be utilized to make the essential dynamics of the process more intelligible. A set of criteria for use of visual information will be necessary. The paper discusses practical aspects for the realisation of such criteria in the context of nuclear power plant. The criteria of the decomposition of the process information concerning the sub-goals safety and availability and also the tentative results of the conceptualization of a PWR-process are discussed in the paper

Thermohydraulic analysis for power increase of IEAR-1 reactor

International Nuclear Information System (INIS)

Umbehaun, Pedro E.; Bastos, Jose L.F.

1996-01-01

In this work has been presented the reactor core thermohydraulic model of IEAR-1, aiming its power operation increase from 2MW to 5MW. The design criteria adopted have been established in Safety Series 35. Three configurations of reactor core were analysed: fuel elements 20, 25 and 30

Decommissioning and decontrolling the R1-reactor

International Nuclear Information System (INIS)

Bergman, C.; Holmberg, B.T.

1985-01-01

Sweden's first nuclear reactor - the research reactor R1 - situated in bedrock under the Royal Technical Institute of Stockholm, has in the period 1981-1983 been subject to a complete decommissioning. The National Institute for Radiation Protection has followed the work in detail, and has after the completion of the decommissioning performed measurements of radioactivity on site. The report gives an account of the work the Institute has done in preparation for- and during decommissioning and specifically report on the measurements for classification of the local as free for non-nuclear use. (aa)

Upgrading of the research reactors FRG-1 and FRG-2

International Nuclear Information System (INIS)

Krull, W.

1981-01-01

In 1972 for the research reactor FRG-2 we applied for a license to increase the power from 15 MW to 21 MW. During this procedure a public laying out of the safety report and an upgrading procedure for both research reactors - FRG-1 (5 MW) and FRG-2 - were required by the licensing authorities. After discussing the legal background for licensing procedures in the Federal Republic of Germany the upgrading for both research reactors is described. The present status and future licensing aspects for changes of our research reactors are discussed, too. (orig.) [de

RA Research reactor Annual report 1981 - Part 1, Operation, maintenance and utilization of the RA reactor

International Nuclear Information System (INIS)

Sotic, O.; Milosevic, M.; Martinc, R.; Kozomara-Maic, S.; Cupac, S.; Radivojevic, J.; Stamenkovic, D.; Skoric, M.

1981-12-01

The RA nuclear reactor stopped operation after March 1979 campaign due to appearance of aluminium oxyhydrates deposits on the surface of fuel element claddings. Relevant decisions of the Sanitary inspection body of the Ministry of health and the Director General of the 'Boris Kidric' Institute of nuclear sciences, Vinca, banned further reactor operation until reasons caused aluminium oxyhydrates deposition are investigated and removed to enable regular reactor operation. Until the end of 1979 and during 1980, after a series of analyses and findings that caused cease of reactor operation, all the preparatory actions needed for restart were performed. Due to the fact that there is no emergency cooling system and no appropriate filtering system at the reactor, and according to the new regulations about start up of nuclear facilities, the Sanitary inspection body made a decision about temporary licence for reactor start-up meaning performance of the 'zero experiment' limiting the operating power to 1% of the nominal power. Accordingly the reactor was restarted on January 21 1981. Criticality was reached with the core made of 80% enriched fuel elements only. After the experiment was finished by the end of March a permission was demanded for operation at higher power levels at full power. Taking into account the state of the reactor components the operating licence was issued limiting the power to 2 MW until reconstruction of the ventilation system and construction of the emergency cooling system are fulfilled. Program of testing operation started on September 15 1981 increasing gradually the operating power. Thus the reactor was operated at 2 MW power for 15 days during November and December. The total production achieved in 1981 was 1698 MWh. This enabled isotopes production at the reactor during last two months. Control and maintenance of the reactor components and systems was done regularly and efficiently within limits imposed by availability of spare parts. The

Matkustussäännön toteuttaminen ja kehittäminen - Case Norilsk Nickel Harjavalta Oy

OpenAIRE

Sihvonen, Aino

2015-01-01

Tämä opinnäytetyö tehtiin toimeksiantona Norilsk Nickel Harjavalta Oy:lle. Opinnäytetyön tarkoituksena oli tutkia toimeksiantajan matkustussäännön vahvuuksia ja puutteita. Tutkimustehtävänä oli selvittää, miten yhtiön henkilöstö kokee nykyisen matkustussäännön sekä mistä johtuu, että matkustusasioissa ilmenee erilaisia käytänteitä. Tutkimuksen tavoitteena oli luoda kehitysehdotuksia yhtiön matkustussääntöön. Matkustussäännön kehittämisellä pyritään kustannustehokkuuden ja ympäristönäkökulmien...

Department of Reactor Technology: annual progress report 1 January - 31 December 1976

International Nuclear Information System (INIS)

1977-06-01

The work of the Department of Reactor Technology within the following fields is described: reactor engineering, structural reliability, system reliability, radiation fiels in nuclear power plants, reactor physics, fuel management, fission product decay analysis, steady-state thermo-hydraulics, reactor accident analysis for LOCA and ECC, containment analysis, experimental heat transfer, reactor core dynamics and power plant simulators, control rod ejection accident analysis, economic studies for power plants, experimental activation measurements and neutron radiography at the DR 1 reactor. (author)

CRM-tietojärjestelmän käyttöopas osana yrityksen asiakkuudenhallintaa : case: Fysioline Oy

OpenAIRE

Ilonen, Mikko

2012-01-01

Tämän opinnäytetyön aiheena on CRM-tietojärjestelmän käyttöopas osana yrityksen asiakkuudenhallintaa. Opinnäytetyön teoriaosuus käsittelee asiakkuudenhallintaa, CRM-tietojärjestelmiä ja CRM:n käyttöönottoa. Työn empiriaosuus muodostuu CRM-tietojärjestelmän käyttöoppaasta. CRM-tietojärjestelmän käyttöopas tehdään kohdeyritys Fysioline Oy:lle. Opinnäytetyön teoriaosuudessa selvitetään vastausta tutkimusongelmaan, miksi yrityksen tulee kiinnittää huomiota asiakkuudenhallintaan ja mitä hyötyä...

ISO 14001 -standardin mukaisen ympäristöjärjestelmän luominen : case: Plastep Oy

OpenAIRE

Harju, Siiri

2016-01-01

Opinnäytetyön tavoitteena oli luoda kattavan ympäristökartoituksen sisältävä ISO 14001 -standardin mukainen ympäristöjärjestelmä Plastep Oy:lle. Lisäksi tarkoituksena oli suunnitella yrityksen ympäristönsuojelun tilaa mahdollisimman luotettavasti kuvaava ympäristömittari sekä tarkastella muovin ruiskuvaluyritykseen kohdistuvia tulevaisuuden näkymiä ympäristönsuojelun näkökulmasta. Opinnäytetyössä esitellään ISO 14001 -ympäristöjärjestelmä sekä kyseisen standardin sisältä...

Irradiation routine in the IPR-R1 Triga reactor

International Nuclear Information System (INIS)

Maretti Junior, F.

1980-01-01

Information about irradiations in the IPR-R1 TRIGA reactor and procedures necessary for radioisotope solicitation are presented All procedures necessary for asking irradiation in the reactor, shielding types, norms of terrestrial and aerial expeditions, payment conditions, and catalogue of disposable isotopes with their respective saturation activities are described. (M.C.K.)

Neutron density optimal control of A-1 reactor analoque model

International Nuclear Information System (INIS)

Grof, V.

1975-01-01

Two applications are described of the optimal control of a reactor analog model. Both cases consider the control of neutron density. Control loops containing the on-line controlled process, the reactor of the first Czechoslovak nuclear power plant A-1, are simulated on an analog computer. Two versions of the optimal control algorithm are derived using modern control theory (Pontryagin's maximum principle, the calculus of variations, and Kalman's estimation theory), the minimum time performance index, and the quadratic performance index. The results of the optimal control analysis are compared with the A-1 reactor conventional control. (author)

Department of Reactor Technology annual progress report 1 January - 31 December 1978

International Nuclear Information System (INIS)

1979-04-01

The activities of the department of reactor technology at Risoe during 1978 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

Reactor Engineering Department annual report (April 1, 1996 - March 31, 1997)

International Nuclear Information System (INIS)

1997-10-01

This report summarizes the research and development activities in the Reactor Engineering Department of JAERI during the fiscal year of 1996 (April 1, 1996 - March 31, 1997). The major Department's programs promoted in the year are the design activities of advanced reactor system and the development of a high power proton linear accelerator to construct an intense neutron source for innovative neutron science. Other Major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analysis, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC's fast reactor project were also progressed. The 99 papers are indexed individually. (J.P.N.)

Reactor engineering department annual report. April 1, 1993-March 31, 1994

International Nuclear Information System (INIS)

1994-11-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1993 (April 1, 1993-March 31, 1994). The major Department's programs promoted in the year are the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the research committees organized by the Department are also summarized in this report. (author)

Reactor Engineering Department annual report (April 1, 1996 - March 31, 1997)

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

This report summarizes the research and development activities in the Reactor Engineering Department of JAERI during the fiscal year of 1996 (April 1, 1996 - March 31, 1997). The major Department`s programs promoted in the year are the design activities of advanced reactor system and the development of a high power proton linear accelerator to construct an intense neutron source for innovative neutron science. Other Major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analysis, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The 99 papers are indexed individually. (J.P.N.)

Reactor engineering department annual report. April 1, 1994 - March 31, 1995

International Nuclear Information System (INIS)

1995-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1994 (April 1, 1994 - March 31, 1995). The major Department's programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

FFUSION research programme 1993-1998. Final report of the Finnish fusion research programme

Energy Technology Data Exchange (ETDEWEB)

Karttunen, S.; Heikkinen, J.; Korhonen, R. [VTT Energy, Espoo (Finland)] [and others

1998-12-31

This report summarizes the results of the Fusion Energy Research Programme, FFUSION, during the period 1993-1998. After the planning phase the programme started in 1994, and later in March 1995 the FFUSION Programme was integrated into the EU Fusion Programme and the Association Euratom-Tekes was established. Research areas in the FFUSION Programme are (1) fusion physics and plasma engineering, (2) fusion reactor materials and (3) remote handling systems. In all research areas industry is involved. Recently, a project on environmental aspects of fusion and other future energy systems started as a part of the socio-economic research (SERF) in the Euratom Fusion Programme. A crucial component of the FFUSION programme is the close collaboration between VTT Research Institutes, universities and Finnish industry. This collaboration has guaranteed dynamic and versatile research teams, which are large enough to tackle challenging research and development projects. Regarding industrial fusion R and D activities, the major step was the membership of Imatran Voima Oy in the EFET Consortium (European Fusion Engineering and Technology), which further strengthened the position of industry in the engineering design activities of ITER. The number of FFUSION research projects was 66. In addition, there were 32 industrial R and D projects. The total cost of the FFUSION Programme in 1993-1998 amounted to FIM 54 million in research at VTT and universities and an additional FIM 21 million for R and D in Finnish industry. The main part of the funding was provided by Tekes, 36%. Since 1995, yearly Euratom funding has exceeded 25%. The FFUSION research teams have played an active role in the European Programme, receiving excellent recognition from the European partners. Theoretical and computational fusion physics has been at a high scientific level and the group collaborates with the leading experimental laboratories in Europe. Fusion technology is focused on reactor materials, joining

FFUSION research programme 1993-1998. Final report of the Finnish fusion research programme

International Nuclear Information System (INIS)

Karttunen, S.; Heikkinen, J.; Korhonen, R.

1998-01-01

This report summarizes the results of the Fusion Energy Research Programme, FFUSION, during the period 1993-1998. After the planning phase the programme started in 1994, and later in March 1995 the FFUSION Programme was integrated into the EU Fusion Programme and the Association Euratom-Tekes was established. Research areas in the FFUSION Programme are (1) fusion physics and plasma engineering, (2) fusion reactor materials and (3) remote handling systems. In all research areas industry is involved. Recently, a project on environmental aspects of fusion and other future energy systems started as a part of the socio-economic research (SERF) in the Euratom Fusion Programme. A crucial component of the FFUSION programme is the close collaboration between VTT Research Institutes, universities and Finnish industry. This collaboration has guaranteed dynamic and versatile research teams, which are large enough to tackle challenging research and development projects. Regarding industrial fusion R and D activities, the major step was the membership of Imatran Voima Oy in the EFET Consortium (European Fusion Engineering and Technology), which further strengthened the position of industry in the engineering design activities of ITER. The number of FFUSION research projects was 66. In addition, there were 32 industrial R and D projects. The total cost of the FFUSION Programme in 1993-1998 amounted to FIM 54 million in research at VTT and universities and an additional FIM 21 million for R and D in Finnish industry. The main part of the funding was provided by Tekes, 36%. Since 1995, yearly Euratom funding has exceeded 25%. The FFUSION research teams have played an active role in the European Programme, receiving excellent recognition from the European partners. Theoretical and computational fusion physics has been at a high scientific level and the group collaborates with the leading experimental laboratories in Europe. Fusion technology is focused on reactor materials, joining

Modification of the IAN-R1 reactor

International Nuclear Information System (INIS)

Jaime, J.; Ahumada, S.; Spin, R.A.

1990-01-01

The IAN-R1 reactor is the only nuclear reactor operating in Colombia; it is installed at the Institute of Nuclear Affairs (AIN) in Bogota, which is an official body coming under the Ministry of Mining and Energy. This reactor started operation in January 1965 with a rated power of 10 kW and was modified a year later to operate at 20 kW, which has been its rated power up to the present. Given its importance for the application of nuclear technology in Columbia for various purposes, principally in the areas of neutron activation analysis, determination of uranium content in minerals using the delayed neutron counting method, production of certain radioisotopes such as 198 Au and 82 Br for engineering applications, and production of radioactive material for teaching and research purposes, research has been in progress for some years into ways of increasing its power. The study on experimental requirements and on the demand for locally produced radioisotopes came to the conclusion that its power should be increased to 1000 kW, which would allow the facility to remain on the same site. The modification includes conversion of the core to low-enriched fuel, operation up to 1 MW, modification of the shielding, renovation of instrumentation and installation of a radioisotope processing plant. When the reactor is modified we will be able to produce other radioisotopes for applications in nuclear medicine, industry and engineering; at the same time, the safety of the facility will be optimized and the experimental facilities improved

Measurement of β/Λ ratio in IEA-R1 reactor using noise technique

International Nuclear Information System (INIS)

Moreira, J.M.L.; Kassar, E.

