Molecular markers for progression of squamous cell carcinoma of the skin

Incidence of nonmelanoma skin cancer (NMSC) is increasing. Ultraviolet (UV) –light is a major risk factor for the development of cutaneous SCC. Cutaneous SCCs that develop to chronic ulcers are known to progress and metastasize more easily than UV-induced SCCs. Matrix metalloproteinases (MMPs) are a group of proteolytic enzymes which are suggested to have a role in cancer growth and invasion. The molecular background for progression of cutaneous SCC was examined by immunohistochemistry (IHC) using tissue samples of recessive dystrophic epidermolysis bullosa (RDEB) –associated SCC, sporadic UV-induced SCC, and SCC precursors. IHC studies using tissue microarray (TMA) technique revealed overexpression of MMP-7 and MMP-13 in SCC tumor cells. MMP-7 expression was enhanced especially in the SCC tumor cells of the RDEB –associated SCCs. Studies with SCC cell lines showed that tumor cell derived MMP-7 activated heparin binding epidermal growth factor –like growth factor (HB-EGF) which enhanced the growth of SCC tumor cells. Further, it was shown that type VII collagen (COL7) is expressed in sporadic SCC tumor cells. Interestingly, it was shown that SCC –associated MMP-13 is capable of cleaving COL7 in vitro. COL7 cleavage may have a role in the progression of cutaneous SCC. Studies on serine proteinase inhibitor gene family using SCC tumor cell gene array, quantitative real-time PCR, SCC cell lines, normal human epidermal keratinocytes and IHC of TMA samples showed that serine proteinase inhibitor clade A, member 1 (serpinA1, alpha-1-antitrypsin) is expressed and produced by human SCC tumor cells but not by normal keratinocytes. Moreover, serpinA1 expression was shown to correlate with the progression of cutaneous SCC using transformed HaCaT-cell lines and mouse chemically induced skin SCC model. SerpinA1 may serve as a novel biomarker for the progression of cutaneous SCC. This study elucidated putative mechanisms of the progression of cutaneous SCC and revealed novel biomarker candidates for the progression of SCC of the skin.

Experimental thermal hydraulic studies on the enhancement of safety of LWRs

The safe use of nuclear power plants (NPPs) requires a deep understanding of the functioning of physical processes and systems involved. Studies on thermal hydraulics have been carried out in various separate effects and integral test facilities at Lappeenranta University of Technology (LUT) either to ensure the functioning of safety systems of light water reactors (LWR) or to produce validation data for the computer codes used in safety analyses of NPPs. Several examples of safety studies on thermal hydraulics of the nuclear power plants are discussed. Studies are related to the physical phenomena existing in different processes in NPPs, such as rewetting of the fuel rods, emergency core cooling (ECC), natural circulation, small break loss-of-coolant accidents (SBLOCA), non-condensable gas release and transport, and passive safety systems. Studies on both VVER and advanced light water reactor (ALWR) systems are included. The set of cases include separate effects tests for understanding and modeling a single physical phenomenon, separate effects tests to study the behavior of a NPP component or a single system, and integral tests to study the behavior of the whole system. In the studies following steps can be found, not necessarily in the same study. Experimental studies as such have provided solutions to existing design problems. Experimental data have been created to validate a single model in a computer code. Validated models are used in various transient analyses of scaled facilities or NPPs. Integral test data are used to validate the computer codes as whole, to see how the implemented models work together in a code. In the final stage test results from the facilities are transferred to the NPP scale using computer codes. Some of the experiments have confirmed the expected behavior of the system or procedure to be studied; in some experiments there have been certain unexpected phenomena that have caused changes to the original design to avoid the recognized problems. This is the main motivation for experimental studies on thermal hydraulics of the NPP safety systems. Naturally the behavior of the new system designs have to be checked with experiments, but also the existing designs, if they are applied in the conditions that differ from what they were originally designed for. New procedures for existing reactors and new safety related systems have been developed for new nuclear power plant concepts. New experiments have been continuously needed.

