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PROJECT PROGRESS REPORTS 4/2004

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Implementation and testing of the broad-spectrum cross-sectional model in the reactor dynamics codes, TRAB-3D and HEXTRAN, must be completed. Participation in the work of the OECD/NEA Working Party on Nuclear Criticality Safety (WPNCS) continued - of particular interest are burnup credit benchmarks 1 - 6 (to be solved using the CASMO-4, MCNP4C and SCALE-5 program system).

Nozzles .1 EAC mechanisms and international co-

Ultrasonic time-of-flight diffraction (TOFD) technique can be used to detect defects in thick-walled components. Based on the results, the technique to be used in the field will be specified.

Internals .1 Corrosion of the fuel cladding materials

Moreover, it is possible that the grain growth caused by repair welding of austenitic steels can be detected based on the ultrasonic sound measured with TOFD technique. This dependence of the ultrasonic noise on the grain structure of the material will be studied experimentally with test samples.

Dosimetry .1 Development of neutron dosimetry

The simulation results are compared with the results of real measurements to produce verification material on the potential and accuracy of the purchased program. An important role in the simulations conducted was to train and expand the skills of staff to use the CIVA program.

RI-ISI, Risk informed in service Inspection Approaches to estimate piping leak and break

Depending on the type of OL3, there may be an increasing need for expertise in the future (about a 10-year time frame). The current version of the Swedish ultrasound modeling program simSUNDT (free software) was received at the related workshop and some experiments were performed with this program.

Fluid-Structure interaction analyses The supporting analyses with CFD and structural

Fatigue

PWR was the first in the world and opened a new question about the reduction of fatigue life due to the combined effect of environment and variable amplitude. Modeling deformation mechanisms is also linked to subtask 2.4.1 on material models for assessing the structural integrity of finite elements.

Corrosion - water chemistry interaction .1 Effect of deformation on surface film

High temperature laboratory tests and electrode calibrations will be performed using the titration equipment developed there. Preliminary tests under laboratory conditions and hydrodynamic modeling will be used to confirm the usability of the electrode.

Other components (INCOM) (5.1 m-m) Objectives

Dissimilar joints

Pressuriser (postponed to 2005)

International/domestic co- operation

RPV-Internals: Physics Modelling .1 RVP-Internals : Long term evolution of

RPV : Mechanics Modelling 1 WP III-1 Models of micro-crack nucleation

The working group will collect existing data on irradiated steel for RPV to provide a comprehensive characterization of flow and fracture. The working group will use fracture toughness models and data from other parts of the subproject to. i) optimize the use of current control sample test results to assess RPV integrity; (ii).

Internals . Integrity of the internals

The WP will develop improved criteria for crack propagation through transgranular cleavage and brittle intergranular fracture and recommend which of the different fracture models considered should be further developed within the Subproject. Theoretical basis of the correlation between the radiation-induced change in yield strength and the shift in the fracture toughness transition temperature.

Co-ordination, administration and training co-ordination (INCOORD) (4,4 m-m)

A detailed plan of the literature survey discussed and agreed during a project meeting with the Swedish partners (16.03). Description of the current state of the model for oxide films on stainless steel and nickel base alloys in LWRs (VYR, SSI).

Deliverables

  • SAFIR 31.01.2005 PROGRESS REPORT 4/04 Project name in english (AGCONT)
  • SAFIR 31.12.2004 PROGRESS REPORT 3/04 Concrete Technological Studies Related to the Construction, Inspection and Reparation of
  • SAFIR 30.1.2005 PROGRESS REPORT 4/04
  • SAFIR 03.02.2005 PROGRESS REPORT 4/04

The result will be a state-of-the-art knowledge of the threat factors involved in control building aging and the behavior of essential materials in aging power plant accidents. Objectives in 2004 Realized Survey of concrete structures of .. nuclear power plants during revisions STATE OF THE ART). The aim is to know the structural behavior and durability of prestressed and non-prestressed concrete structures.

This will mainly affect the vibration of the structure, but not the initial shock response. Thirdly, data on the absence of debris caused by the impact is also required. After the phase of preliminary tests, in August 2004, a detailed design of the test device was made.

2 Models of the impacting objects and the reaction wall

The aim of the project is to improve system modeling and analysis capabilities in Computational Fluid Dynamics (CFD) and Finite Element Stress and Strain Analysis (FEM) for mechanical and structural systems in reactor technology. The vehicle for this geometry model generation and meshing is a modern computer-aided engineering code that will be selected for this task during project implementation. The goal of the project is to significantly reduce the effort of physical modeling and increase the efficiency of modeling and analytical work.

The CFD (Gambit) and FEA (Abaqus) models of the reactor vessel were modified and transferred to VTT for further analysis - loads defined for the ENPRIMA FEA model of the reactor vessel and loops. The task consists of the development and analysis of the containment model, including the internal structures of the containment, the pressure boundary of the containment, and the fluid within the containment. We have decided to abandon work on the project because it is a little outside the scope of this study and would require a very large amount of time and labor resources.