1986-01-01

The ratio β/Λ for the IEA-R1 reactor is obtained experimentally through the noise analysis technique. This technique is based on the determination of the power spectral density of the reactor neutron population, with the reactor in a subcritical state driven by a 'white' neutron source. A ratio β/Λ of 43,5 s -1 is estimated from the break frequency of the measured transfer function of the IEA-R1 reactor. (Author) [pt

RPV-1: A Virtual Test Reactor to simulate irradiation effects in light water reactor pressure vessel steels

International Nuclear Information System (INIS)

Jumel, Stephanie; Van-Duysen, Jean Claude

2005-01-01

Many key components in commercial nuclear reactors are subject to neutron irradiation which modifies their mechanical properties. So far, the prediction of the in-service behavior and the lifetime of these components has required irradiations in so-called 'Experimental Test Reactors'. This predominantly empirical approach can now be supplemented by the development of physically based computer tools to simulate irradiation effects numerically. The devising of such tools, also called Virtual Test Reactors (VTRs), started in the framework of the REVE Project (REactor for Virtual Experiments). This project is a joint effort among Europe, the United States and Japan aimed at building VTRs able to simulate irradiation effects in pressure vessel steels and internal structures of LWRs. The European team has already built a first VTR, called RPV-1, devised for pressure vessel steels. Its inputs and outputs are similar to those of experimental irradiation programs carried out to assess the in-service behavior of reactor pressure vessels. RPV-1 is made of five codes and two databases which are linked up so as to receive, treat and/or convey data. A user friendly Python interface eases the running of the simulations and the visualization of the results. RPV-1 is sensitive to its inputs (neutron spectrum, temperature, ...) and provides results in conformity with experimental ones. The iterative improvement of RPV-1 has been started by the comparison of simulation results with the database of the IVAR experimental program led by the University of California Santa Barbara. These first successes led 40 European organizations to start developing RPV-2, an advanced version of RPV-1, as well as INTERN-1, a VTR devised to simulate irradiation effects in stainless steels, in a large effort (the PERFECT project) supported by the European Commission in the framework of the 6th Framework Program

Recurring Events in the Finnish Nuclear Power Plants

International Nuclear Information System (INIS)

Suksi, Seija; Olander, Ronnie; Tiippana, Petteri

2003-01-01

An analysis and evaluation of event investigation methods applied by the Radiation and Nuclear Safety Authority (STUK), and the two Finnish nuclear power plant operators Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy (Fortum) was carried out by the Technical Research Centre (VIT) on an assignment from STUK. The study aimed at providing a broad overview of the whole organisational framework to support event investigation practices at the regulatory body and at the utilities. The study was part of the IAEA Co-ordinated Research Programme (CRP) on 'Investigation of Methodologies for Incident Analysis'. The main objective of the research was to evaluate the adequacy and reliability of event investigation analysis methods and practices in the Finnish nuclear power industry and based on the results to further develop them. In general, the direct causes of identified events could be detected and eliminated, but more emphasis should be given to the prevention of recurrence of events and identification of common causes and latent failures. The study showed that the evaluated organisations had rather comprehensive incident analysis arrangements. The study also showed that more focus and prioritisation are needed. Deficiencies were identified mostly in the areas of recording, assessment and classification of new events, use of existing operating experience data, utilisation of information technology tools, and allocation of work and resources. Also the indicators or measures for the effectiveness of event investigation and operating experience feedback were missing. All organisations should maintain adequate resources in this area. The researchers suggested a more effective operating experience feedback loop. Especially more attention should be paid to root cause analysis of significant events, tasks and activities where the initial errors have occurred, and weaknesses of defensive barriers. It was also recommended that implementing periodic operational experience

Reactor engineering department annual report. April 1, 1995 - March 31, 1996

International Nuclear Information System (INIS)

1996-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The major Department's programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermalhydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermalhydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

Reactor engineering department annual report. April 1, 1994 - March 31, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1994 (April 1, 1994 - March 31, 1995). The major Department`s programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author).

Reactor Engineering Department annual report. April 1, 1997 - March 31, 1998

Energy Technology Data Exchange (ETDEWEB)

Ochiai, Masaaki; Ohnuki, Akira; Ono, Toshihiko [eds.] [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

1998-11-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1997 (April 1, 1997 - March 31, 1998). The major Department`s programs promoted in the year are the achievement of the world-strongest lasing of Free Electron Laser and the verification of the core thermal integrity during design basis events in PWRs. Other Major tasks of the Department are various basic researches on the advanced reactor system design studies, the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

Reactor Engineering Department annual report. April 1, 1997 - March 31, 1998

International Nuclear Information System (INIS)

Ochiai, Masaaki; Ohnuki, Akira; Ono, Toshihiko

1998-11-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1997 (April 1, 1997 - March 31, 1998). The major Department's programs promoted in the year are the achievement of the world-strongest lasing of Free Electron Laser and the verification of the core thermal integrity during design basis events in PWRs. Other Major tasks of the Department are various basic researches on the advanced reactor system design studies, the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC's fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

Reactor engineering department annual report. April 1, 1995 - March 31, 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The major Department`s programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermalhydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermalhydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

Present and future activities of TRIGA RC-1 Reactor

International Nuclear Information System (INIS)

Festinesi, A.

1986-01-01

A summary of reactor activities is presented and discussed. The RC-1 reactor is used by ENEA's laboratories, research institutes and national industries for different aims: research, analysis materials behaviour under neutron flux, etc. To satisfy the requests increase it is important to signalize: - the realization of a new radiochemical laboratory for radioisotopes production, to be used in a medical and/or diagnostic field in general; - the realization of a tritium handling laboratory, to study tritium solubility, release and diffusion in different material (particularly in ceramic breeder as lithium aluminate) to support Italian programs on fusion technology; - a research activity on the reactors computerized control by a console of advanced conception. The aim of this activity is the development of an ergonomic control room that could be a reference point for the planning of the power reactor control rooms

Neutronic studies in the enrichment reduction of research reactor IEAR-1

International Nuclear Information System (INIS)

Maiorino, J.R.; Fanaro, L.C.B.; Mai, L.A.; Ferreira, P.S.B.; Garone, J.G.M.

1987-01-01

In the present work the codes used by the Reactor Physics Division of IPEN-CNEN-SP in calculations for plate-type reactors are described analyzing research reactor IEAR-1. The IAEA model problem for a plate-type reactor 10 MW with high, medium and low enrichment is solved through different methodologies now in use at the RTF/IPEN-CNEN-SP (HAMMER and HAMMER-TECH-CITATION and LEO4-2DBP-UM) looking into the calculation capability for high to low enrichment conversion within the contract held with the IAEA (BRA-4661). Finally, present reactor configuration calculations are compared with experimental measurements with the aim to validate the calculation method. (Author)

Valokuvauksen voima päihdekuntoutuksessa

OpenAIRE

Nieminen, Noora

2016-01-01

Tämän projektin tarkoituksena oli toteuttaa entisille päihteidenkäyttäjille päihdekuntoutusta voimauttava valokuva - menetelmällä. Projektin tavoitteena oli, että projektin lopuksi osallistujat kokevat onnistumisen tunteita toiminnastaan ja ymmärtävät luovien menetelmien merkityksen päihdekuntoutuksen tukena. Opinnäytetyöntekijän henkilökohtaisina tavoitteina oli kehittää ohjaustaitoja, oppia voimauttava valo-kuvamenetelmästä, oppia toteuttamaan projektiluontoinen opinnäytetyö ja nähdä t...

RA Research reactor Annual report 1982 - Part 1, Operation, maintenance and utilization of the RA reactor

International Nuclear Information System (INIS)

Sotic, O.; Martinc, R.; Kozomara-Maic, S.; Cupac, S.; Radivojevic, J.; Stamenkovic, D.; Skoric, M.; Miokovic, J.

1982-12-01

Reactor test operation started in September 1981 at 2 MW power with 80% enriched fuel continued during 1982 according to the previous plan. The initial reactor core was made of 44 fuel channel each containing 10 fuel slugs. The first half of 1982 was used for the needed measurements and analysis of operating parameters and functioning of reactor systems and equipment under operating conditions. Program concerned with the testing operation at higher power levels was started in the second half of this year. It was found that the inherent excess reactivity and control rod worths ensure safe operation according to the IAEA safety standards. Excess reactivity is high enough to enable higher power level of 4.7 MW during 4 monthly cycles each lasting 15-20 days. Favourable conditions for cooling exist for the initial core configuration. Effects of poisoning at startup on the reactivity and power density distribution were measured as well as initial spatial distribution of the neutron flux which was 3,9 10 13 cm -2 s -1 at 2 MW power. Modification of the calibration coefficient in the system for automated power level control was determined. All the results show that all the safety criteria and limitations concerned with fuel utilization are fulfilled if reactor power would be 4.7 MW. Additional testing operation at 3, 4, and 4.7 MW power levels will be needed after obtaining the licence for operating at nominal power. Transition from the initial core with 44 fuel channels to the equilibrium lattice configuration with 72 fuel channels each containing 10 fuel slugs, would be done gradually. Reactor was not operated in September because of the secondary coolant pipes were exchanged between Danube and the horizontal sedimentary. Control and maintenance of the reactor equipment was done regularly and efficiently dependent on the availability of the spare parts. Difficulties in maintenance of the reactor instrumentation were caused by unavailability of the outdated spare parts

Verkkokauppa osaksi B2B-yrityksen sähköistä liike-toimintaa : case: Capcons Technology Oy

OpenAIRE

Kaitarinne, Tomi; Hannula, Tuomo

2010-01-01

Tämän opinnäytetyön tarkoituksena on kuvata monipuolisesti B2B-verkkokaupan perustamisprosessi nykyaikaisin menetelmin ja uusimpien vaatimusten mukaisesti. Opinnäytetyön case-yrityksenä toimii Capcons Technology Oy, jonka verkko-kaupan perustamisprosessissa on tarkoitus soveltaa työssä käsiteltyjä asioita. Tavoitteena on, että yritys pystyy hyödyntämään opinnäytetyötä kattavasti verkko-kaupan perustamisen eri vaiheissa. Lisäksi tätä työtä voidaan hyödyntää myös muita B2B-verkkokauppoja perust...

LASER APPLICATIONS AND OTHER TOPICS IN QUANTUM ELECTRONICS: Synthesis of bulk SiO2 : MxOy materials in a steady-state laser plume

Science.gov (United States)

Lebedev, V. F.

1997-01-01

An analysis was made of the conditions of existence of a two-component steady-state laser plume in atmospheric air. Such a plume is used in single-stage synthesis of bulk molten materials belonging to the SiO2 : MxOy system. Targets of the SiO2 : M type (metal foil and a silica glass rod) and doping elements with boiling points below and above the boiling point of silica glass are discussed. The regimes and efficiency of steady-state transfer of the dopants are considered. The efficiency of transfer of metal oxides during growth of samples with the aid of a cw CO2 laser is reported to be ~0.05, 0.4, and 0.75g min-1 kW-1 when the mass dopant concentration is ~8%, 20%, and 60% for the oxides of Ti, Cu, and Ni, respectively.

Reliabitity study of the accumulator system for Angra-1 reactor

International Nuclear Information System (INIS)

Santos Maciel, C.C.R.

1980-01-01

The realibility of the Accumulator System of Angra 1 reactor is studied. The fault tree techniques is use for identification and evaluation of the probability of occurrence of the possible failure modes of the system. The study has as a guide the report WASH 1400 in which the analysis of the reliability of a Tipical PWR reactor of USA. Comparisons between results obtained for Accumulator System of Angra 1 and that published in the report WASH 1400 for the Accumulator System of the Typical Reactor are done. Critiques to the methodology used in the reportd WASH 1400 and an analysis of the sensitivity of the system in relation with its components are also done. (author) [pt

Design of a new research reactor : 1st year conceptual design

International Nuclear Information System (INIS)

Park, Cheol; Lee, B. C.; Chae, H. T.

2004-01-01

A new research reactor model satisfying the strengthened regulatory environments and the changed circumstances around nuclear society should be prepared for the domestic and international demand of research reactor. This can also lead to the improvement of technologies and fostering manpower obtained during the construction and the operation of HANARO. In this aspect, this study has been launched and the 1st year conceptual design has been carried out in 2003. The major tasks performed at the first year of conceptual design stage are as follows; Establishments of general design requirements of research reactors and experimental facilities, Establishment of fuel and reactor core concepts, Preliminary analysis of reactor physics and thermal-hydraulics for conceptual core, Conceptual design of reactor structure and major systems, International cooperation to establish foundations for exporting

Education and research at the VR-1 Vrabec training reactor facility

International Nuclear Information System (INIS)

Matejka, K.

1993-01-01

The results of 12 years' efforts devoted to the construction of the VR-1 ''Vrabec'' training reactor at the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague and to establishing the training reactor department, as well as the contribution of the training reactor facility to the teaching and scientific activities of the Faculty are presented in a comprehensive manner. The thesis is divided into 2 parts: (i) preconditions, reactor construction and commissioning, and constituting the reactor department, and (ii) basic and comprehensive information concerning the current utilization of the reactor for the benefit of students from various university level institutions. The prospects of scientific activities of the department are also outlined. Attention is paid to selected nuclear safety aspects of the reactor during operation and teaching of students, as well as to its innovated digital control system whose implementation is planned. The results achieved are compared with the initial goals and with similar experience abroad. (P.A.)

Graphite stack corrosion of BUGEY-1 reactor (synthesis)

International Nuclear Information System (INIS)

Petit, A.; Brie, M.

1996-01-01

The definitive shutdown date for the BUGEY-1 reactor was May 27th, 1994, after 12.18 full power equivalent years and this document briefly describes some of the feedback of experience from operation of this reactor. The radiolytic corrosion of graphite stack is the major problem for BUGEY-1 reactor, despite the inhibition of the reaction by small quantities of CH 4 added to the coolant gas. The mechanical behaviour of the pile is predicted using the ''INCA'' code (stress calculation), which uses the results of graphite weight loss variation determined using the ''USURE'' code. The weight loss of graphite is determined by annually taking core samples from the channel walls. The results of the last test programme undertaken after the definitive shutdown of BUGEY-1 have enabled an experimental graph to be established showing the evolution of the compression resistance (perpendicular and parallel direction to the extrusion axis) as a function of the weight loss. The numerous analyses, made on the samples carried out in the most sensitive regions, have allowed to verify that no brutal degradation of the mechanical properties of graphite happens for the high value of weight loss up to 40% (maximum weight loss reached locally). (author). 10 refs, 3 figs, 4 tabs

Sandia reactor kinetics codes: SAK and PK1D

International Nuclear Information System (INIS)

Pickard, P.S.; Odom, J.P.

1978-01-01

The Sandia Kinetics code (SAK) is a one-dimensional coupled thermal-neutronics transient analysis code for use in simulation of reactor transients. The time-dependent cross section routines allow arbitrary time-dependent changes in material properties. The one-dimensional heat transfer routines are for cylindrical geometry and allow arbitrary mesh structure, temperature-dependent thermal properties, radiation treatment, and coolant flow and heat-transfer properties at the surface of a fuel element. The Point Kinetics 1 Dimensional Heat Transfer Code (PK1D) solves the point kinetics equations and has essentially the same heat-transfer treatment as SAK. PK1D can address extended reactor transients with minimal computer execution time

Threats and benefits updated information on local opinions regarding the spent nuclear fuel repository in Finland - 16128

International Nuclear Information System (INIS)

Kojo, Matti; Kari, Mika; Litmanen, Tapio

2009-01-01

The aim of the paper is to provide updated information on local opinion regarding the siting of a spent nuclear fuel repository in Finland. The main question is how the residents of the municipality perceive the threats and benefits of the repository. In accordance with the Decision in Principle by the Council of State passed in 2000, the Olkiluoto area in Municipality of Eurajoki was chosen as the location for the repository to accommodate spent nuclear fuel produced in Finland. Updated information on local opinions is needed as the siting process is approaching the next phase, the application for a construction license by 2012. The nuclear waste management company Posiva, owned by the utilities Teollisuuden Voima and Fortum Power and Heat, has also applied for a new Decision in Principle (DiP) for expansion of the repository. The data provided in this paper is based on a survey carried out in June 2008. The respondents were selected from the residents of the municipality of Eurajoki and the neighbouring municipalities using stratified random sampling (N=3000). The response rate of the survey was 20% (N=606). The paper is part of a joint research project between the University of Jyvaeskylae and the University of Tampere. The research project 'Follow-up research regarding socio-economic effects and communication of final disposal facility of spent nuclear fuel in Eurajoki and its neighbouring municipalities' is funded by the Finnish Research Programme on Nuclear Waste Management (KYT2010). (authors)

Ageing problems and renovation programme of ET-RR-1 reactor

International Nuclear Information System (INIS)

Khattab, M.S.; Sultan, M.A.

1995-01-01

Based on Practical Experience gained from interfacing ageing systems in addition to operating new systems, current problems could be deduced whenever in-service inspection are carried out. This paper summarizes the in-service inspection made, and the proposed programme of rehabilitation of mechanical system in the ET-RR-1 research reactor at Inshass. Exchangeable experience in solving common problems in similar reactors play an important role in the effectiveness of such rehabilitation programme. The paper summarizes also the modernization of control, measuring and radiation monitoring system already carried out at the reactor. (orig.)

Generating the flux map of Nigeria Research Reactor-1 for efficient ...

African Journals Online (AJOL)

One of the main uses to which the Nigeria Research Reactor-1 (NIRR-1) will be put is neutron activation analysis. The activation analyst requires information about the flux level at various points within and around the reactor core to enable him identify the point of optimum flux (at a given operating power) for any irradiation ...

Reactor protection system. Revision 1

International Nuclear Information System (INIS)

Fairbrother, D.B.; Vincent, D.R.; Lesniak, L.M.