Practical Solutions for Increased Safety in Paper Mill Operations

Tämä diplomityö käsittelee työterveys- ja työturvallisuushallinnan (TTT) sekä ympäristönsuojelun ongelmia ja riskejä, joita tehdasalueen toiminnanharjoittaja kohtaa ulkoistaessaan tehdastoimintojaan ja siirtyessään käyttämään 24 h ulkoisia kunnossapitopalveluja. Teoriaosa selventää ulkoistukseen liittyviä lainmukaisia määräyksiä ja vaatimuksia koskien terveyden, turvallisuuden ja ympäristöongelmien hallintaa sellu-, paperi- ja kartonkitehtaissa Euroopassa, Yhdysvalloissa ja Suomessa. TTT-toiminnan tason sekä ympäristönsuojelun tason mittaamisen ongelmat tuodaan esille. Olemassa olevia kansainvälisiä TTT-johtamisjärjestelmien ja ympäristöjärjestelmien standardeja, riskien hallintatyökaluja ja ohjelmia esitellään lyhyesti. Käytännön osa toteutettiin tapaustutkimuksena, jonka kohteena oli Äänekosken tehdaskombinaatti ja kemianteollisuuden laitos, Noviant CMC Oy. TTT-hallintatoimien ja ympäristönsuojelun ongelmia tutkitaan tehdastoimintoja ulkoistettaessa. Integroidun johtamisjärjestelmän auditointimenettelyt, ulkoistuksen kohdealueet, pk-yrityksien riskien hallinta ja ulkoisten työntekijöiden turvallisuuskoulutus ovat erityisen tarkastelun alla. Käyttäen hyväksi kerättyä TTT- ja ympäristöaineistoa, suunniteltiin malli ja sisältöehdotus uudelle internet-selain tyyppiselle työkalulle TTT- ja ympäristöasioiden hallinnan avuksi. Työkalu on tarkoitettu palvelemaan Noviant CMC Oy:n eri sidosryhmien tarpeita. Diplomityön käytännön osa muodostaa pohjan JP MILLSAFE - pilottiprojektille, joka käynnistettiin internet-selain tyyppisen turvallisuuspalvelusovelluksen kehittämiseksi palvelemaan Äänekosken tehdaskombinaatin eri sidosryhmien tarpeita.

Borrelia burgdorferi evades the effects of ceftriaxone treatment in a mouse model of Lyme borreliosis

Borrelia burgdorferi infektoitujen hiirten antibioottihoidon jälkeinen oireilu Lymen borrelioosi on puutiaisten välittämä monimuotoinen infektiotauti, jonka tunnetuin oire on ns. vaeltava ihottuma eli erythema migrans. Muita tavallisia ilmentymiä ovat erityisesti nivel- ja hermosto-oireet sekä harvemmin sydän- ja silmäoireet. Suurin osa potilaista paranee täysin terveeksi antibioottihoidon avulla, mutta jopa 10 % borrelioosiin sairastuneista oireilee suositusten mukaisesta hoidosta huolimatta. Pitkittyneen oireilun on ajateltu johtuvan mm. infektion laukaisemasta autoimmuunitaudista tai kroonisesta infektiosta, mutta teorioiden tueksi ei ole kyetty esittämään kiistattomia todisteita. Onkin todennäköistä, että antibioottihoidon jälkeisen oireilun takana on useampia mekanismeja eikä yksi teoria selitä kaikkien potilaiden oireilua. Tässä väitöskirjatyössä on tutkittu hoidonjälkeistä borrelioosia hiirimallin avulla. Varhaisvaiheessa (2 viikkoa infektoinnin jälkeen) annettu antibiootti vähensi hiirten nivelturvotusta ja esti B. burgdorferi – bakteerin kasvun kudoksista otetuista näytteissä. Hoidettu¬jen hiirten B. burgdorferi -spesifiset IgG-luokan vasta-aineet pysyivät kuitenkin koholla ja osasta kudosnäytteistä löytyi B. burgdorferi:n DNA:ta PCR-tutkimuksen avulla. Mikäli hiiret hoidettiin myöhäisessä vaiheessa (yli 18 viikkoa infektoinnista) tulokset olivat muuten samanlaiset, mutta keftriaksoni ei vaikuttanut nivelturvotukseen. Näin hiirissä oli aikaansaatu tilanne, joka on hyvin samankaltainen ihmisen hoitoresistentin borrelia-artriitin kanssa: oireet jatkuvat, mutta taudinaiheuttajaa ei saada esiin. Inflammaatiota vaimentavaa anti-TNF-alphaa on käytetty nivelreuman hoidossa menestyksekkäästi huonosti muuhun hoitoon reagoivilla potilailla ja siitä syystä sen ajateltiin voivan vaikuttaa suotuisasti myös B. burgdorferi -infektoitujen hiirten hoidonjälkeiseen nivelturvotukseen. Sillä ei kuitenkaan ollut vaikutusta nivelturvotukseen, mutta yllättäen hoidon jälkeen osa hiirten kudosnäytteistä osoittautui viljelypositiivisiksi. On siis ilmeistä, että hiirimallissamme osa B. burgdorferi spirokeetoista pystyy välttämään keftriaksonihoidon vaikutuksen joko hakeutumalla elimistössä kudokseen, jossa antibiootin pitoisuus ei nouse riittävän korkeaksi, tai ne kykenevät muuntautumaan metabolisesti inaktiiviin tilaan eikä mikrobilääke yhdessä immuunipuolustuksen kanssa onnistu tappamaan niitä. Jatkotutkimuksissa selvitimme B. burgdorferi - spirokeetan mahdollista piilopaikkaa tutkimalla antibioottihoidon jälkeen useita eri kudoksia PCR-menetelmällä. Tulosten perusteella spirokeetta näyttää suosivan nivelkudosta tai soluja, joita esiintyy nivelessä runsaasti. On kuitenkin edelleen epäselvää, missä muodossa B. burgdorferi –spirokeetat säilyvät kudoksessa antibioottihoidon jälkeen.

