Test automation scheme for LTE core network element

Modern sophisticated telecommunication devices require even more and more comprehensive testing to ensure quality. The test case amount to ensure well enough coverage of testing has increased rapidly and this increased demand cannot be fulfilled anymore only by using manual testing. Also new agile development models require execution of all test cases with every iteration. This has lead manufactures to use test automation more than ever to achieve adequate testing coverage and quality. This thesis is separated into three parts. Evolution of cellular networks is presented at the beginning of the first part. Also software testing, test automation and the influence of development model for testing are examined in the first part. The second part describes a process which was used to implement test automation scheme for functional testing of LTE core network MME element. In implementation of the test automation scheme agile development models and Robot Framework test automation tool were used. In the third part two alternative models are presented for integrating this test automation scheme as part of a continuous integration process. As a result, the test automation scheme for functional testing was implemented. Almost all new functional level testing test cases can now be automated with this scheme. In addition, two models for integrating this scheme to be part of a wider continuous integration pipe were introduced. Also shift from usage of a traditional waterfall model to a new agile development based model in testing stated to be successful.

Failure modes of passive decay heat removing safety systems of modern nuclear power plants

The purpose of this master’s thesis is to gain an understanding of passive safety systems’ role in modern nuclear reactors projects and to research the failure modes of passive decay heat removal safety systems which use phenomenon of natural circulation. Another purpose is to identify the main physical principles and phenomena which are used to establish passive safety tools in nuclear power plants. The work describes passive decay heat removal systems used in AES-2006 project and focuses on the behavior of SPOT PG system. The descriptions of the main large-scale research facilities of the passive safety systems of the AES-2006 power plant are also included. The work contains the calculations of the SPOT PG system, which was modeled with thermal-hydraulic system code TRACE. The dimensions of the calculation model are set according to the dimensions of the real SPOT PG system. In these calculations three parameters are investigated as a function of decay heat power: the pressure of the system, the natural circulation mass flow rate around the closed loop, and the level of liquid in the downcomer. The purpose of the calculations is to test the ability of the SPOT PG system to remove the decay heat from the primary side of the nuclear reactor in case of failure of one, two, or three loops out of four. The calculations show that three loops of the SPOT PG system have adequate capacity to provide the necessary level of safety. In conclusion, the work supports the view that passive systems could be widely spread in modern nuclear projects.