1975-04-01

The reactor protection system-II (RPS-II) designed for use on Babcock and Wilcox 145- and 205-fuel assembly pressurized water reactors is described. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W. (U.S.)

RA Research nuclear reactor Part 1, RA Reactor operation and maintenance in 1987

International Nuclear Information System (INIS)

Sotic, O.; Martinc, R.; Cupac, S.; Sulem, B.; Badrljica, R.; Majstorovic, D.; Sanovic, V.

1987-01-01

RA research reacto was not operated due to the prohibition issued in 1984 by the Government of Serbia. Three major tasks were finished in order to fulfill the licensing regulations about safety of nuclear facilities which is the condition for obtaining permanent operation licence. These projects involved construction of the emergency cooling system, reconstruction of the existing special ventilation system, and renewal of the system for electric power supply of the reactor systems. Renewal of the RA reactor instrumentation system was initiated. Design project was done by the Russian Atomenergoeksport, and is foreseen to be completed by the end of 1988. The RA reactor safety report was finished in 1987. This annual report includes 8 annexes concerning reactor operation, activities of services and financial issues, and three special annexes: report on testing the emergency cooling system, report on renewal of the RA reactor and design specifications for reactor renewal and reconstruction [sr

Thirtieth anniversary of reactor accident in A-1 Nuclear Power Plant Jaslovske Bohunice

International Nuclear Information System (INIS)

Kuruc, J.; Matel, L.

2007-01-01

The facts about reactor accidents in A-1 Nuclear Power Plant Jaslovske Bohunice, Slovakia are presented. There was the reactor KS150 (HWGCR) cooled with carbon dioxide and moderated with heavy water. A-1 NPP was commissioned on December 25, 1972. The first reactor accident happened on January 5, 1976 during fuel loading. This accident has not been evaluated according to the INES scale up to the present time. The second serious accident in A-1 NPP occurred on February 22, 1977 also during fuel loading. This INES level 4 of reactor accident resulted in damaged fuel integrity with extensive corrosion damage of fuel cladding and release of radioactivity into the plant area. The A-1 NPP was consecutively shut down and is being decommissioned in the present time. Both reactor accidents are described briefly. Some radioecological and radiobiological consequences of accidents and contamination of area of A-1 NPP as well as of Manivier Canal and Dudvah River as result of flooding during the decommissioning are presented (authors)

Demolition of the FRJ-1 research reactor (MERLIN)

International Nuclear Information System (INIS)

Stahn, B.; Matela, K.; Zehbe, C.; Poeppinghaus, J.; Cremer, J.

2003-01-01

FRJ-2 (MERLIN), the swimming pool reactor cooled and moderated by light water, was built at the then Juelich Nuclear Research Establishment (KFA) between 1958 and 1962. In the period between 1964 and 1985, it was used for. The reactor was decommissioned in 1985. Since 1996, most of the demolition work has been carried out under the leadership of a project team. The complete secondary cooling system was removed by late 1998. After the cooling loops and experimental installations had been taken out, the reactor vessel internals were removed in 2000 after the water had been drained from the reactor vessel. After the competent authority had granted a license, demolition of the reactor block, the central part of the research reactor, was begun in October 2001. In a first step, the reactor operating floor and the reactor attachment structures were removed by the GNS/SNT consortium charged with overall planning and execution of the job. This phase gave rise to approx. The reactor block proper is dismantled in a number of steps. A variety of proven cutting techniques are used for this purpose. Demolition of the reactor block is to be completed in the first half of 2003. (orig.) [de

Evaporation rate measurement in the pool of IEAR-1 reactor

International Nuclear Information System (INIS)

Torres, Walmir Maximo; Cegalla, Miriam A.; Baptista Filho, Benedito Dias

2000-01-01

The surface water evaporation in pool type reactors affects the ventilation system operation and the ambient conditions and dose rates in the operation room. This paper shows the results of evaporation rate experiment in the pool of IEA-R1 research reactor. The experiment is based on the demineralized water mass variation inside cylindrical metallic recipients during a time interval. Other parameters were measured, such as: barometric pressure, relative humidity, environmental temperature, water temperature inside the recipients and water temperature in the reactor pool. The pool level variation due to water contraction/expansion was calculated. (author)

New digital control system for the operation of the Colombian research reactor IAN-R1; Nuevo sistema de control digital para la operacion del reactor de investigacion Colombiano IAN-R1

Energy Technology Data Exchange (ETDEWEB)

Celis del A, L.; Rivero, T.; Bucio, F.; Ramirez, R.; Segovia, A.; Palacios, J., E-mail: lina.celis@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2015-09-15

En 2011, Mexico won the Colombian international tender for the renewal of instrumentation and control of the IAN-R1 Reactor, to Argentina and the United States. This paper presents the design criteria and the development made for the new digital control system installed in the Colombian nuclear reactor IAN-R1, which is based on a redundant and diverse architecture, which provides increased availability, reliability and safety in the reactor operation. This control system and associated instrumentation met all national export requirements, with the safety requirements established by the IAEA as well as the requirements demanded by the Colombian Regulatory Body in nuclear matter. On August 20, 2012, the Colombian IAN-R1 reactor reached its first criticality controlled with the new system developed at Instituto Nacional de Investigaciones Nucleares (ININ). On September 14, 2012, the new control system of the Colombian IAN-R1 reactor was officially handed over to the Colombian authorities, this being the first time that Mexico exported nuclear technology through the ININ. Currently the reactor is operating successfully with the new control system, and has an operating license for 5 years. (Author)

IEA-R1 research reactor: operational life extension and considerations regarding future decommissioning

International Nuclear Information System (INIS)

Frajndlich, Roberto

2009-01-01

The IEA-R1 reactor is a pool type research reactor moderated and cooled by light water and uses graphite and beryllium reflectors. The reactor is located at the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), in the city of Sao Paulo, Brazil. It is the oldest research reactor in the southern hemisphere and one of the oldest of this kind in the world. The first criticality of the reactor was obtained on September 16, 1957. Given the fact that Brazil does not have yet a definitive radioactive waste repository and a national policy establishing rules for the spent fuel storage, the institutions which operate the research reactors for more than 50 years in the country have searched internal solutions for continued operation. This paper describes the spent fuel assemblies and radioactive waste management process for the IEA-R1 reactor and the refurbishment and modernization program adopted to extend its lifetime. Some considerations about the future decommissioning of the reactor are also discussed which, in my opinion, might help the operating organization to make decisions about financial, legal and technical aspects of the decommissioning procedures in a time frame of 10-15 years(author)

RA reactor operation and maintenance in 1992, Part 1

International Nuclear Information System (INIS)

Sotic, O.; Cupac, S.; Sulem, B.; Zivotic, Z.; Majstorovic, D.; Tanaskovic, M.

1992-01-01

During 1992 Ra reactor was not in operation. All the activities were fulfilled according to the previously adopted plan. Basic activities were concerned with revitalisation of the RA reactor and maintenance of reactor components. All the reactor personnel was busy with reconstruction and renewal of the existing reactor systems and building of the new systems, maintenance of the reactor devices. Part of the staff was trained for relevant tasks and maintenance of reactor systems [sr

Thermal hydraulic and safety analyses for Pakistan Research Reactor-1

International Nuclear Information System (INIS)

Bokhari, I.H.; Israr, M.; Pervez, S.

1999-01-01

Thermal hydraulic and safety analysis of Pakistan Research Reactor-1 (PARR-1) utilizing low enriched uranium (LEU) fuel have been performed using computer code PARET. The present core comprises of 29 standard and 5 control fuel elements. Results of the thermal hydraulic analysis show that the core can be operated at a steady-state power level of 10 MW for a flow rate of 950 m 3 /h, with sufficient safety margins against ONB (onset of nucleate boiling) and DNB (departure from nucleate boiling). Safety analysis has been carried out for various modes of reactivity insertions. The events studied include: start-up accident; accidental drop of a fuel element in the core; flooding of a beam tube with water; removal of an in-pile experiment during reactor operation etc. For each of these transients, time histories of reactor power, energy released and clad surface temperature etc. were calculated. The results indicate that the peak clad temperatures remain well below the clad melting temperature during these accidents. It is therefore concluded that the reactor can be safely operated at 10 MW without compromising safety. (author)

Spent fuel management - two alternatives at the FiR 1 reactor

International Nuclear Information System (INIS)

Salmenhaara, S.E.J.

2001-01-01

The FiR 1 -reactor, a 250 kW Triga reactor, has been in operation since 1962. The reactor with its subsystems has experienced a large renovation work in 1996-97. The main purpose of the upgrading was to install the new Boron Neutron Capture Therapy (BNCT) irradiation facility. The BNCT work dominates the current utilization of the reactor: four days per week for BNCT purposes and only one day per week for neutron activation analysis and isotope production. The Council of State (government) granted for the reactor a new operating license for twelve years starting from the beginning of the year 2000. There is however a special condition in the new license. We have to achieve a binding agreement between our Research Centre and the domestic Nuclear Power Plant Companies about the possibility to use the final disposal facility of the Nuclear Power Plants for our spent fuel, if we want to continue the reactor operation beyond the year 2006. In addition to the choosing of one of the spent fuel management alternatives the future of the reactor will also depend strongly on the development of the BNCT irradiations. If the number of patients per year increases fast enough and the irradiations of the patients will be economically justified, the operation of the reactor will continue independently of the closing of the USDOE alternative in 2006. Otherwise, if the number of patients will be low, the funding of the reactor will be probably stopped and the reactor will be shut down. (author)

Measurement of the thermal flux distribution in the IEA-R1 reactor

International Nuclear Information System (INIS)

Tangari, C.M.; Moreira, J.M.L.; Jerez, R.

1986-01-01

The knowledge of the neutron flux distribution in research reactors is important because it gives the power distribution over the core, and it provides better conditions to perform experiments and sample irradiations. The measured neutron flux distribution can also be of interest as a means of comparison for the calculational methods of reactor analysis currently in use at this institute. The thermal neutron flux distribution of the IEA-R1 reactor has been measured with the miniature chamber WL-23292. For carrying out the measurements, it was buit a guide system that permit the insertion of the mini-chamber i between the fuel of the fuel elements. It can be introduced in two diferent positions a fuel element and in each it spans 26 axial positions. With this guide system the thermal neutron flux distribution of the IEA-R1 nuclear reactor can be obtained in a fast and efficient manner. The element measured flux distribution shows clearly the effects of control rods and reflectors in the IEA-R1 reactor. The difficulties encountered during the measurements are mentioned with detail as well as the procedures adopteed to overcome them. (Author) [pt

Computer-aided testing and operational aids for PARR-1 nuclear reactor

International Nuclear Information System (INIS)

Ansari, S.A.

1990-01-01

The utilization of the plant computer of Pakistan Research Reactor (PARR-1) for automatic periodic testing of nuclear instrumentation in the reactor is described. Computer algorithms have been developed for on-line acquisition and real-time processing of nuclear channel signals. The mean value, standard deviation, and probability distributions of nuclear channel signals are obtained in real time, and the computer generates a warning message if the signal error exceeds the maximum permissible error. In this way a faulty channel is automatically identified. Other real-time algorithms are also described that assist the operator in safe reactor operation by automatically computing approach-to-criticality during reactor start-up and the control rod worth determination

Properties of autoregressive model in reactor noise analysis, 1

International Nuclear Information System (INIS)

Yamada, Sumasu; Kishida, Kuniharu; Bekki, Keisuke.

1987-01-01

Under appropriate conditions, stochastic processes are described by the ARMA model, however, the AR model is popularly used in reactor noise analysis. Hence, the properties of AR model as an approximate representation of the ARMA model should be made clear. Here, convergence of AR-parameters and PSD of AR model were studied through numerical analysis on specific examples such as the neutron noise in subcritical reactors, and it was found that : (1) The convergence of AR-parameters and AR model PSD is governed by the ''zero nearest to the unit circle in the complex plane'' (μ -1 ,|μ| M . (3) The AR model of the neutron noise of subcritical reactors needs a large model order because of an ARMA-zero very close to unity corresponding to the decay constant of the 6-th group of delayed neutron precursors. (4) In applying AR model for system identification, much attention has to be paid to a priori unknown error as an approximate representation of the ARMA model in addition to the statistical errors. (author)

On severe accident hydrogen behaviour in Loviisa

International Nuclear Information System (INIS)

Okkonen, T.

1996-02-01

This study is related to the hydrogen management strategy of the Loviisa ice-condenser containments. A synthetic survey is conducted of the various parts of the subject by using compact 'back-of-the-envelope' analysis methods. The analysed cases are consistent with the principal hydrogen management approaches proposed by the utility Imatran Voima Oy (IVO). The study begins by introduction of the Loviisa plant features and various severe accident types. Hydrogen generation characteristics are analysed mainly for the core degradation phase, but the hydrogen sources from molten fuel-coolant interactions and reflooding of a degraded core are discussed, as well. The hydrogen generation and release rates are compared with the overall gas convection and mixing conditions in order to estimate hydrogen concentrations in the containment. The natural convection currents are examined also from the scaling point of view, concerning the scaled-down VICTORIA tests of IVO. Finally, the potential for large deflagration loadings or local detonations is examined for the Loviisa containments. The study is concluded by preliminary subjective judgments about the most critical factors of the Loviisa hydrogen problematics and about any issues that may require additional confirmative research. (orig.) (47 refs., 4 figs., 24 tabs.)

On severe accident hydrogen behaviour in Loviisa

Energy Technology Data Exchange (ETDEWEB)

Okkonen, T. [OTO-Consulting Ay, Helsinki (Finland)

1996-02-01

This study is related to the hydrogen management strategy of the Loviisa ice-condenser containments. A synthetic survey is conducted of the various parts of the subject by using compact `back-of-the-envelope` analysis methods. The analysed cases are consistent with the principal hydrogen management approaches proposed by the utility Imatran Voima Oy (IVO). The study begins by introduction of the Loviisa plant features and various severe accident types. Hydrogen generation characteristics are analysed mainly for the core degradation phase, but the hydrogen sources from molten fuel-coolant interactions and reflooding of a degraded core are discussed, as well. The hydrogen generation and release rates are compared with the overall gas convection and mixing conditions in order to estimate hydrogen concentrations in the containment. The natural convection currents are examined also from the scaling point of view, concerning the scaled-down VICTORIA tests of IVO. Finally, the potential for large deflagration loadings or local detonations is examined for the Loviisa containments. The study is concluded by preliminary subjective judgments about the most critical factors of the Loviisa hydrogen problematics and about any issues that may require additional confirmative research. (orig.) (47 refs., 4 figs., 24 tabs.).

SCALE-4 analysis of pressurized water reactor critical configurations. Volume 1: Summary

International Nuclear Information System (INIS)

DeHart, M.D.

1995-03-01

The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor criticality safety analyses be validated against experimental measurements. If credit is to be taken for the reduced reactivity of burned or spent fuel relative to its original fresh composition, it is necessary to benchmark computational methods used in determining such reactivity worth against spent fuel reactivity measurements. This report summarizes a portion of the ongoing effort to benchmark away-from-reactor criticality analysis methods using critical configurations from commercial pressurized water reactors (PWR). The analysis methodology utilized for all calculations in this report is based on the modules and data associated with the SCALE-4 code system. Each of the five volumes comprising this report provides an overview of the methodology applied. Subsequent volumes also describe in detail the approach taken in performing criticality calculations for these PWR configurations: Volume 2 describes criticality calculations for the Tennessee Valley Authority's Sequoyah Unit 2 reactor for Cycle 3; Volume 3 documents the analysis of Virginia Power's Surry Unit 1 reactor for the Cycle 2 core; Volume 4 documents the calculations performed based on GPU Nuclear Corporation's Three Mile Island Unit 1 Cycle 5 core; and, lastly, Volume 5 describes the analysis of Virginia Power's North Anna Unit 1 Cycle 5 core. Each of the reactor-specific volumes provides the details of calculations performed to determine the effective multiplication factor for each reactor core for one or more critical configurations using the SCALE-4 system; these results are summarized in this volume. Differences between the core designs and their possible impact on the criticality calculations are also discussed. Finally, results are presented for additional analyses performed to verify that solutions were sufficiently converged

Spent fuel management plans for the FiR 1 Reactor

International Nuclear Information System (INIS)

Salmenhaara, S. E. J.

