The scope of projects in 2005 ranged from a few person months to several person years, and the planned total duration from one to four years. The research areas and focal points of the program were defined in the proposal for the content and organization of the new research program. SAFIR is a dynamic research program that enables the inclusion of new projects or the expansion of existing projects during the research year.
The construction of the new power plant unit increases the need for experts in the field in Finland. The division of the twelve main future security challenges into the six research areas of SAFIR [1]. The project titles and their division into six research areas are illustrated in Table 1.1.
Reactor core and fuel
A user guide has been published for the new versions of the HEXBU-3D program (MOD5.3 and MOD6.1). A more accurate model for the heat transfer properties of the gap between pellet and cladding has been implemented in the HEXTRAN and TRAB-3D codes. Increasing the detail of the modeling was again necessary to meet the demand of the test setup.
This has become possible because more experience has been gained with the performance of the rig. Recorrelation of the original fission gas release model into the ENIGMA code has begun and shows promising results. Updated versions and links of the FRAPTRAN and FRAPTRAN-GENFLO codes A comprehensive report on the modeling of fission gas release and the combined IMAGINE-ENIGMA application (Figure 2.3) has been released in the form of a master thesis.
Reactor circuit and structural safety
The workshop prepares a state-of-the-art report on the integration of aging effects in PSA. An important contribution has been made to one of the most important chapters of the draft report. To estimate the loads in pressure extinguishing basins, research has been done into determining the pressure sources.
The second draft version of the IAEA VVER SG TECDOC report was received for comments. In general, the agreement between the simulation results and experimental measurements was quite good (Figure 2.4). A brief memorandum on the annual meeting of the OECD/NEA/IAGE CONCRETE WG in Lyon on 8 April 2005.
Containment and process safety functions
Based on these calculations, the results of the pipe fracture analyzes appear reasonable. An important part of the project is also the validation of some new or improved APROS models. Most of the improvements are related to the spray pattern, spray effects and other important phenomena in braking.
The aim of the project was to develop calculation tools and increase the understanding of thermal hydraulic phenomena. Data from the experiments were to be used in the TIFANY project to validate the temperature stratification model for the APROS system code. Instrumentation and the data acquisition system in the pool trig modeling a BWR suppression pool were further upgraded.
The thermal stratification model of the APROS system code was validated using the POOLEX data of the TIFANY project. Calculations were carried out for or with a view to supporting the planning of the reinforced concrete measures. The effects of the various boundary conditions and details associated with the computational implementation were investigated.
Prototype design of the deformable rocket is reported in Crushing force of a rocket (in Finnish). In the first tests, accelerometers were used to measure the time signal of the impact force. Moreover, within the framework of the project, the follow-up and participation of major international research projects in the field of serious accidents is carried out.
The construction of the facility and conducting the tests will take place in the next research project outside SANCY. Part of the project was to train young experts for work in the field of nuclear safety. VTT will continue to analyze the deposition, resuspension and revaporization of fission products in the primary circuit of the test facility.
Automation, control room and information technology
The basis of the method lies in existing standards and literature on the evaluation and design of user interfaces of complex systems. It is complemented by proprietary innovations aimed at improving the generalizability of the validation results, and creating a comprehensive, activity-oriented evaluation approach that we call system usability. Theoretical justification for the proposed structure, indicators and criteria of the method were developed and compared with corresponding methods.
The suitability of CASU version 1 was tested in a standard design in which two different design concepts, Ecological Interface Design (University of Toronto) and functional design (EdF) are tested in HRP HAMLAB. We conducted interviews with designers to determine and evaluate the design rationale for the control room modernization. This task facilitates the goal of linking the CASU assessment tool to the needs of the design process.
Designers and users of both power plants and power companies, as well as representatives of the regulator, participated. The main goal of the research is to generate recommendations for document reviews and other application artifacts of software-intensive I&C systems. Software documents that users receive from I&C system suppliers are usually text documents and semi-formal graphs, for example requirements specifications are function diagrams and design documents are logic diagrams.