Thermal-Hydraulic Studies on the Safety Of VVER-440 Type Nuclear Power Plants

This thesis includes several thermal hydraulic analyses related to the Loviisa WER 440 nuclear power plant units. The work consists of experimental studies, analysis of the experiments, analysis of some plant transits and development of a calculational model for calculation of boric acid concentrations in the reactor. In the first part of the thesis, in the case of won of boric acid solution behaviour during long term cooling period of LOCAs, experiments were performed in scaled down test facilities. The experimental data together with the results of RELAPS/MOD3 simulations were used to develop a model for calculations of boric acid concentrations in the reactor during LOCAs. The results of calculations showed that margins to critical concentrations that would lead to boric acid crystallization were large, both in the reactor core and in the lower plenum. This was mainly caused by the fact that water in the primary cooling circuit includes borax (Na)BsO,.IOHZO), which enters the reactor when ECC water is taken from the sump and greatly increases boric acid solubility in water. In the second part, in the case of simulation of horizontal steam generators, experiments were performed with PACTEL integral test loop to simulate loss of feedwater transients. The PACTEL experiments, as well as earlier REWET III natural circulation tests, were analyzed with RELAPS/MOD3 Version Sm5 code. The analysis showed that the code was capable of simulating the main events during the experiments. However, in the case of loss of secondary side feedwater the code was not completely capable to simulate steam superheating in the secondary side of the steam generators. The third part of the work consists of simulations of Loviisa VVER reactor pump trip transients with RELAPSlMODI Eur, RELAPS/MOD3 and CATHARE codes. All three codes were capable to simulate the two selected pump trip transients and no significant differences were found between the results of different codes. Comparison of the calculated results with the data measured in the Loviisa plant also showed good agreement.

APROS model validation in case of fast transients in a boiling water reactor

This Master´s thesis investigates the performance of the Olkiluoto 1 and 2 APROS model in case of fast transients. The thesis includes a general description of the Olkiluoto 1 and 2 nuclear power plants and of the most important safety systems. The theoretical background of the APROS code as well as the scope and the content of the Olkiluoto 1 and 2 APROS model are also described. The event sequences of the anticipated operation transients considered in the thesis are presented in detail as they will form the basis for the analysis of the APROS calculation results. The calculated fast operational transient situations comprise loss-of-load cases and two cases related to a inadvertent closure of one main steam isolation valve. As part of the thesis work, the inaccurate initial data values found in the original 1-D reactor core model were corrected. The input data needed for the creation of a more accurate 3-D core model were defined. The analysis of the APROS calculation results showed that while the main results were in good accordance with the measured plant data, also differences were detected. These differences were found to be caused by deficiencies and uncertainties related to the calculation model. According to the results the reactor core and the feedwater systems cause most of the differences between the calculated and measured values. Based on these findings, it will be possible to develop the APROS model further to make it a reliable and accurate tool for the analysis of the operational transients and possible plant modifications.

Repair of segmental bone defects with fiber-reinforced composite: a study of material development and an animal model on rabbits