2002-01-01

The FiR 1-reactor, a 250 kW TRIGA reactor, has been in operation since 1962. The main purpose to run the reactor is now the Boron Neutron Capture Therapy (BNCT). The BNCT work dominates the current utilization of the reactor: three days per week for BNCT purposes and only two days per week for other purposes such as the neutron activation analysis and isotope production. The final disposal site is situated in Olkiluoto, on the western coast of Finland. Olkiluoto is also one of the two nuclear power plant sites in Finland. In the new operating license of our reactor there is a special condition. We have to achieve a binding agreement between our Research Centre and either the domestic Nuclear Power Companies about the possibility to use the Olkiluoto final disposal facility for our spent fuel or US DOE about the return of our spent fuel back to USA. If we want to continue the reactor operation beyond the year 2006. the domestic final disposal is the only possibility. At the moment it seems to be reasonable to prepare to both possibilities: the domestic final disposal and the return to the USA offered by US DOE. Because the cost estimates of the both possibilities are on the same order of magnitude, the future of the reactor itself will decide, which of the spent fuel policies will be obeyed. In a couple of years' time it will be seen, if the funding of the reactor and the incomes from the BNCT treatments will cover the costs. If the BNCT and other irradiations develop satisfactorily, the reactor can be kept in operation beyond the year 2006 and the domestic final disposal will be implemented. If, however, there is still lack of money, there is no reason to continue the operation of the reactor and the choice of US DOE alternative is natural. (author)

CRM-järjestelmän suunnittelu ja käyttöönotto myynnin strategiseksi työkaluksi : case: Stala Oy

OpenAIRE

Pirkkalainen, Markus

2013-01-01

Tämän opinnäytetyön aiheena on asiakkuudenhallinta- eli Customer Relationship Management(CRM)-järjestelmän suunnittelu ja käyttöönotto myynnin strategiseksi työkaluksi. Opinnäytetyön teoriaosuudessa tutkitaan asiakkuudenhallintaa, CRM-järjestelmiä ja CRM-järjestelmien suunnitteluun sekä käyttöönottoon liittyviä haasteita. Työn empiirinen osuus koostuu CRM-järjestelmän käyttöoppaasta kohdeyritys Stala Oy:n myyntitiimille. Tutkimusongelma vastaa kysymykseen, miksi yrityksen tulisi panostaa a...

Experimental study of the IPR-R1 TRIGA reactor power channels responses

International Nuclear Information System (INIS)

Mesquita, Henrique F.A.; Ferreira, Andrea V.

2015-01-01

The IPR-R1 nuclear reactor installed at Centro de Desenvolvimento da Tecnologia Nuclear CDTN/CNEN, Belo Horizonte, Brazil, is a Mark I TRIGA reactor (Training, Research, Isotopes, General Atomics) and became operational on November of 1960. The reactor has four irradiation devices: a rotary specimen rack with 40 irradiation channels, the central tube, and two pneumatic transfer tubes. The nuclear reactor is operated in a power range between zero and 100 kW. The instrumentation for IPR-R1 operation is mainly composed of four neutronic channels for power measurements. The aim of this work is to investigate the responses of neutronic channels of IPR-R1, Linear, Log N and Percent Power channels, and to check their linearity. Gold foils were activated at low powers (0.125-1.000 kW), and cobalt foils were activated at high powers (10-100kW). For each sample irradiated at rotary specimen rack, another one was irradiated at the same time at the pneumatic transfer tube-2. The obtained results allowed evaluating the linearity of the neutronic channels responses. (author)

Irradiation experience of IPEN fuel at IEA-R1 research reactor

International Nuclear Information System (INIS)

Perrotta, Jose A.; Neto, Adolfo; Durazzo, Michelangelo; Souza, Jose A.B. de; Frajndlich, Roberto

1998-01-01

IPEN/CNEN-SP produces, for its IEA-R1 Research Reactor, MTR fuel assemblies based on U 3 O 8 -Al dispersion fuel type. Since 1985 a qualification program on these fuel assemblies has been performed. Average 235 U burnup of 30% and peak burnup of 50% was already achieved by these fuel assemblies. This paper presents some results acquire, by these fuel assemblies, under irradiation at IEA-R1 Research Reactor. (author)

RA reactor operation and maintenance in 1996, Part 1

International Nuclear Information System (INIS)

Sotic, O.; Cupac, S.; Sulem, B.; Zivotic, Z.; Mikic, N.; Tanaskovic, M.

1996-01-01

During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The planned major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. The existing RA reactor instrumentation was dismantled. Renewal of the reactor instrumentation was started but but it is behind the schedule because the delivery of components from USSR was stopped for political reasons. Since the RA reactor is shutdown since 1984, it is high time for decision making of its future status. Possible solutions for the future status of the RA reactor discussed in this report are: renewal of reactor components for the reactor restart, conservation of the reactor (temporary shutdown) or permanent reactor shutdown. Control and maintenance of the reactor instrumentation and devices was done regularly but dependent on the availability of the spare parts and financial means. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor [sr

Possible future roles for fast breeder reactors Part 1 and 2

International Nuclear Information System (INIS)

1978-06-01

Part 1. The Fast Breeder Reactor (in particular in its sodium cooled version) has been steadily developed in the Community. This report attempts to quantify the advantages of this system in terms of fossil energy and uranium savings in the medium/long term as well as to examine some long term economic implications. The methodology of comparing scenarios, not individual reactor systems is followed. These scenarios have been chosen taking into account a range of assumptions concerning Community energy demand growth, fossil energy and uranium availability and technological capabilities. Part 2. The fast breeder reactor (FBR), particularly its sodium-cooled form (LMFBR) has been under development in the Community for many years. Industrial enterprises dedicated to its commercialisation have been formed and long range plans for its industrial utilisation are being formulated. The value of breeder reactors from the point of view of minimising Community fuel requirements has been discussed in Part I of this report (1). In Part II the consequences of delaying their introduction, and the demands placed upon the recycle industry by the introduction of fast reactors of different characteristics, using the Community electricity demand scenarios developed for Part I, are discussed. In addition comments are provided upon the effect of FBR introduction on the size of plutonium stocks

The AMPS 1.5 MW low-pressure compact reactor

International Nuclear Information System (INIS)

Hewitt, J.S.

1987-01-01

The 1.5-MWt reactor of the Autonomous Marine Power Source (AMPS) is designed to meet the unusual requirements of its first application. To provide for 100 kWe (net) on board self-sustaining manned submersible vehicles, the AMPS reactor must deliver safely, reliably and without direct operator surveillance, its thermal output to freon Rankine-cycle engines at thermodynamically useful temperatures. It must also conform to space and weight limits on the order of less than 50 cubic metres and 70 tonnes. The safety requirements are met by (i) limiting lifetime excess reactivity requirements by incorporation of burnable poison in the U-Zr-H fuel, (ii) maintaining nominal pressures in the light-water primary system at about 1 atmosphere, and (iii) maintaining a large volume of primary reserve coolant at temperature depressed relative to that of the circulating coolant. The latter averages 90 degrees celsius as it is pumped around loops that include the reactor core and the freon evaporators during normal operation. In the event of loss of pumped flow, the system defaults by intrinsic means to core cooling through natural convective exchange with the reserve coolant. In the post-shutdown situation, this passive cooling mode continues to operate regardless of vessel orientation and decay heat is safely dissipated to the sea. The design of the AMPS system, including the reactor, the freon engines, the control and monitoring system, the safety shut-down system and the power source container, are in advanced stages of design. (author)

Flux distribution measurements in the Bruce A unit 1 reactor

International Nuclear Information System (INIS)

Okazaki, A.; Kettner, D.A.; Mohindra, V.K.

1977-07-01

Flux distribution measurements were made by copper wire activation during low power commissioning of the unit 1 reactor of the Bruce A generating station. The distribution was measured along one diameter near the axial and horizontal midplanes of the reactor core. The activity distribution along the copper wire was measured by wire scanners with NaI detectors. The experiments were made for five configurations of reactivity control mechanisms. (author)

Extension of the Repository Under Excavation. The Opinions of the Local Residents in the Municipality of Eurajoki

International Nuclear Information System (INIS)

Kojo, Matti; Kari, Mika; Litmanen, Tapio

2009-12-01

The aim of the paper is to provide updated information on the opinions of residents of Eurajoki municipality concerning the disposal facility for spent nuclear fuel (SNF) in Finland. The SNF facility project is approaching the construction licence phase by 2012. At the same time as it prepares for the next phase the nuclear waste company Posiva Oy is planning to extend the disposal capacity of the facility up to 12000 tU due to the revival of nuclear energy policy in Finland. It is not only the owners of Posiva, namely Teollisuuden Voima (TVO) and Fortum Power and Heat (FPH), who need more disposal capacity. A brand new nuclear operator Fennovoima is also interested in disposing of its SNF into Posiva's facility. The possible extension of the SNF facility needs to be approved by the council of Eurajoki municipality. According to the Nuclear Energy Act the council has the right of veto. The original application of Posiva was approved by the council in 2000. According to an opinion poll 59% of the residents of the Eurajoki municipality would have accepted the siting in 1999 if the facility were found safe by the investigations of the authorities. The Olkiluoto site in the municipality of Eurajoki was chosen to be the site for further investigations in accordance with the DiP of 2000 by the Council of State. The DiP was ratified by Parliament in May 2001. Thus the local residents have lived the post site selection phase for nearly one decade. During this phase Posiva, for example, has started excavations for the Underground Rock Characterization Facility Onkalo into the bedrock of Olkiluoto. The residents have also experienced years of risk communication after the site selection of 2001. However, two recent surveys indicate that the local attitudes are showing increasing reservations rather than confidence regarding the disposal of SNF in Olkiluoto. Furthermore, data show that over 50% of the residents perceived at least an explicit threat to the health, safety and

Thermal hydraulic analysis of the IPR-R1 TRIGA reactor; Analise termo-hidraulica do reator TRIGA IPR-R1

Energy Technology Data Exchange (ETDEWEB)

Veloso, Marcelo Antonio [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); Fortini, Maria Auxiliadora [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear

2002-07-01

The subchannel approach, normally employed for the analysis of power reactor cores that work under forced convection, have been used for the thermal hydraulic evaluation of a TRIGA Mark I reactor, named IPR-R1, at 250 kW power level. This was accomplished by using the PANTERA-1P subchannel code, which has been conveniently adapted to the characteristics of natural convection of TRIGA reactors. The analysis of results indicates that the steady state operation of IPR-R1 at 250 kW do not imply risks to installations, workers and public. (author)

Pellet bed reactor for nuclear propelled vehicles: Part 1: Reactor technology

Science.gov (United States)

El-Genk, Mohamed S.

1991-01-01

The pellet bed reactor (PBR) for nuclear propelled vehicles is briefly discussed. Much of the information is given in viewgraph form. Viewgraphs include information on the layout for a Mars mission using a PBR nuclear thermal rocket, the rocket reactor layout, the fuel pellet design, materials compatibility, fuel microspheres, microsphere coating, melting points in quasibinary systems, stress analysis of microspheres, safety features, and advantages of the PBR concept.

Pellet bed reactor for nuclear propelled vehicles: Part 1: Reactor technology

International Nuclear Information System (INIS)

El-genk, M.S.

1991-01-01

The pellet bed reactor (PBR) for nuclear propelled vehicles is briefly discussed. Much of the information is given in viewgraph form. Viewgraphs include information on the layout for a Mars mission using a PBR nuclear thermal rocket, the rocket reactor layout, the fuel pellet design, materials compatibility, fuel microspheres, microsphere coating, melting points in quasibinary systems, stress analysis of microspheres, safety features, and advantages of the PBR concept

Experience and research with the IEA-R1 Brazilian reactor

International Nuclear Information System (INIS)

Fulfaro, R.; Sousa, J.A. de; Nastasi, M.J.C.; Vinhas, L.A.; Lima, F.W.

1982-06-01

The IEA-R1 reactor of the Instituto de Pesquisas Energeticas e Nucleares, IPEN, of Sao Paulo, Brazil, a lightwater moderated swimming-pool research reactor of MTR type, went critical for the first time on September 16, 1957. In a general way, in these twenty four years the reactor was utilized without interruption by users of IPEN and other institutions, for the accomplishment of work in the field of applied and basic research, for master and doctoral thesis and for technical development. Some works performed and the renewal programme established for the IEA-R1 research reactor in which several improvements and changes were made. Recent activities in terms of production of radioisotopes and some current research programm in the field of Radiochemistry are described, mainly studies and research on chemical reactions and processes using radioactive tracers and development of radioanalytical methods, such as neutron activation and isotopic dilution. The research programmes of the Nuclear Physics Division of IPEN, which includes: nuclear spectroscopy studies and electromagnetic hyperfine interactions; neutron diffraction; neutron inelastic scattering studies in condensed matter; development and application of the technique of fission track register in solid state detectors; neutron radioactive capture with prompt gamma detection and, finally, research in the field of nuclear metrology, are presented. (Author) [pt

Experience and research with the IEA-R1 Brazilian reactor

International Nuclear Information System (INIS)

Fulfaro, R.; Sousa, J.A. de; Nastasi, M.J.C.; Vinhas, L.A.; Lima, F.W. de.

1982-06-01

The IEA-R1 reactor of the Instituto de Pesquisas Energeticas e Nucleares, IPEN, of Sao Paulo, Brazil, a lighwater moderated swimming-pool research reactor of MTR type, went critical for the first time on September 16, 1957. In a general way, in these twenty four years the reactor was utilized without interruption by users of IPEN and other institutions, for the accomplishment of work in the field of applied and basic research, for master and doctoral thesis and for technical development. Some works performed and the renewal programme established for the IEA-R1 research reactor in which several improvements and changes were made. Recent activities in terms of production of radioisotopes and some current research programm in the field of Radiochemistry are described, mainly studies and research on chemical reactions and processes using radioactive tracers and development of radioanalytical methods, such as neutron activation and isotopic dilution. It is also presented the research programmes of the Nuclear Physics Division of IPEN, which includes: nuclear spectroscopy studies and electromagnetic hyperfine interactions; neutron diffraction; neutron inelastic scattering studies in condensed matter; development and application of the technique of fission track register in solid state detectors; neutron radioactive capture with prompt gamma detection and, finally, research in the field of nuclear metrology. (Author) [pt

Decorative black TiCxOy film fabricated by DC magnetron sputtering without importing oxygen reactive gas

Science.gov (United States)

Ono, Katsushi; Wakabayashi, Masao; Tsukakoshi, Yukio; Abe, Yoshiyuki

2016-02-01

Decorative black TiCxOy films were fabricated by dc (direct current) magnetron sputtering without importing the oxygen reactive gas into the sputtering chamber. Using a ceramic target of titanium oxycarbide (TiC1.59O0.31), the oxygen content in the films could be easily controlled by adjustment of total sputtering gas pressure without remarkable change of the carbon content. The films deposited at 2.0 and 4.0 Pa, those are higher pressure when compared with that in conventional magnetron sputtering, showed an attractive black color. In particular, the film at 4.0 Pa had the composition of TiC1.03O1.10, exhibited the L* of 41.5, a* of 0.2 and b* of 0.6 in CIELAB color space. These values were smaller than those in the TiC0.29O1.38 films (L* of 45.8, a* of 1.2 and b* of 1.2) fabricated by conventional reactive sputtering method from the same target under the conditions of gas pressure of 0.3 Pa and optimized oxygen reactive gas concentration of 2.5 vol.% in sputtering gas. Analysis of XRD and XPS revealed that the black film deposited at 4.0 Pa was the amorphous film composed of TiC, TiO and C. The adhesion property and the heat resisting property were enough for decorative uses. This sputtering process has an industrial advantage that the decorative black coating with color uniformity in large area can be easily obtained by plain operation because of unnecessary of the oxygen reactive gas importing which is difficult to be controlled uniformly in the sputtering chamber.