The scope of the classification of new error types is as defined in the project plan in the user perspective to find out how prone the artifacts are to errors. Initial hypotheses were established for the new software error types, i.e. Syntactic, Semantic and Pragmatic Errors (SSP Errors) in order to be able to compare with results obtained at the end of the project. The aim of this preliminary study was to study the causes of the growth of whiskers in metals such as tin (Sn) and zinc (Zn), the influences of the manufacturing process and the environment during operation on this growth and the effect of whiskers on the reliability of electronics. .
The development of the new IEC standard, IEC 62342: Nuclear power plants – Management of obsolescence of nuclear power plant instrumentation and control and associated equipment (45A/441/NP), continued.
Organisations and safety management
However, according to the literature and many recent observations, whisker growth can be driven by two key factors: the formation of intermetallic compounds, which is accompanied by a build-up of biaxial microstress in the metal layer, and the capability of such metal layers. to release this stress by pathways distinct from whisker growth. The main objective of the CulMa project is to increase the understanding of how organizational factors affect nuclear safety. The project aims to generate knowledge about the effects of organizational culture, organizational changes and the different ways of organizing work with safety in nuclear power production.
The project continues the work done in the FINNUS/WOPS project to develop a methodology for contextual assessment of organizational culture (CAOC) in safety critical environments. The project is carried out in case studies in close cooperation with the power plants. In 2005, the work in the CulMa project aimed to study the safety effects of organizational changes at NPPs and to study and develop the learning of newcomers in maintenance organizations.
Three presentations were also held at the conference, a scientific article was submitted, as well as a full paper and an abstract at the conferences to be held in 2006. The case study for the training and socialization of newcomers to TVO maintenance continued. The results and recommendations regarding the change of attitudes, the change in conceptual understanding, the training experiences has been.
Organizational changes and their safety consequences in Nordic nuclear maintenance units were analyzed and a final report on the management of change in the nuclear industry was written. The project staff also participated in the NKS-R/Safety Management Network coordinated by prof. The main objectives of the TIMANTTI project are to improve, increase and develop the sharing of tacit knowledge between experienced and inexperienced employees, to motivate employees of different ages to share knowledge, and to identify factors, understand and develop that affect the effectiveness and success of knowledge sharing.
The specific goals for 2005 were to create a new understanding of the role and content of tacit knowledge in the two selected case units and to develop and implement methods for its preservation by strengthening the exchange of knowledge between experts and newcomers.
Risk-informed safety management
MC modeling continued to observe convergence, the influence of the shape of the input distributions, and. Development of a method focusing on the management of fire situations from a cooperative perspective, based on the interdisciplinary work of expert groups in both nuclear power plants in Finland. The organization of the IAEA expert meeting on the implementation and licensing of digital I&C systems and equipment in nuclear power plants has been agreed and the proceedings are being prepared.
Following the OECD/NEA/CSNI/WGRISK task "Software Reliability – Task on the Safety Assessment of Programmable Computers", managing the activity of the ad hoc group on the research topic and participating in relevant conferences (SAFECOMP 2005 ). The OECD/NEA/CSNI/WGRISK Task White Paper on Software Reliability has been commented on and delivered to the authors of the paper. The total volume of the projects financed by VYR was €4.85 million and the total volume of the other two projects was €0.35 million.
The planned and realized financing and expenses for the VYR-financed projects are indicated respectively in figure 3.1. and 3.2. The proportion of staff costs was about 86% of the annual expenditure, as illustrated in Figure 3.2. A more detailed overview of the planned and realized costs and financing for the VYR-financed projects is given in table 3.1.
Many of the projects have deliberately aimed at publishing the results as comprehensive research institute reports. The information about the research carried out in SAFIR has been communicated formally via the quarterly progress reports, the program's annual report and the program's www pages. The publications of the projects in the years 2003-2004 were collected on CD and distributed to all SAFIR organizations presented in the Steering Group.
Nuclear power plant safety research Proposal for the content and organization of the new research program.