The objective of this subtask is to develop physically reliable correlations with flow friction and flow area within the ice condenser. Ylijoki, APROS Model of the Steam Generator of an EPR Plant, PRO5/7807/04 (confidential), VTT Processes.

Report on the water infiltration model slightly delayed due to latest updates to the code, estimated new issue date early 2005. Follow-up of the work in the project and distribution of results/reports of the MCCI project to STUK, TVO and Fortum NS. A proposal for future CCI experiments within a planned follow-up project was submitted to the OECD/MCCI project management in 1/2005.

The results of the ruthenium experiments already carried out were applied to the work of the Phebus Air Ingress Task Force. It is possible that ruthenium instrumentation applied in the Phebus STLOC1 experiment will be tested at the facility at VTT. Information on the deposition, reevaporation and resuspension of fission products, acquired in the Phebus project, was applied to the development of APROS SA modules for aerosol transport.

A part of the ruthenium work is planned to be included in the PhD thesis of Ulrika Backman. PhD thesis of Ari Auvinen on aerosol transport in severe nuclear accidents will contain information obtained in the Phebus project.

The subtask started with checking the status of the model and how it can be implemented in APROS SA. The Horizon 1 tube experiment is modeled in APROS SA to be used in detailed calculations with a resuspension model. ISP-46 of PHEBUS FPT-1 was selected as one validation case and the circuit portion of the facility was modeled in APROS SA.

VICTORIA-61 has been modeled and the results show that the modeling of aerosol content in APROS SA is adequate. The calculation of the consequence factor with a special code is being developed and the coefficients will be implemented in SaTu as such. A Master's Thesis on the validation of the revaporization model in the Fission Product Model APROS SA (Ville Karttunen) was completed in February 2005.

The appropriate blowdown pipe diameter will be selected and the initial test parameters will be determined. The size of the exhaust pipe (DN200) was the same as in the previous series. Mass flows of steam between 6-13 kg/m2s and total pool temperatures between 10-75 °C were used in the experiments.

The PKL project was completed and the final version of the project report was reviewed and adopted at the PRG meeting in December (participated by Mr. H. Purhonen). The purchase of a new data acquisition system necessitated some changes to the research team's existing data conversion programs and routines. The project staff currently includes two postgraduate scientists who can be considered members of the Young Generation (YG).

  • Planning of the project proposal to OECD 1 Project planning (10 k€, 2 person months)
  • Case studies in the iterative development of the evaluation framework (8,8 monts) Loviisa: Conduction of simulation

She will participate in the implementation of Loviisa races and in the analysis of the research material. Leena Norros gave three lectures (half a day) in the nuclear safety course YK2 on 2 December.

SAFIR 31.1.2005 PROGRESS REPORT 4/04

  • Modifications in electronics due to EU RoHS -directive The changes due to the directive will
  • Participation in IEC TC45 standardisation work The development of the new IEC-
  • Reporting of results Results of the prestudy will be
  • Management of change in nuclear power plants
  • Reporting

A conference paper or journal article summarizing the main results of the work carried out in 2003. The public results of the case study will be reported in the NKS interim report (see Task 4). The conference paper was presented and published in the proceedings of the 9th International Symposium on Logistics in July 2004.

The results of the maintenance culture measure TVO, FKA and LO were presented at the monthly meeting of the Loviisa maintenance unit (February) with more than 100 participants. The results of the maintenance culture remeasurement at Loviisa were presented to the Loviisa project team and maintenance staff at the maintenance unit's monthly meeting (December) with approximately 90 participants. A scientific paper on the results of the assessment of maintenance culture at TVO and FKA was published together with Carl Rollenhagen from Mälardalen University in Sweden.

Two conference abstracts were written and accepted for the IAEA Nuclear Knowledge Management Conference on 7-9 September in Saclay, France. The papers were also edited into articles submitted for publication in the International Journal of Nuclear Knowledge Management.

Continued evaluation of numerical data on the reliability of selected systems of active fire protection from nuclear and non-nuclear installations. Sensitivity analyzes and assessment of maintenance practices of active fire protection systems used in Finnish NPPs as well as assessment of operational actions. Study on sensitivity analyzes and evaluation of current maintenance practices based on these models and collected data.

The first version describes a method for periodic review and analysis of maintenance history to systematically identify, analyze and prevent human-caused CCFs and individual failures. The 2nd draft of the scientific article is written and forwarded to the reference group for comments. First, the availability of ABB experts was limited because they were planning a new high-priority plant.

Two ad hoc group meetings were held and memos from the meetings were written and provided to the steering committee. The OECD/NEA/CSNI/WGRISK Task White Paper on Software Reliability has been commented on and provided to the authors of the paper. Expressions of interest from the SERAMIC project and the NERA project submitted to the evaluation of proposals for EU research in the field of reactor safety (6th Framework Programme).

Viittaukset

LIITTYVÄT TIEDOSTOT

II-308 Step 2: Order reversal of up- and downsam- pler In the intermediate step up- and downsampler are shifted into each branch of the polyphase filter, whereby the order of branch