CAC-RA1 1958-1998. The first years of the Constituyentes Atomic Center (CAC). History of the first Argentine nuclear reactor (RA-1); CAC-RA-1 1958-1998. Los primeros anios del CAC. Historia del primer reactor nuclear argentino (RA-1)

Energy Technology Data Exchange (ETDEWEB)

Forlerer, Elena; Palacios, Tulio A [comps.

1998-07-01

After giving the milestones of the development of the Constituyentes Atomic Center since 1957, the history of the construction of the first nuclear reactor (RA-1) in Argentina, including the local fabrication of its fuel elements, is surveyed. The RA-1 reached criticality on January 17, 1958. The booklet commemorates the 40th year of the reactor operation.

Benchmark testing of Canadol-2.1 for heavy water reactor

International Nuclear Information System (INIS)

Liu Ping

1999-01-01

The new version evaluated nuclear data library of ENDF-B 6.5 has been released recently. In order to compare the quality of evaluated nuclear data CENDL-2.1 with ENDF-B 6.5, it is necessary to do benchmarks testing for them. In this work, CENDL-2.1 and ENDF-B 6.5 were used to generated the WIMS-69 group library respectively, and benchmarks testing was done for the heavy water reactor, using WIMS5A code. It is obvious that data files of CENDL-2.1 is better than that of old WIMS library for the heavy water reactors calculations, and is in good agreement with those of ENDF-B 6.5

Reactivity feedback coefficients Pakistan research reactor-1 using PRIDE code

Energy Technology Data Exchange (ETDEWEB)

Mansoor, Ali; Ahmed, Siraj-ul-Islam; Khan, Rustam [Pakistan Institute of Engineering and Applied Sciences, Islamabad (Pakistan). Dept. of Nuclear Engineering; Inam-ul-Haq [Comsats Institute of Information Technology, Islamabad (Pakistan). Dept. of Physics

2017-05-15

Results of the analyses performed for fuel, moderator and void's temperature feedback reactivity coefficients for the first high power core configuration of Pakistan Research Reactor - 1 (PARR-1) are summarized. For this purpose, a validated three dimensional model of PARR-1 core was developed and confirmed against the reference results for reactivity calculations. The ''Program for Reactor In-Core Analysis using Diffusion Equation'' (PRIDE) code was used for development of global (3-dimensional) model in conjunction with WIMSD4 for lattice cell modeling. Values for isothermal fuel, moderator and void's temperature feedback reactivity coefficients have been calculated. Additionally, flux profiles for the five energy groups were also generated.

Use of self powered neutron detectors in the IEA-R1 reactor

International Nuclear Information System (INIS)

Galo Rocha, F. del.

1989-01-01

A survey of self-powered neutron detectors, SPND, which are used as part of the in-core instrumentation of nuclear reactors is presented. Measurements with Co and Er SPND's were made in the IEA-R1 reactor for determining the neutron flux distribution and the integral reactor power. Due to the size of the available detectors, the neutron flux distribution could not be obtained with accuracy. The results obtained in the reactor power measurements demonstrate that the SPND have the linearity and the quick response necessary for a reactor power channel. This work also presents a proposed design of a SPND using Pt as wire emissor. This proposed design is based in the experience gained in building two prototypes. The greatest difficulties encountered include materials and technology to perform the delicate weldings. (author)

Status of prompt gamma neutron activation analysis (PGAA) at TRR-1/M1 (Thai Research Reactor-1/Modified 1)

Energy Technology Data Exchange (ETDEWEB)

Asvavijnijkulchai, Chanchai; Dharmavanij, Wanchai; Siangsanan, Pariwat; Ratanathongchai, Wichian; Chongkum, Somporn [Physics Division, Office of Atomic Energy for Peace, Vibhavadi Rangsit Road, Chatuchak, Bangkok (Thailand)

1999-08-01

The first prompt gamma activation analysis (PGAA) was designed, constructed and installed at a 6 inch diameter neutron beam port of the Thai Research Reactor-1/Modified 1 (TRR-1/M1) since 1989. Beam characteristic were made by Gd foil irradiation, X-ray film exposing and densitometry scanning consequently. The thermal neutron flux at sample position was measured by Au foil activation, and was about 1 x 10{sup 7} n.cm{sup 2}.sec{sup -1} at 700 kW operating power. The experiments have been conducted successfully. In 1998, the PGAA facility has been developed for the reactor operating power at 1.2 MW. The new PGAA system, e.g., beam shutter, gamma collimator and biological shields have been designed to reduce the leakage of neutrons and gamma radiation to the acceptance levels in accordance with the International Commission on Radiation Protection Publication 60 (ICRP 60). The construction and installation will be completed in April 1999. (author)

Status of prompt gamma neutron activation analysis (PGAA) at TRR-1/M1 (Thai Research Reactor-1/Modified 1)

International Nuclear Information System (INIS)

Asvavijnijkulchai, Chanchai; Dharmavanij, Wanchai; Siangsanan, Pariwat; Ratanathongchai, Wichian; Chongkum, Somporn

1999-01-01

The first prompt gamma activation analysis (PGAA) was designed, constructed and installed at a 6 inch diameter neutron beam port of the Thai Research Reactor-1/Modified 1 (TRR-1/M1) since 1989. Beam characteristic were made by Gd foil irradiation, X-ray film exposing and densitometry scanning consequently. The thermal neutron flux at sample position was measured by Au foil activation, and was about 1 x 10 7 n.cm 2 .sec -1 at 700 kW operating power. The experiments have been conducted successfully. In 1998, the PGAA facility has been developed for the reactor operating power at 1.2 MW. The new PGAA system, e.g., beam shutter, gamma collimator and biological shields have been designed to reduce the leakage of neutrons and gamma radiation to the acceptance levels in accordance with the International Commission on Radiation Protection Publication 60 (ICRP 60). The construction and installation will be completed in April 1999. (author)

Reactor inventory monitoring system for Angra-1 reactor

International Nuclear Information System (INIS)

S Neto, Joaquim A.; Silva, Marcos C.; Pinheiro, Ronaldo F.M.; Soares, Milton; Martinez, Aquilino; Comerlato, Cesar A.; Oliveira, Eugenio A.

1996-01-01

This work describes the project of Reactor Inventory Monitoring System, which will be installed in Angra I Nuclear Power Plant. The inventory information is important to the operators take corrective actions in case of an incident that may cause a failure in the core cooling. (author)

Modifications done in the IPR-R1 reactor and their auxiliary systems

International Nuclear Information System (INIS)

Maretti Junior, F.; Amorim, V.A. de; Coura, J.G.

1986-01-01

The improvements done in the IPR-R1 reactor for adequateness of operation conditions and increase of irradiation sample capability. The cooling systems, reactor pool, system of control rods were substituted. The optimization of transfer pneumatic system was done. (M.C.K.) [pt

Proceedings of 2. Yugoslav symposium on reactor physics, Part 1, Herceg Novi (Yugoslavia), 27-29 Sep 1966

International Nuclear Information System (INIS)

1966-01-01

This Volume 1 of the Proceedings of 2. Yugoslav symposium on reactor physics includes nine papers dealing with the following topics: reactor kinetics, reactor noise, neutron detection, methods for calculating neutron flux spatial and time dependence in the reactor cores of both heavy and light water moderated experimental reactors, calculation of reactor lattice parameters, reactor instrumentation, reactor monitoring systems; measuring methods of reactor parameters; reactor experimental facilities

Thai research reactor

International Nuclear Information System (INIS)

Aramrattana, M.

1987-01-01

The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

Continuous backfitting measures for the FRG-1 and FRG-2 research reactors

International Nuclear Information System (INIS)

Blom, K.H.; Falck, K.; Krull, W.

1990-01-01

The GKSS-Research Centre Geesthacht GmbH has been operating the research reactors FRG-1 and FRG-2 with power levels of 5 MW and 15 MW for 31 and 26 years respectively. Safe operation at full power levels over so many years with an average utilization between 180 d to 250 d per year is possible only with great efforts in modernization and upgrading of the research reactors. Emphasis has been placed on backfitting since around 1975. At that time within the Federal Republic of Germany many new guidelines, rules, ordinances, and standards in the field of (power) reactor safety were published. Much work has been done on the modernization of the FRG-1 and FRG-2 research reactors therefore within the last ten years. Work done within the last two years and presently underway includes: measures against water leakage through the concrete and along the beam tubes; repair of both cooling towers; modernization of the ventilation system; measures for fire protection; activities in water chemistry and water quality; installation of a double tubing for parts of the primary piping of the FRG-1; replacement of instrumentation, process control systems (operation and monitoring system) and alarm system; renewal of the emergency power supply; installation of internal lightning protection; installation of a cold neutron source; enrichment reduction for FRG-1. These efforts will continue to allow safe operation of our research reactors over their whole operational life

Dose measurements in controlled area of TRIGA IPR-R1 reactor

International Nuclear Information System (INIS)

Alvarenga, F.L.; Junior, F.M.

2005-01-01

The workers doses in exposure areas to the radiation are so important for a Radioprotection Quality Program, as well as to guarantee the workers safety. For that it is necessary to raise the doses in the radiation areas, to obtain the accumulated dose in certain procedures for detailed studies. Several risings were accomplished to obtain the radiation levels in the areas where the workers are exposed due the operation of a research nuclear reactor and in the radioisotopes manipulation laboratories of a nuclear institute. The radiation levels and doses can be observed through graphs in the dependences of the Controlled Area 1 (AC-1) and the Reactor Laboratory. Those limits are in according of the CNEN-NE-3.01 work limits rules. The conclusion of the work allowed to demonstrate that the Laboratory of the Reactor and AC-1, have booth an effective radiological program with efficient operational practices that contributes with low doses to the workers

Demolition of the FRJ-1 research reactor (MERLIN); Abbau des Reaktorblocks des Forschungsreaktors FRJ-1 (MERLIN)

Energy Technology Data Exchange (ETDEWEB)

Stahn, B.; Matela, K.; Zehbe, C. [Forschungszentrum Juelich GmbH (Germany); Poeppinghaus, J. [Gesellschaft fuer Nuklearservice, Essen (Germany); Cremer, J. [SNT Siempelkamp Nukleartechnik, Heidelberg (Germany)

2003-06-01

FRJ-2 (MERLIN), the swimming pool reactor cooled and moderated by light water, was built at the then Juelich Nuclear Research Establishment (KFA) between 1958 and 1962. In the period between 1964 and 1985, it was used for. The reactor was decommissioned in 1985. Since 1996, most of the demolition work has been carried out under the leadership of a project team. The complete secondary cooling system was removed by late 1998. After the cooling loops and experimental installations had been taken out, the reactor vessel internals were removed in 2000 after the water had been drained from the reactor vessel. After the competent authority had granted a license, demolition of the reactor block, the central part of the research reactor, was begun in October 2001. In a first step, the reactor operating floor and the reactor attachment structures were removed by the GNS/SNT consortium charged with overall planning and execution of the job. This phase gave rise to approx. The reactor block proper is dismantled in a number of steps. A variety of proven cutting techniques are used for this purpose. Demolition of the reactor block is to be completed in the first half of 2003. (orig.) [German] Der mit Leichtwasser gekuehlte und moderierte Schwimmbad-Forschungsreaktor FRJ-2 (MERLIN) wurde von 1958 bis 1962 fuer die damalige Kernforschungsanlage Juelich (KFA) errichtet. Von 1964 bis 1985 wurde er fuer Experimente mit zunaechst 5 MW und spaeter 10 MW thermischer Leistung bei einem maximalen thermischen Neutronenfluss von 1,1.10{sup 14} n/cm{sup 2}s genutzt. Im Jahr 1985 stellte der Reaktor seinen Betrieb ein. Die Brennelemente wurden aus der Anlage entfernt und in die USA und nach Grossbritannien verbracht. Seit 1996 erfolgen die wesentlichen Abbautaetigkeiten unter Leitung eines verantwortlichen Projektteams. Bis Ende 1998 wurde das komplette Sekundaerkuehlsystem entfernt. Dem Abbau der Kuehlkreislaeufe und Experimentiereinrichtungen folgte im Jahr 2000 der Ausbau der

Equipment for neutron measurements at VR-1 Sparrow training reactor

International Nuclear Information System (INIS)

Kolros, Antonin; Huml, Ondrej; Kos, Josef

2008-01-01

Full text: The VR-1 Sparrow training reactor is the experimental nuclear facility especially employed for education and teaching of students from different technical universities in the Czech Republic and other countries. Since 2005 the uniform all-purpose devices EMK310 have been used for measurement at reactor laboratory with different type of gas filled neutron detectors. The neutron detection system are employed for reactivity measurement, control rod calibration, critical experiment, study of delayed neutrons, study of nuclear reactor dynamics and study of detection systems dead time. The small dimension isotropic detectors are especially used for measurement of thermal neutron flux distribution inside the reactor core. The EMK-310 is a high performance, portable, three-channel fast amplitude analyzer designed for counting applications. It was developed for nuclear applications and made in close co-operation with firm TEMA Ltd. The precise rack eliminates electromagnetic disturbance and contains the control unit and four modules. The modules of high voltage supply and amplifier for gas filled detectors or scintillation probes are used in basic configuration. Software is tailored specifically to the reactor measurement and allows full online control. For applications involving the study of signals that may vary with the time, example study of delayed neutrons or nuclear reactor dynamics, the EMK-310 provides a Multichannel Scaling (MCS) acquisition mode. MCS dwell time can be set from 2 ms. Now, the new generation of digital multichannel analyzers DA310 is introduced. They have similarly attributes as EMK310 but the output information of unipolar signals from detector is more complete. The pipeline A/D converter with field programmable gate array (FPGA) is the hearth of the DA310 device. The resolution is 12 bits (4096 channels); the sample frequency is 80 MHz. The application for the neutron noise analysis is supposed. The correction method for non linearity

Report on safety related occurrences and reactor trips July 1, 1979 - December 31, 1979

International Nuclear Information System (INIS)

Olsson, S.; Andermo, L.

1980-01-01

This is a report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1 to December 31, 1979 inclusive. The facilities involved are Barsebaeck 1 and 2, Oskarshamn 1 and 2 and Ringhals 1 and 2. During this period of 6 months 76 safety related occurrences and 27 reactor trips have been reported to the Nuclear Power Inspectorate. It is to the greatest extent conventional components such as valves and pumps which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant system and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The total number of reactor trips are normal. The average value for these 6 months is 4.5 trips/unit. Approximetely one half of the reactor trips happened at zero or very low power operation. The fact that even small deviations from prescribed operation result in an automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The greatest outages are caused by occurrences without safety significance. (author)

RA Research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1986

International Nuclear Information System (INIS)

Sotic, O.; Martinc, R.; Cupac, S.; Sulem, B.; Badrljica, R.; Majstorovic, D.; Sanovic, V.

1986-01-01

In order to enable future reliable operation of the RA reactor, according to new licensing regulations, three major tasks started in 1984 were fulfilled: building of the new emergency system, reconstruction of the existing ventilation system, and reconstruction of the power supply system. Simultaneously in 1985/1986 renewal of the instrumentation and reconstruction of the system for handling and storage of the spent fuel in the reactor building have started. Design projects for these tasks are almost finished and the reconstruction of both systems is expected to be finished until 1988 and mid 1989 respectively. RA reactor Safety report was finished according to the recommendations of the IAEA. Investments in 1986 were used for 8000 kg of heavy water, maintenance of reactor systems and supply of new components, reconstruction of reactor systems. This report includes 8 annexes concerning reactor operation, activities of services and financial issues [sr

Communications highlights of the Finnish nuclear industry in 1997

International Nuclear Information System (INIS)

Heininen-Ojanperae, Marke

1998-01-01

Full text: The Poster will contain two major issues i.e. description of the information Centre Renovation Project at Loviisa Power Plant and a presentation with material of the Sunray III Project. The Sunray Project: The Sunray Project is a national radiation project intended for all ninth graders in the Finnish school system. The project started two years ago. Attention has been focused on the topic of radiation. The topic has been dealt with in connection with different subject as history, English, Swedish, French, Finnish, mathematics, physics, chemistry, geography, health and home economics, as well as vocational counselling. The aim of the project is to provide extensive information on the subject of radiation and radioactivity, to investigate benefits and disadvantages and to help pupils understand units and see things in correct proportions. Sunray I focused on radon, Sunray II on light. Sunray III will start this autumn and its main theme will be risk perception. The programme of the Sunray III is structured as follows: Part One: Articles on risk provided by experts from different fields. Part Two: A risk management game Part Three: A special view on natural radiation. The project is coordinated by Economic Information Bureau in cooperation with the Finnish Centre for Radiation and Nuclear Safety and two major power companies Imatran Voima and Teollisuuden Voima. The coordinator of the Sunray III Project is Mr. Matti Lattu. The Information Centre Renovation Project (ICRP) The ICRP has been a two-year project which was completed for the 20th anniversary celebration of Loviisa Nuclear Power Plant in February 1997. The main emphasis was to harness the local natural environment as much as possible. The focal point of the project was presented by a new, large-sized map as a water-colour painting (a printed version), a bird-eye view of the Haestholinen Island environment. The information signs system was completely renewed. A large sea-water aquarium containing

Progress in the neutronic core conversion (HEU-LEU) analysis of Ghana research reactor-1.

