Nystad, Espen; Sebok, Angelia; Meyer, Geir
Institutt for energiteknikk, OECD Halden Reactor Project, Halden (Norway)2004
Institutt for energiteknikk, OECD Halden Reactor Project, Halden (Norway)2004
AbstractAbstract
[en] The Halden Virtual Reality Centre has developed work-planning software that predicts the radiation exposure of workers in contaminated areas. To validate the accuracy of the predicted radiation dosages, it is necessary to compare predicted doses to actual dosages. During an experimental study conducted at the Halden Boiling Water Reactor (HBWR) hall, the radiation exposure was measured for all participants throughout the test session, ref. HWR-681 [3]. Data from this experimental study have also been used to model tasks in the work-planning software and gather data for predicted radiation exposure. Two different methods were used to predict radiation dosages; one method used all radiation data from all the floor levels in the HBWR (all-data method). The other used only data from the floor level where the task was conducted (isolated data method). The study showed that the all-data method gave predictions that were on average 2.3 times higher than the actual radiation dosages. The isolated-data method gave predictions on average 0.9 times the actual dosages. (Author)
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Apr 2004; 14 p; Available from IFE, PO Box 173, 1751 Halden Norway; refs., figs
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Fantoni, Paolo; Iguchi, Yukihiro; Meyer, Geir; Soerensen, Aimar; Van Dyck, Claude
Institutt for energiteknikk, OECD Halden Reactor Project, Halden (Norway)1996
Institutt for energiteknikk, OECD Halden Reactor Project, Halden (Norway)1996
AbstractAbstract
[en] CAMS (Computerized Accident Management Support) is a system that will provide assistance to the staff in the control room, in the technical support centre, and in a national safety centre. These three groups of users do not need the same type of support. Support is offered in identification of the plant state, in assessment of the future development of the accident, and in planning of accident mitigation strategies. Last year the predictive part of the system was tested at a safety exercise arranged by the Swedish Nuclear Inspectorate, and found to be a useful tool, with potential for further development. Now, new methods are added in signal validation, state identification, tracking simulation, predictive simulation, risk monitoring, and man-machine interface design. A prototype will be demonstrated at Loen in May 1996. This prototype is still under development. The purpose of this prototype is to test those methods in a simulated environment to verify that the developed functions, using different techniques, can work together producing the desired result in an efficient way. The plan is to test these techniques at power plants. During the CAMS design, a considerable effort has been given to maintain the generality of the CAMS concept; although the referenced process has been so far a BWR nuclear plant, the use of this structure and design can be applied to other processes, including non-nuclear processes. The research programme is carried out in close cooperation with member organizations (author)
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Apr 1996; 44 p; Available from IFE, PO Box 173, 1751 Halden Norway; 14 refs., 19 figs.
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Report
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ANALOG SYSTEMS, BHWR TYPE REACTORS, COOPERATION, DEVELOPED COUNTRIES, ENRICHED URANIUM REACTORS, EUROPE, EXPERIMENTAL REACTORS, FUNCTIONAL MODELS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, INTERNATIONAL ORGANIZATIONS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SCANDINAVIA, TANK TYPE REACTORS, TESTING, THERMAL REACTORS, WESTERN EUROPE
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Johnsen, Terje; Edvardsen, S.T.; Meyer, Geir; Rindahl, Grete; Sebok, A.L.; Sivertsen, E.R.
Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)2004
Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)2004
AbstractAbstract
[en] In the VRdose R5 version the connection with the dynamic radiation evaluation system (DRES) was the main task. DRES can calculate the dose rate field of the Fugen plant in detail. By inserting special markers into the scenario, VRdose tells DRES what changes have been made to the model. The changes are about objects that are inserted, removed, cut or moved. DRES will then calculate new dose rate fields reflecting these changes. VRdose uses the new dose rate fields in the dose calculation of the workers in the scenario. The dose rate fields are switched automatically as VRdose plays the scenario and in the dose calculation. To minimize the calculation needed for DRES, VRdose can provide a volume enclosing only the area of interest for a given scenario and give the resolution of the calculation in all axes. In addition to the DRES connection, version R5 retrieves information about the objects in the model from the Fugen object database. Among the large amount of information available, are size, weight and surface contamination of co-60 used. The wizard uses the size and weight information in the calculation of the man-work required. The surface contamination is used in a new feature that colonizes the objects after the contamination value. This makes it easier for workers to become aware of the contamination of pipes and pumps etc. R5 has been internationalized on all menus, buttons, messages and other text. VRdose can therefore be translated into any desired language. A feasibility study has been made into using Japanese characters in names and properties in the scenario. Printing of the 3D view has been implemented, which is useful for documenting. The scenario can also be printed, both as a graphical representation and in a textual report format. Other functionality that can be mentioned is output from the wizard to Cosmard and the saving of viewpoints. The manikins wear different protection masks and in version R5 the efficiency of the protection can be changed for each nuclide. A special database administrator program has been developed to increase the security of the VRdose database. Several other minor changes have been made, such as the ability to switch between extern dose and nuclide intake in the dose graph panels. (author)
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Mar 2004; 192 p; Available from JST Library (JST: Japan Science and Technology Agency), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781 (domestic), FAX:+81-3-3979-2210 (oversea)
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Report
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Software
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COMPUTER OUTPUT DEVICES, COMPUTER-GRAPHICS DEVICES, CONTAMINATION, DECOMMISSIONING, DOCUMENT TYPES, DOSES, HEAVY WATER MODERATED REACTORS, HWLWR TYPE REACTORS, MANAGEMENT, NATURAL URANIUM REACTORS, NUCLEAR FACILITIES, PLUTONIUM REACTORS, POWER PLANTS, POWER REACTORS, PRESSURE TUBE REACTORS, REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS
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Skjerve, Ann Britt; Strand, Stine; Skraaning, Gyrd Jr.; Nihlwing, Christer; Helgar, Stein; Olsen, Asle; Kvilesjoe, Hans Oeyvind; Meyer, Geir; Droeivoldsmo, Asgeir; Svengren, Haakan
Institutt for energiteknikk, OECD Halden Reactor Project, Halden (Norway)2005
Institutt for energiteknikk, OECD Halden Reactor Project, Halden (Norway)2005
AbstractAbstract
[en] The report documents the study plan for the Extended Teamwork 2004/2005 exploratory study, which is performed within the Extended Teamwork HRP research program. The purpose of the research program is to generate ideas on how teamwork in nuclear power plants may be affected by the introduction of new operational concepts. The Extended Teamwork 2004/2005 exploratory study contributes with empirical knowledge on the effect of a new operational concept, implying increased automation levels, changed operator roles, redefined competence requirements to the operators, and new technologies to support co-operation, on teamwork. The Extended Teamwork 2004/2005 exploratory study covered occurrences during the early transition phase, i.e., from the time the operators are introduced to the possible future operational environment, to the time they have completed the twelve scenarios comprised by the study. The study assessed how familiarity with operation in the possible future operational environment may affect the extent and quality of co-operation. The report accounts for the motivation for performing the exploratory study, and explains the research question. It describes the theoretical approach, which is based on Co-operation Theory, the human-centered automation approach, and theories on co-operation across distances, and introduces the concept extended teamwork. It also describes the method applied: it provides a detailed description of the possible future operational environment, including requirements with respect to autonomy and authority - both for humans and for automatic agents, and describes the technology applied to support co-operation in the control-room team. In addition, all measurement techniques applied in the study are accounted for (system logs, questionnaires, interviews, etc.). (Author)
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Sep 2005; 154 p; Available from IFE, PO Box 173, 1751 Halden Norway; refs., figs., tabs
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