Energy Technology Data Exchange (ETDEWEB)

Anim-Sampong, S.; Maakuu, B. T.; Akaho, E. H. K.; Andam, A.; Liaw, J. J. R.; Matos, J. E.; Nuclear Engineering Division; Ghana Atomic Energy Commission; Kwame Nkrumah Univ. of Science and Technology

2006-01-01

The Ghana Research Reactor-1 (GHARR-1) is a commercial version of the Miniature Neutron Source Reactor (MNSR) and has operated at different power levels since its commissioning in March 1995. As required for all nuclear reactors, neutronic and thermal hydraulic analysis are being performed for the HEU-LEU core conversion studies of the Ghana Research Reactor-1 (GHARR-1) facility, which is a commercial version of the Miniature Neutron Source Reactor (MNSR). Stochastic Monte Carlo particle transport methods and tools (MCNP4c/MCNP5) were used to fine-tune a previously developed 3-D MCNP model of the GHARR-1 facility and perform neutronic analysis of the 90.2% HEU reference and candidate LEU (UO{sub 2}, U{sub 3}Si{sub 2}, U-9Mo) fresh cores with varying enrichments from 12.6%-19.75%. In this paper, the results of the progress made in the Monte Carlo neutronic analysis of the HEU reference and candidate LEU fuels are presented. In particular, a comparative performance assessment of the LEU with respect to neutron flux variations in the fission chamber and experimental irradiation channels are highlighted.

RA Research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1988

International Nuclear Information System (INIS)

Sotic, O.; Martinc, R.; Cupac, S.; Sulem, B.; Badrljica, R.; Majstorovic, D.; Sanovic, V.

1988-01-01

According to the action plan for 1988, operation of the RA reactor should have been restarted in October, but the operating license was not obtained. Control and maintenance of the reactor components was done regularly and efficiently dependent on the availability of the spare parts. The major difficulty was maintenance of the reactor instrumentation. Period of the reactor shutdown was used for repair of the heavy water pumps in the primary coolant loop. With the aim to ensure future safe and reliable reactor operation, action were started concerning renewal of the reactor instrumentation. Design project was done by the soviet company Atomenergoeksport. The contract for constructing this equipment was signed, and it is planned that the equipment will be delivered by the end of 1990. In order to increase the space for storage of the irradiated fuel elements and its more efficient usage, projects were started concerned with reconstruction of the existing fuel handling equipment, increase of the storage space and purification of the water in the fuel storage pools. These projects are scheduled to be finished in mid 1989. This report includes 8 annexes concerning reactor operation, activities of services and financial issues [sr

IPR-R1 TRIGA research reactor decommissioning plan

International Nuclear Information System (INIS)

Andrade Grossi, Pablo; Oliveira de Tello, Cledola Cassia; Mesquita, Amir Zacarias

2008-01-01

The International Atomic Energy Agency (IAEA) is concerning to establish or adopt standards of safety for the protection of health, life and property in the development and application of nuclear energy for peaceful purposes. In this way the IAEA recommends that decommissioning planning should be part of all radioactive installation licensing process. There are over 200 research reactors that have either not operated for a considerable period of time and may never return to operation or, are close to permanent shutdown. Many countries do not have a decommissioning policy, and like Brazil not all installations have their decommissioning plan as part of the licensing documentation. Brazil is signatory of Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, but until now there is no decommissioning policy, and specifically for research reactor there is no decommissioning guidelines in the standards. The Nuclear Technology Development Centre (CDTN/CNEN) has a TRIGA Mark I Research Reactor IPR-R1 in operation for 47 years with 3.6% average fuel burn-up. The original power was 100 k W and it is being licensed for 250 k W, and it needs the decommissioning plan as part of the licensing requirements. In the paper it is presented the basis of decommissioning plan, an overview and the end state / final goal of decommissioning activities for the IPR-R1, and the Brazilian ongoing activities about this subject. (author)

The Chernobyl reactor accident. Pt. 1 and 2

International Nuclear Information System (INIS)

1986-06-01

The report first summarizes the available information on the various incidents of the whole accident scenario, and combines the information to present a first general outline and a basis for appraisal. The most significant incidents reported, namely power excursion, core meltdown, and fire, are discussed with a view to the reactor design and safety of reactors installed in the FRG. The main differences and advantages of German reactor designs are shown, as e.g.: Power excursions are mastered by inherent physical conditions; far better redundancy of engineered safety systems; enclosure of the complete reactor cooling system in a pressure-retaining steel containment; reactor buildings being made of reinforced concrete. The second part of the report deals with the radiological effects to be expected for our country. Data are given on the varying radiological exposure of the different regions. The fate and uptake of radioactivity in the human body are discussed. The conclusion drawn from the data presented is that the individual exposure due to the reactor accident will remain within the variations and limits of natural radioactivity and effects. (orig./HP) [de

Current activities at the FiR 1 TRIGA reactor

International Nuclear Information System (INIS)

Salmenhaara, Seppo

2002-01-01

The FiR 1 -reactor, a 250 kW Triga reactor, has been in operation since 1962. The main purpose to run the reactor is now the Boron Neutron Capture Therapy (BNCT). The epithermal neutrons needed for the irradiation of brain tumor patients are produced from the fast fission neutrons by a moderator block consisting of Al+AlF 3 (FLUENTAL), which showed to be the optimum material for this purpose. Twenty-one patients have been treated since May 1999, when the license for patient treatment was granted to the responsible BNCT treatment organization. The treatment organization has a close connection to the Helsinki University Central Hospital. The BNCT work dominates the current utilization of the reactor: three days per week for BNCT purposes and only two days per week for other purposes such as the neutron activation analysis and isotope production. In the near future the back end solutions of the spent fuel management will have a very important role in our activities. The Finnish Parliament ratified in May 2001 the Decision in Principle on the final disposal facility for spent fuel in Olkiluoto, on the western coast of Finland. There is a special condition in our operating license. We have now about two years' time to achieve a binding agreement between VTT and the Nuclear Power Plant Companies about the possibility to use the final disposal facility of the Nuclear Power Plants for our spent fuel. If this will not happen, we have to make the agreement with the USDOE with the well-known time limits. At the moment it seems to be reasonable to prepare for both spent fuel management possibilities: the domestic final disposal and the return to the USA offered by USDOE. Because the cost estimates of the both possibilities are on the same order of magnitude, the future of the reactor itself will determine, which of the spent fuel policies will be obeyed. In a couple of years' time it will be seen, if the funding of the reactor and the incomes from the BNC treatments will cover

Käyttäjäystävällisen SharePoint 2013 -ohjeen laatiminen : Case VisualWeb Group Oy

OpenAIRE

Pynttäri, Henna

2014-01-01

Tässä toimintakeskeisessä opinnäytetyössä suunniteltiin ja toteutettiin VisualWeb Group Oy :n asiakkaille käyttäjäystävällinen ohje SharePoint 2013 -alustan käyttöön. Manuaali on suunnattu peruskäyttäjille, ja se sisältää ohjeet sellaisista toiminnoista, joita käyttäjä tarvitsee aloittaessaan SharePoint-alustan päälle rakennetun sivustonsa päivittämisen. Päätavoitteena oli laatia käyttöohjeesta mahdollisimman selkeä ja yksinkertainen, koska se on suunnattu käyttäjäryhmälle, jolla on vähän tai...

Insertion of reactivity (RIA) without scram in the reactor core IEA-R1 using code PARET

International Nuclear Information System (INIS)

Alves, Urias F.; Castrillo, Lazara S.; Lima, Fernando A.

2013-01-01

The modeling and analysis thermo hydraulics of a research reactor with MTR type fuel elements - Material Testing Reactor - was performed using the code PARET (Program for the Analysis of Reactor Transients) when in the system some external event is introduced that changed the reactivity in the reactor core. Transients of Reactivity Insertion of 0.5 , 1.5 and 2.0$/ 0.7s in the brazilian reactor IEA-R1 will be presented, and will be shown under what conditions it is possible to ensure the safe operation of its nucleus. (author)

Expanding the storage capability at ET-RR-1 research reactor at Inshass

International Nuclear Information System (INIS)

Sultan, Mariy M.; Khattab, M.

1999-01-01

Storing of spent fuel from Test Reactor in developing countries has become a big dilemma for the following reasons: The transportation of spent fuel is very expensive; There are no reprocessing plants in most developing countries; The expanding of existing storage facilities in reactor building require experience that most of developing countries lack; Some political motivations from Nuclear Developed countries intervene which makes the transportation procedures and logistics to those countries difficult. This paper gives the conceptual design of a new spent fuel storage now under construction at Inshass research reactor (ET-RR-1). The location of the new storage facility is chosen to be within the premises of the reactor facility so that both reactor and the new storage are one Material Balance Area. The paper also proposes some ideas that can enhance the transportation and storage of spent fuel of test reactors, such as: Intensifying the role of IAEA in helping countries to get rid of the spent fuel; The initiation of regional spent fuel storage facilities in some developing countries. (author)

Licensing of the first reload of Angra-1 reactor

International Nuclear Information System (INIS)

Alvarenga, M.A.B.

1985-01-01

The historical aspects related to the licensing of the first reload of Angra-1 reactor are presented. The dates, the institutions, the experts, as well as the documents generated during that process are presented. (M.I.)

Evaluation of the trial design studies for an advanced marine reactor, (1)

International Nuclear Information System (INIS)

1988-03-01

The trial design of three type reactors, semi-integrated, integrated and integrated (self-pressurized) type, was carried out in order to clarify the reactor type for the advanced marine reactor that would be developed for its realization in future and in order to extract its research and development theme. The trial design was carried and finished as for the three type reactors in same specifications in order to improve the following characteristics, small in size, light in weight, high in safety and reliability, and economic. In this report, a comparison and review of the following items are described as for the above three type reactors, (1) specifications, (2) shielding, (3) refueling, (4) in-service inspection, (5) analysis of the transients and accidents, (6) piping systems, (7) control systems, (8) dynamic analysis, (9) overall comparison, (10) research and development theme and theme for study in future. (author)

Transformation of 1,1,1-trichloroethane in an anaerobic packed-bed reactor at various concentrations of 1,1,1-trichloroethane, acetate and sulfate

NARCIS (Netherlands)

deBest, JH; Jongema, H; Weijling, A; Doddema, HJ; Janssen, DB; Harder, W

Biotransformation of 1,1,1-trichloroethane (CH3CCl3) was observed in an anaerobic packed-bed reactor under conditions of both sulfate reduction and methanogenesis. Acetate (1 mM) served as an electron donor. CH3CCl3 was completely converted up to the highest investigated concentration of 10 mu M.

Evaluation of power behavior during startup and shutdown procedures of the IPR-R1 Triga Reactor

International Nuclear Information System (INIS)

Zangirolami, Dante M.; Mesquita, Amir Z.; Ferreira, Andrea V.

2009-01-01

The IPR-R1 nuclear reactor of Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN is a TRIGA Mark I pool type reactor cooled by natural circulation of light water. In the IPR-R1, the power is measured by four nuclear channels, neutron-sensitive chambers, which are mounted around the reactor core: the Startup Channel for power indication during reactor startup; the Logarithmic Wide Range Power Monitoring Channel; the Linear Multi-Range Power Monitoring Channel and the Percent Power Safety Channel. A data acquisition system automatically does the monitoring and storage of all the reactor operational parameters including the reactor power. The startup procedure is manual and the time to reach the desired reactor power level is different on each irradiation which may introduces differences in induced activity of samples irradiated in different irradiations. In this work, the power evolution during startup and shutdown periods of IPR-R1 operation was evaluated and the mean values of reactor energy production in these operational phases were obtained. The analyses were performed on basis of the Linear Multi-Range Channel data. The results show that the sum of startup and shutdown periods corresponds to 1% of released energy for irradiations during 1h at 100kW. This value may be useful to correct experimental data in neutron activation experiments. (author)

Modernization of Safety and Control Instrumentation of the IEA-R1 Research Reactor

Energy Technology Data Exchange (ETDEWEB)

De Carvalho, P.V., E-mail: paulov@ien.gov.br [Institute of Nuclear Engineering (IEN), National Nuclear Energy Commission (CNEN), Rio de Janeiro (Brazil)

2014-08-15

The research reactor IEA-R1 located in the Institute of Energy and Nuclear Research (IPEN), São Paulo, Brazil, obtained its first criticality on 16 September 1957 and since then has served the scientific and medical community in the performance of experiments in applied nuclear physics, as well as the provision of radioisotopes for production of radiopharmaceuticals. The reactor produces radioisotopes {sup 82}Br and {sup 41}Ar for special processes in industrial inspection and {sup 192}Ir and {sup 198}Au as sources of radiation used in brachytherapy, {sup 153}Sm for pain relief in patients with bone metastasis, and calibrated sources of {sup 133}Ba, {sup 137}Cs, {sup 57}Co, {sup 60}Co, {sup 241}Am and {sup 152}Eu used in medical clinics and hospitals practicing nuclear medicine and research laboratories. Services are offered in regular non-destructive testing by neutron radiography, neutron irradiation of silicon for phosphorous doping and other various irradiations with neutrons. The reactor is responsible for producing approximately 70% of radiopharmaceutical {sup 131}I used in Brazil, which saves about US$ 800 000 annually for the country. After more than 50 years of use, most of its equipment and systems have been modernized, and recently the reactor power was increased to 5 MW in order to enhance radioisotope production capability. However, the control room and nuclear instrumentation system used for reactor safety have operated more than 30 years and require constant maintenance. Many equipment and electronic components are obsolete, and replacements are not available in the market. The modernization of the nuclear safety and control instrumentation systems of IEA-R1 is being carried out with consideration for the internationally recognized criteria for safety and reliable reactor operations and the latest developments in nuclear electronic technology. The project for the new reactor instrumentation system specifies three wide range neutron monitoring

Operation and maintenance of the RA Reactor in 1985, Part 1, Annex A - Reactor applications

International Nuclear Information System (INIS)

Martinc, R.; Stanic, A.

1985-01-01

This document describes reactor operation from 1981 to 1985, including data about short term (shorter than 24 hours) and long term operation interruptions, as well as safety shutdown and reactor applications. During 1982, 1983 until July 1984 reactor was operated at 2 MW power according to the plan. Plan was not fulfilled in 1983 because deposits were noticed again, at the end of 1982, on the surface of fuel elements. Reactor was mainly used for neutron activation purposes and isotope production as source of neutrons for experimental purposes [sr

Report on safety related occurrences and reactor trips July 1, 1977 - December 31, 1977

International Nuclear Information System (INIS)

Andermo, L.; Sundman, B.

1974-04-01

This is a systematically arranged report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1 to December 31, 1977 inclusive. The facilities involved are Barsebaeck 1 and 2, Oskarshamn 1 and 2 and Ringhals 1 and 2. During this period of 6 months 48 safety related occurrences and 49 reactor trips have been reported to the Nuclear Power Inspectorate. Included is also one incident June 21 in Barsebaeck 2 which was not included in the last compilation of occurrences. As earlier experiences have shown it is to the greatest extent the conventional components which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant systems and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The total number of reactor trips have increased nearly 30% since the last period. Those occurred during power operation however, were less. More than 50% of the reactor trips happened in the shutdown condition. The fact that even small deviations from prescribed operation result in automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The greatest outages are caused by occurrences withou02068NRM 0000169 450

New digital control system for the operation of the Colombian research reactor IAN-R1

International Nuclear Information System (INIS)

Celis del A, L.; Rivero, T.; Bucio, F.; Ramirez, R.; Segovia, A.; Palacios, J.

2015-09-01

En 2011, Mexico won the Colombian international tender for the renewal of instrumentation and control of the IAN-R1 Reactor, to Argentina and the United States. This paper presents the design criteria and the development made for the new digital control system installed in the Colombian nuclear reactor IAN-R1, which is based on a redundant and diverse architecture, which provides increased availability, reliability and safety in the reactor operation. This control system and associated instrumentation met all national export requirements, with the safety requirements established by the IAEA as well as the requirements demanded by the Colombian Regulatory Body in nuclear matter. On August 20, 2012, the Colombian IAN-R1 reactor reached its first criticality controlled with the new system developed at Instituto Nacional de Investigaciones Nucleares (ININ). On September 14, 2012, the new control system of the Colombian IAN-R1 reactor was officially handed over to the Colombian authorities, this being the first time that Mexico exported nuclear technology through the ININ. Currently the reactor is operating successfully with the new control system, and has an operating license for 5 years. (Author)

Experimental study of the temperature distribution in the TRIGA IPR-R1 Brazilian research reactor

International Nuclear Information System (INIS)

Mesquita, Amir Zacarias

2005-01-01

The TRIGA-IPR-R1 Research Nuclear Reactor has completed 44 years in operation in November 2004. Its initial nominal thermal power was 30 kW. In 1979 its power was increased to 100 kW by adding new fuel elements to the reactor. Recently some more fuel elements were added to the core increasing the power to 250 kW. The TRIGA-IPR-R1 is a pool type reactor with a natural circulation core cooling system. Although the large number of experiments had been carried out with this reactor, mainly on neutron activation analysis, there is not many data on its thermal-hydraulics processes, whether experimental or theoretical. So a number of experiments were carried out with the measurement of the temperature inside the fuel element, in the reactor core and along the reactor pool. During these experiments the reactor was set in many different power levels. These experiments are part of the CDTN/CNEN research program, and have the main objective of commissioning the TRIGA-IPR-R1 reactor for routine operation at 250 kW. This work presents the experimental and theoretical analyses to determine the temperature distribution in the reactor. A methodology for the calibration and monitoring the reactor thermal power was also developed. This methodology allowed adding others power measuring channels to the reactor by using thermal processes. The fuel thermal conductivity and the heat transfer coefficient from the cladding to the coolant were also experimentally valued. lt was also presented a correlation for the gap conductance between the fuel and the cladding. The experimental results were compared with theoretical calculations and with data obtained from technical literature. A data acquisition and processing system and a software were developed to help the investigation. This system allows on line monitoring and registration of the main reactor operational parameters. The experiments have given better comprehension of the reactor thermal-fluid dynamics and helped to develop numerical

Report on safety related occurrences and reactor trips July 1, 1976-December 31, 1976

International Nuclear Information System (INIS)

Andermo, L.

1977-04-01

This is a systematically arranged report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1, 1976 to December 31, 1976 inclusive. The facilities involved are Oskarshamn 1 and 2, Ringhals 1 and 2 and Barsebaeck 1. During this period of the 6 months 37 safety related occurrences and 34 reactor trips have been reported to the Nuclear Power Inspectorate. As earlier experiences have shown it is to the greatest extent the conventional components which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant systems and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The fact that even small deviations from prescribed operation results in automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The number of reactor trips are almost as low as during the last period, which is a drastic reduction compared to earlier time periods. The greatest outages are caused by occurrences without safety significance.(author)

Probabilistic study of LOFA in ETRR-1 reactor. Vol. 4

Energy Technology Data Exchange (ETDEWEB)

El-Messeiry, A M [National Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo (Egypt)

1996-03-01

In evaluating the safety of a research reactor an analysis of reactor to a wide range of postulated initiating events must be carried out, that could lead to anticipated operational occurrences or accident conditions. These disturbances include decrease in heat removal by the reactor coolant system which may be due to loss of coolant flow (LOFA) or loss of coolant heat sink. LOFA is considered here for this study for the tank type research reactor with a probabilistic approach applied to (ET-RR-1). The reactor is provided with engineering safety system to respond to accidents and perform mitigating functions. The possible malfunctions, Failures, operator errors leading to LOFA initiating event are presented (pipe break; valve opening; pump failure ...etc.). The basic event frequency/probability is calculated using appropriate probability model. The logic event tree model is constructed to illustrate all possible accident scenarios. This scenario combines system success and failure probabilities with the probability of postulated initiating events occurring that result in an accident sequence probability associated with a certain plant state. Fault tree technique is adopted to determine engineering safety features probabilities. The results show the possible minimal cut sets of variable order of each system failure. Accident sequences leading to core damage state, effects of component failures, operator errors, and system failure on plant states. The possible weak points in the design are presented. 14 figs., 3 tabs.

Probabilistic study of LOFA in ETRR-1 reactor. Vol. 4

International Nuclear Information System (INIS)

El-Messeiry, A.M.

1996-01-01

In evaluating the safety of a research reactor an analysis of reactor to a wide range of postulated initiating events must be carried out, that could lead to anticipated operational occurrences or accident conditions. These disturbances include decrease in heat removal by the reactor coolant system which may be due to loss of coolant flow (LOFA) or loss of coolant heat sink. LOFA is considered here for this study for the tank type research reactor with a probabilistic approach applied to (ET-RR-1). The reactor is provided with engineering safety system to respond to accidents and perform mitigating functions. The possible malfunctions, Failures, operator errors leading to LOFA initiating event are presented (pipe break; valve opening; pump failure ...etc.). The basic event frequency/probability is calculated using appropriate probability model. The logic event tree model is constructed to illustrate all possible accident scenarios. This scenario combines system success and failure probabilities with the probability of postulated initiating events occurring that result in an accident sequence probability associated with a certain plant state. Fault tree technique is adopted to determine engineering safety features probabilities. The results show the possible minimal cut sets of variable order of each system failure. Accident sequences leading to core damage state, effects of component failures, operator errors, and system failure on plant states. The possible weak points in the design are presented. 14 figs., 3 tabs

COSTANZA, 1-D 2 Group Space-Dependent Reactor Dynamics of Spatial Reactor with 1 Group Delayed Neutrons

International Nuclear Information System (INIS)

Agazzi, A.; Gavazzi, C.; Vincenti, E.; Monterosso, R.

1964-01-01

1 - Nature of physical problem solved: The programme studies the spatial dynamics of reactor TESI, in the two group and one space dimension approximation. Only one group of delayed neutrons is considered. The programme simulates the vertical movement of the control rods according to any given movement law. The programme calculates the evolution of the fluxes and temperature and precursor concentration in space and time during the power excursion. 2 - Restrictions on the complexity of the problem: The maximum number of lattice points is 100

Monte Carlo simulation of core physics parameters of the Nigeria Research Reactor-1 (NIRR-1)

Energy Technology Data Exchange (ETDEWEB)

Jonah, S.A. [Reactor Engineering Section, Centre for Energy Research and Training, Ahmadu Bello University, Zaria, P.M.B. 1014 (Nigeria)], E-mail: jonahsa2001@yahoo.com; Liaw, J.R.; Matos, J.E. [RERTR Program, Nuclear Engineering Division, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States)

2007-12-15

The Monte Carlo N-Particle (MCNP) code, version 4C (MCNP4C) and a set of neutron cross-section data were used to develop an accurate three-dimensional computational model of the Nigeria Research Reactor-1 (NIRR-1). The geometry of the reactor core was modeled as closely as possible including the details of all the fuel elements, reactivity regulators, the control rod, all irradiation channels, and Be reflectors. The following reactor core physics parameters were calculated for the present highly enriched uranium (HEU) core: clean cold core excess reactivity ({rho}{sub ex}), control rod (CR) and shim worth, shut down margin (SDM), neutron flux distributions in the irradiation channels, reactivity feedback coefficients and the kinetics parameters. The HEU input model was validated by experimental data from the final safety analyses report (SAR). The model predicted various key neutronics parameters fairly accurately and the calculated thermal neutron fluxes in the irradiation channels agree with the values obtained by foil activation method. Results indicate that the established Monte Carlo model is an accurate representation of the NIRR-1 HEU core and will be used to perform feasibility for conversion to low enriched uranium (LEU)

Welding of the A1 reactor pressure vessel

International Nuclear Information System (INIS)

Becka, J.

1975-01-01

As concerns welding, the A-1 reactor pressure vessel represents a geometrically complex unit containing 1492 welded joints. The length of welded sections varies between 10 and 620 mm. At an operating temperature of 120 degC and a pressure of 650 N/cm 2 the welded joints in the reactor core are exposed to an integral dose of 3x10 18 n/cm 2 . The chemical composition is shown for pressure vessel steel as specified by CSN 413090.9 modified by Ni, Ti and Al additions, and for the welding electrodes used. The requirements are also shown for the mechanical properties of the base and the weld metals. The technique and conditions of welding are described. No defects were found in ultrasonic testing of welded joints. (J.B.)

Determination flux in the Reactor JEN-1

International Nuclear Information System (INIS)

Manas Diaz, L.; Montes Ponce de leon, J.

1960-01-01

This report summarized several irradiations that have been made to determine the neutron flux distributions in the core of the JEN-1 reactor. Gold foils of 380 μ gr and Mn-Ni (12% de Ni) of 30 mg have been employed. the epithermal flux has been determined by mean of the Cd radio. The resonance integral values given by Macklin and Pomerance have been used. (Author) 9 refs

Comparison of the N Reactor and Ignalina Unit No. 2 Level 1 Probabilistic Safety Assessments

International Nuclear Information System (INIS)

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

1995-06-01

A multilateral team recently completed a full-scope Level 1 Probabilistic Safety Assessment (PSA) on the Ignalina Unit No. 2 reactor plant in Lithuania. This allows comparison of results to those of the PSA for the U.S. Department of Energy's (DOE) N Reactor. The N Reactor, although unique as a Western design, has similarities to Eastern European and Soviet graphite block reactors

Study of dietary supplements compositions by neutron activation analysis at the VR-1 training reactor

Science.gov (United States)

Stefanik, Milan; Rataj, Jan; Huml, Ondrej; Sklenka, Lubomir

2017-11-01

The VR-1 training reactor operated by the Czech Technical University in Prague is utilized mainly for education of students and training of various reactor staff; however, R&D is also carried out at the reactor. The experimental instrumentation of the reactor can be used for the irradiation experiments and neutron activation analysis. In this paper, the neutron activation analysis (NAA) is used for a study of dietary supplements containing the zinc (one of the essential trace elements for the human body). This analysis includes the dietary supplement pills of different brands; each brand is represented by several different batches of pills. All pills were irradiated together with the standard activation etalons in the vertical channel of the VR-1 reactor at the nominal power (80 W). Activated samples were investigated by the nuclear gamma-ray spectrometry technique employing the semiconductor HPGe detector. From resulting saturated activities, the amount of mineral element (Zn) in the pills was determined using the comparative NAA method. The results show clearly that the VR-1 training reactor is utilizable for neutron activation analysis experiments.

IGORR 1: Proceedings of the 1. meeting of the International Group On Research Reactors

Energy Technology Data Exchange (ETDEWEB)

West, C D [comp.

1990-05-01

Descriptions of the ongoing projects presented at this Meeting were concerned with: New Research Reactor FRM-II at Munich; MITR-II reactor; The Advanced. Neutron Source (ANS) Project; The high Flux Reactor Petten, Status and Prospects; The High Flux Beam Reactor Instrumentation Upgrade; BER-II Upgrade; The BR2 Materials Testing Reactor Past, Ongoing and Under-Study Upgrades; The ORPHEE, Reactor Current Status and Proposed Enhancement of Experimental Variabilities; Construction of the Upgraded JRR-3; Status of the University of Missouri-Columbia Research Reactor Upgrade; the Reactor and Cold Neutron Facility at NIST; Upgrade of Materials Irradiation Facilities in HFIR; Backfitting of the FRG Reactors; University Research Reactors in the United States; and Organization of the ITER Project - Sharing of Informational Procurements. Topics of interest were: Thermal-hydraulic tests and correlations, Corrosion tests and analytical models , Multidimensional kinetic analysis for small cores, Fuel plates fabrication, Fuel plates stability, Fuel irradiation, Burnable poison irradiation, Structural materials irradiation, Neutron guides irradiation, Cold Source materials irradiation, Cold Source LN{sub 2} test, Source LH2-H{sub 2}O reaction (H or D), Instrumentation upgrading and digital control system, Man-machine interface.

IGORR 1: Proceedings of the 1. meeting of the International Group On Research Reactors

International Nuclear Information System (INIS)

West, C.D.

1990-05-01

Descriptions of the ongoing projects presented at this Meeting were concerned with: New Research Reactor FRM-II at Munich; MITR-II reactor; The Advanced. Neutron Source (ANS) Project; The high Flux Reactor Petten, Status and Prospects; The High Flux Beam Reactor Instrumentation Upgrade; BER-II Upgrade; The BR2 Materials Testing Reactor Past, Ongoing and Under-Study Upgrades; The ORPHEE, Reactor Current Status and Proposed Enhancement of Experimental Variabilities; Construction of the Upgraded JRR-3; Status of the University of Missouri-Columbia Research Reactor Upgrade; the Reactor and Cold Neutron Facility at NIST; Upgrade of Materials Irradiation Facilities in HFIR; Backfitting of the FRG Reactors; University Research Reactors in the United States; and Organization of the ITER Project - Sharing of Informational Procurements. Topics of interest were: Thermal-hydraulic tests and correlations, Corrosion tests and analytical models , Multidimensional kinetic analysis for small cores, Fuel plates fabrication, Fuel plates stability, Fuel irradiation, Burnable poison irradiation, Structural materials irradiation, Neutron guides irradiation, Cold Source materials irradiation, Cold Source LN 2 test, Source LH2-H 2 O reaction (H or D), Instrumentation upgrading and digital control system, Man-machine interface

Nuclear reactor and materials science research: Technical report, May 1, 1985-September 30, 1986

International Nuclear Information System (INIS)

1987-01-01

Throughout the 17-month period of its grant, May 1, 1985-September 30, 1986, the MIT Research Reactor (MITR-II) was operated in support of research and academic programs in the physical and life sciences and in related engineering fields. The reactor was operated 4115 hours during FY 1986 and for 6080 hours during the entire 17-month period, an average of 82 hours per week. Utilization of the reactor during that period may be classified as follows: neutron beam tube research; nuclear materials research and development; radiochemistry and trace analysis; nuclear medicine; radiation health physics; computer control of reactors; dose reduction in nuclear power reactors; reactor irradiations and services for groups outside MIT; MIT Research Reactor. Data on the above utilization for FY 1986 show that the MIT Nuclear Reactor Laboratory (NRL) engaged in joint activities with nine academic departments and interdepartmental laboratories at MIT, the Charles Stark Draper Laboratory in Cambridge, and 22 other universities and nonprofit research institutions, such as teaching hospitals

Baikal-1 stand complex. Preparation and carrying out of the first energy start-up of the IVG-1 reactor

International Nuclear Information System (INIS)

Tikhomirov, L.N.

1995-01-01

The IVG-1 reactor was a first ground prototype of nuclear rocket engine. The reactor was built on the site 10 of the Semipalatinsk test site. Since the first energy start-up in 1975 the reactor was exploited 14 years till its modernization in 1989. The Bajkal-1 stand complex was designed and built for the carrying out of tests for fuel assemblies of different modifications. The energy start-up has been sum of long creative work of different research and constructive staffs on creation of high-temperature gas-cooled IVG-1 reactor. The history of construction, project and assembling of the stand complex is presented. Complex start and put works were carried out in the December 1974. Control physical start-up was carried out in the January 1975. Cold start-up by hydrogen was in the February 1975. Hot start-up was in the March 1975. The result of the hot start-up was experimental confirmation of metodics of thermohydrovlical estimations. 2 figs., 3 tabs

RA reactor operation and maintenance in 1994, Part 1

International Nuclear Information System (INIS)

Sotic, O.; Cupac, S.; Sulem, B.; Zivotic, Z.; Mikic, N.; Tanaskovic, M.

1994-01-01

During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The planned major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. The existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Renewal of the reactor instrumentation was started but but it is behind the schedule because the delivery of components from USSR was stopped for political reasons. The spent fuel elements used from the very beginning of reactor operation are stored in the existing pools. Project concerned with increase of the storage space and the efficiency of handling the spent fuel elements has started in 1988 and was fulfilled in 1990. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor [sr

Determination flux in the Reactor JEN-1; Medida de flujos de neutrones en el nucleo del Reactor JEN-1

Energy Technology Data Exchange (ETDEWEB)

Manas Diaz, L; Montes Ponce de leon, J.

1960-07-01

This report summarized several irradiations that have been made to determine the neutron flux distributions in the core of the JEN-1 reactor. Gold foils of 380 {mu} gr and Mn-Ni (12% de Ni) of 30 mg have been employed. the epithermal flux has been determined by mean of the Cd radio. The resonance integral values given by Macklin and Pomerance have been used. (Author) 9 refs.

Reactor core conversion studies of Ghana: Research Reactor-1 and proposal for addition of safety rod

International Nuclear Information System (INIS)

Odoi, H.C.

2014-06-01

The inclusion of an additional safety rod in conjunction with a core conversion study of Ghana Research Reactor-1 (GHARR-1) was carried out using neutronics, thermal hydraulics and burnup codes. The study is based on a recommendation by Integrated Safety Assessment for Research Reactors (INSARP) mission to incorporate a safety rod to the reactor safety system as well as the need to replace the reactor fuel with LEU. Conversion from one fuel type to another requires a complete re-evaluation of the safety analysis. Changes to the reactivity worth, shutdown margin, power density and material properties must be taken into account, and appropriate modifications made. Neutronics analysis including burnup was studied followed by thermal hydraulics analyses which comprise steady state and transients. Four computer codes were used for the analysis; MCNP, REBUS, PLTEP and PARET. The neutronics analysis revealed that the LEU core must be operated at 34 Kw in order to attain the flux of 1.0E12 n/cm 2 .s as the nominal flux of the HEU core. The auxiliary safety rod placed at a modified irradiation site gives a better worth than the cadmium capsules. For core excess reactivity of 4 mk, 348 fuel pins would be appropriate for the GHARR-1 LEU core. Results indicate that flux level of 1.0E12 n/cm 2 .s in the inner irradiation channel will not be compromised, if the power of the LEU core is increased to 34 kW. The GHARR-1 core using LEU-U0 2 -12.5% fuel can be operated for 23 shim cycles, with cycles length 2.5 years, for over 57 years at the 17 kW power level. All 23 LEU cycles meet the ∼ 4.0 mk excess reactivity required at the beginning of cycle . For comparison, the MNSR HEU reference core can also be operated for 23 shim cycles, but with a cycle length of 2.0 years for just over 46 years at 15.0kW power level. It is observed that the GHARR-1 core with LEU UO 2 fuel enriched to 12.5% and a power level of 34 kW can be operated ∼25% longer than the current HEU core operated at

New burnup calculation of TRIGA IPR-R1 reactor

International Nuclear Information System (INIS)

Meireles, Sincler P. de; Campolina, Daniel de A.M.; Santos, Andre A. Campagnole dos; Menezes, Maria A.B.C.; Mesquita, Amir Z.

2015-01-01

The IPR-R1 TRIGA Mark I research reactor, located at the Nuclear Technology Development Center - CDTN, Belo Horizonte, Brazil, operates since 1960.The reactor is operating for more than fifty years and has a long history of operation. Determining the current composition of the fuel is very important to calculate various parameters. The reactor burnup calculation has been performed before, however, new techniques, methods, software and increase of the processing capacity of the new computers motivates new investigations to be performed. This work presents the evolution of effective multiplication constant and the results of burnup. This new model has a more detailed geometry with the introduction of the new devices, like the control rods and the samarium discs. This increase of materials in the simulation in burnup calculation was very important for results. For these series of simulations a more recently cross section library, ENDF/B-VII, was used. To perform the calculations two Monte Carlo particle transport code were used: Serpent and MCNPX. The results obtained from two codes are presented and compared with previous studies in the literature. (author)

Reactor Engineering Department annual report, April 1, 1985 - March 31, 1986

International Nuclear Information System (INIS)

1986-08-01

Research and development activities in the Department of Reactor Engineering in fiscal 1985 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor, High Conversion Light Water Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, reactor decommissioning technology, and activities of the Committee on Reactor Physics. (author)

Economics and utilization of thorium in nuclear reactors. Technical annexes 1 and 2

International Nuclear Information System (INIS)

1978-05-01

An assessment of the impact of utilizing the 233 U/thorium fuel cycle in the U.S. nuclear economy is strongly dependent upon several decisions involving nuclear energy policy. These decisions include: (1) to recycle or not recycle fissile material; (2) if fissile material is recycled, to recycle plutonium, 233 U, or both; and (3) to deploy or not to deploy advanced reactor designs such as Fast Breeder Reactors (FBR's), High Temperature Gas Reactors (HTGR's), and Canadian Deuterium Uranium Reactors (CANDU's). This report examines the role of thorium in the context of the above policy decisions while focusing special attention on economics and resource utilization

Neutron flux measurement and thermal power calibration of the IAN-R1 TRIGA reactor

Energy Technology Data Exchange (ETDEWEB)

Sarta Fuentes, Jose A.; Castiblanco Bohorquez, Luis A

2008-10-29

The IAN-R1 TRIGA reactor in Colombia was initially fueled with MTR-HEU enriched to 93% U-235, operated since 1965 at 10 kW, and was upgraded to 30 kW in 1980. General Atomics achieved in 1997 the conversion of HEU fuel to LEU fuel TRIGA type, and upgraded the reactor power to 100 kW. Since the IAN-R1 TRIGA reactor was in an extended shutdown during seven years, it was necessary to repeat some results of the commissioning test conducted in 1997. The thermal power calibration was carried out using the calorimetric method. The reactor was operated approximately at 20 kW during 3.5 hours, with manual power corrections since the automatic control system failed and with the forced refrigeration off. During the calorimetric experiment, the pool temperature was measured with a RTD which is installed near to the core. The dates were collected in intervals of 30 minutes. For establishing thermal power reactor, the water temperature versus the running were registered. For a calculated tank volume of 16 m{sup 3}, the tank constant calculated for the IAN-R1 TRIGA reactor is 0.0539 C/kW-hr. The reactor power determined was 19 kW. The core configuration is a rectangular grid plate that holds a combination of 4-rod and 3-rod clusters. The core contains 50 fuel rods with LEU fuel TRIGA (UZr H1.6) type enriched to 19.7%. The radial reflector consists of twenty graphite elements six of which are used for isotope production. The top an bottom reflectors are the cylindrical graphite end reflectors which are installed above and below of the active fuel section in each fuel rod. The spatial dependence of thermal neutron flux was measured axially in the 3-rod clusters 4C, 3D, 5E and in the 4F graphite element. The spatial distribution of the thermal neutron was determined using a self-powered detector and the absolute value of thermal neutron flux was determined by a gold activation detector. The (n, b- ) reaction is applied to determine the relative spatial distribution of thermal

Problems of nuclear reactor safety. Vol. 1

International Nuclear Information System (INIS)

Shal'nov, A.V.

1995-01-01

Proceedings of the 9. Topical Meeting 'Problems of nuclear reactor safety' are presented. Papers include results of studies and developments associated with methods of calculation and complex computerized simulation for stationary and transient processes in nuclear power plants. Main problems of reactor safety are discussed as well as rector accidents on operating NPP's are analyzed

Experiment on continuous operation of the Brazilian IEA-R1 research reactor

International Nuclear Information System (INIS)

Freitas Pintaud, M. de

1994-01-01

In order to increase the radioisotope production in the IEA-R1 research reactor at IPEN/CNEN-SP, it has been proposed a change in its operation regime from 8 hours per day and 5 days per week to continuous 48 hours per week. The necessary reactor parameters for this new operation regime were obtained through an experiment in which the reactor was for the first time operated in the new regime. This work presents the principal results from this experiment: xenon reactivity, new shutdown margins, and reactivity loss due to fuel burnup in the new operation regime. (author)

Auxiliary control system of the safety parameters for IPR-R1 reactor

International Nuclear Information System (INIS)

Coura, J.G.

1986-01-01

This paper deals with the description for the control of three cooling water parameters (conductivity, temperature and the maximum and minimum water levels) as well as the percent power fraction of the nuclear research reactor IPR-R1. In order to keep the reactor in good operation conditions, one permanent and accurate control of the cooling water is needed. The double monitoring of a fourth parameter, part of the original design, the percent power fraction, is obtained through the control of the uncompensated ion chamber current and aims to avoid the operation of the reactor without running the cooling system. (Author) [pt

OSCAR-4 Code System Application to the SAFARI-1 Reactor

International Nuclear Information System (INIS)

Stander, Gerhardt; Prinsloo, Rian H.; Tomasevic, Djordje I.; Mueller, Erwin

2008-01-01

The OSCAR reactor calculation code system consists of a two-dimensional lattice code, the three-dimensional nodal core simulator code MGRAC and related service codes. The major difference between the new version of the OSCAR system, OSCAR-4, and its predecessor, OSCAR-3, is the new version of MGRAC which contains many new features and model enhancements. In this work some of the major improvements in the nodal diffusion solution method, history tracking, nuclide transmutation and cross section models are described. As part of the validation process of the OSCAR-4 code system (specifically the new MGRAC version), some of the new models are tested by comparing computational results to SAFARI-1 reactor plant data for a number of operational cycles and for varying applications. A specific application of the new features allows correct modeling of, amongst others, the movement of fuel-follower type control rods and dynamic in-core irradiation schedules. It is found that the effect of the improved control rod model, applied over multiple cycles of the SAFARI-1 reactor operation history, has a significant effect on in-cycle reactivity prediction and fuel depletion. (authors)

Unitary theory of xenon instability in nuclear thermal reactors - 1. Reactor at 'zero power'

International Nuclear Information System (INIS)

Novelli, A.

1982-01-01

The question of nuclear thermal-reactor instability against xenon oscillations is widespread in the literature, but most theories, concerned with such an argument, contradict each other and, above all, they conflict with experimentally-observed instability at very low reactor power, i.e. without any power feedback. It is shown that, in any nuclear thermal reactor, xenon instability originates at very low power levels, and a very general stability condition is deduced by an extension of the rigorous, simple and powerful reduction of the Nyquist criterion, first performed by F. Storrer. (author)

Thermal-hydraulic modelling of the SAFARI-1 research reactor using RELAP/SCDAPSIM/MOD3.4

International Nuclear Information System (INIS)

Sekhri, Abdelkrim; Graham, Andy; D'Arcy, Alan; Oliver, Melissa

2008-01-01

The SAFARI-1 reactor is a tank-in-pool MTR type research reactor operated at a nominal core power of 20 MW. It operates exclusively in the single phase liquid water regime with nominal water and fuel temperatures not exceeding 100 deg. C. RELAP/SCDAPSIM/MOD3.4 is a Best Estimate Code for light water reactors as well as for low pressure transients, as part of the code validation was done against low pressure facilities and research reactor experimental data. The code was used to simulate SAFARI-1 in normal and abnormal operation and validated against the experimental data in the plant and was used extensively in the upgrading of the Safety Analysis Report (SAR) of the reactor. The focus of the following study is the safety analysis of the SAFARI-1 research reactor and describes the thermal hydraulic modelling and analysis approach. Particular emphasis is placed on the modelling detail, the application of the no-boiling rule and predicting the Onset of Nucleate Boiling and Departure from Nucleate Boiling under Loss of Flow conditions. Such an event leads the reactor to switch to a natural convection regime which is an adequate mode to maintain the clad and fuel temperature within the safety margin. It is shown that the RELAP/SCDAPSIM/MOD3.4 model can provide accurate predictions as long as the clad temperature remains below the onset of nucleate boiling temperature and the DNB ratio is greater than 2. The results are very encouraging and the model is shown to be appropriate for the analysis of SAFARI-1 research reactor. (authors)

Thermal hydraulic analysis of the IPR-R1 TRIGA research reactor using a RELAP5 model

International Nuclear Information System (INIS)

Costa, Antonella L.; Reis, Patricia Amelia L.; Pereira, Claubia; Veloso, Maria Auxiliadora F.; Mesquita, Amir Z.; Soares, Humberto V.

2010-01-01

The RELAP5 code is widely used for thermal hydraulic studies of commercial nuclear power plants. Current investigations and code adaptations have demonstrated that the RELAP5 code can be also applied for thermal hydraulic analysis of nuclear research reactors with good predictions. Therefore, as a contribution to the assessment of RELAP5/MOD3.3 for research reactors analysis, this work presents steady-state and transient calculation results performed using a RELAP5 model to simulate the IPR-R1 TRIGA research reactor at 50 kilowatts (kW) of power operation. The reactor is located in the Nuclear Technology Development Center (CDTN), Brazil. It is a 250 kW, light water moderated and cooled, graphite-reflected, open pool type research reactor. The development and the assessment of a RELAP5 model for the IPR-R1 TRIGA are presented. Experimental data were considered in the process of the RELAP5 model validation. The RELAP5 results were also compared with calculated data from the STHIRP-1 (Research Reactors Thermal Hydraulic Simulation) code. The results obtained have shown that the RELAP5 model for the IPR-R1 TRIGA reproduces the actual steady-state reactor behavior in good agreement with the available data.

SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configurations

International Nuclear Information System (INIS)

Gauld, I.C.

2000-01-01

Five commercial reactor criticals (CRCs) for the LaSalle Unit 1 boiling-water reactor have been analyzed using KENO V.a, the Monte Carlo criticality code of the SCALE 4 code system. The irradiated fuel assembly isotopics for the criticality analyses were provided by the Waste Package Design team at the Yucca Mountain Project in the US, who performed the depletion calculations using the SAS2H sequence of SCALE 4. The reactor critical measurements involved two beginning-of-cycle and three middle-of-cycle configurations. The CRCs involved relatively low-cycle burnups, and therefore contained a relatively high gadolinium poison content in the reactor assemblies. This report summarizes the data and methods used in analyzing the critical configurations and assesses the sensitivity of the results to some of the modeling approximations used to represent the gadolinium poison distribution within the assemblies. The KENO V.a calculations, performed using the SCALE 44GROUPNDF5 ENDF/B-V cross-section library, yield predicted k eff values within about 1% Δk/k relative to reactor measurements for the five CRCs using general 8-pin and 9-pin heterogeneous gadolinium poison pin assembly models

Calculations of Changes in Reactivity during some regular periods of operation of JEN-1 MOD Reactor; Calculo de vairaciones de reactividad en algunos periodos regulares de operacion del reactor JEN-1 Mod.

Energy Technology Data Exchange (ETDEWEB)

Alcala Ruiz, F

1973-07-01

By a Point-Reactor model and Perturbation Theory, changes in reactivity during some regular operating periods of JEN-1 MOD Reactor have been calculated and compared with available measured values. they were in good agreement. Also changes in reactivity have been calculated during operations at higher power levels than the present one, concluding some practical consequences for the case of increasing the present power of this reactor. (Author)

Reactor Engineering Department annual report (April 1, 1986 - March 31, 1987)

International Nuclear Information System (INIS)

1987-08-01

Research and development activities in the Department of Reactor Engineering in the fiscal year 1986 are described. The major activities of the Department are closely related to the reactor physics of very high temperature gas-cooled reactor, high conversion light water reactor and liquid metal fast breeder reactor and to blanket neutronics of fusion reactor. Contents of this report are divided into the activities on nuclear data and group constants, theoretical methods and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control, diagnosis and robotics. The activity of the Research Committee on Reactor Physics is also included. (author)

Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

International Nuclear Information System (INIS)

1982-01-01

A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)