The Repair of segmental defects in load-bearing long bones is a challenging task because of the diversity of the load affecting the area; axial, bending, shearing and torsional forces all come together to test the stability/integrity of the bone. The natural biomechanical requirements for bone restorative materials include strength to withstand heavy loads, and adaptivity to conform into a biological environment without disturbing or damaging it. Fiber-reinforced composite (FRC) materials have shown promise, as metals and ceramics have been too rigid, and polymers alone are lacking in strength which is needed for restoration. The versatility of the fiber-reinforced composites also allows tailoring of the composite to meet the multitude of bone properties in the skeleton. The attachment and incorporation of a bone substitute to bone has been advanced by different surface modification methods. Most often this is achieved by the creation of surface texture, which allows bone growth, onto the substitute, creating a mechanical interlocking. Another method is to alter the chemical properties of the surface to create bonding with the bone – for example with a hydroxyapatite (HA) or a bioactive glass (BG) coating. A novel fiber-reinforced composite implant material with a porous surface was developed for bone substitution purposes in load-bearing applications. The material’s biomechanical properties were tailored with unidirectional fiber reinforcement to match the strength of cortical bone. To advance bone growth onto the material, an optimal surface porosity was created by a dissolution process, and an addition of bioactive glass to the material was explored. The effects of dissolution and orientation of the fiber reinforcement were also evaluated for bone-bonding purposes. The Biological response to the implant material was evaluated in a cell culture study to assure the safety of the materials combined. To test the material’s properties in a clinical setting, an animal model was used. A critical-size bone defect in a rabbit’s tibia was used to test the material in a load-bearing application, with short- and long-term follow-up, and a histological evaluation of the incorporation to the host bone. The biomechanical results of the study showed that the material is durable and the tailoring of the properties can be reproduced reliably. The Biological response - ex vivo - to the created surface structure favours the attachment and growth of bone cells, with the additional benefit of bioactive glass appearing on the surface. No toxic reactions to possible agents leaching from the material could be detected in the cell culture study when compared to a nontoxic control material. The mechanical interlocking was enhanced - as expected - with the porosity, whereas the reinforcing fibers protruding from the surface of the implant gave additional strength when tested in a bone-bonding model. Animal experiments verified that the material is capable of withstanding load-bearing conditions in prolonged use without breaking of the material or creating stress shielding effects to the host bone. A Histological examination verified the enhanced incorporation to host bone with an abundance of bone growth onto and over the material. This was achieved with minimal tissue reactions to a foreign body. An FRC implant with surface porosity displays potential in the field of reconstructive surgery, especially regarding large bone defects with high demands on strength and shape retention in load-bearing areas or flat bones such as facial / cranial bones. The benefits of modifying the strength of the material and adjusting the surface properties with fiber reinforcement and bone-bonding additives to meet the requirements of different bone qualities are still to be fully discovered.

Safety study of hydrogen peroxide direct synthesis

Kandidaatintyön johdantokappaleessa esitellään vetyperoksidi ja mihin sitä käytetään teollisuudessa. Työssä vertaillaan antrakinoniprosessia ja suoraa prosessia sekä selvitetään nykyisin enemmän vetyperoksidituotantoon käytetyn antrakinoniprosessin ongelmakohdat ja osoitetaan, miksi suora synteesi vetyperoksidin tuotannossa olisi parempi vaihtoehto. Kandidaatintyön käsittelee suurilta osin turvallisuusongelmia, joita esiintyy suoran synteesin yhteydessä. Kirjallisuudesta on etsitty ratkaisuja näihin ongelmiin, kuten membraaniprosessin käyttöä räjähdysvaaran välttämiseksi. Pienemmän reaktorin eli ns. mikroreaktorin käyttö tuo mukanaan monia etuja vetyperoksidin tuotantoon. Tällöin prosessi on turvallisempi ja sitä on helpompi hallita. Mikroreaktorissa voidaan käyttää korkeampia lämpötiloja ja paineita kuin makroreaktorilla ilman, että räjähdysvaara prosessissa kasvaisi. Mikroreaktorin sisällä olevat mikrokanavat luovat turvallisen ympäristön synteesille. Aspen plus – simulointiohjelmalla mallinnettiin ja simulointiin suoran prosessin kriittisiä virtoja mikroreaktorissa. Tarkoituksena oli löytää virrat, joissa kulkee mahdollisesti räjähtävä kaasuseos. Kaasumaiset prosessivirrat ovat kriittisimmät vetyperoksidin suorassa synteesissä, koska ne aiheuttavat todennäköisemmin räjähdyksen kuin nestemäiset prosessivirrat. Kaikkein eniten prosessiturvallisuutta uhkaavat ainevirrat ennen ja jälkeen mikroreaktoria.

Licensing Model Development for Small Modular Reactors (SMRs) - Focusing on the Finnish Regulatory Framework

Recently, Small Modular Reactors (SMRs) have attracted increased public discussion. While large nuclear power plant new build projects are facing challenges, the focus of attention is turning to small modular reactors. One particular project challenge arises in the area of nuclear licensing, which plays a significant role in new build projects affecting their quality as well as costs and schedules. This dissertation - positioned in the field of nuclear engineering but also with a significant section in the field of systems engineering - examines the nuclear licensing processes and their suitability for the characteristics of SMRs. The study investigates the licensing processes in selected countries, as well as other safety critical industry fields. Viewing the licensing processes and their separate licensing steps in terms of SMRs, the study adopts two different analysis theories for review and comparison. The primary data consists of a literature review, semi-structured interviews, and questionnaire responses concerning licensing processes and practices. The result of the study is a recommendation for a new, optimized licensing process for SMRs. The most important SMR-specific feature, in terms of licensing, is the modularity of the design. Here the modularity indicates multi-module SMR designs, which creates new challenges in the licensing process. As this study focuses on Finland, the main features of the new licensing process are adapted to the current Finnish licensing process, aiming to achieve the main benefits with minimal modifications to the current process. The application of the new licensing process is developed using Systems Engineering, Requirements Management, and Project Management practices and tools. Nuclear licensing includes a large amount of data and documentation which needs to be managed in a suitable manner throughout the new build project and then during the whole life cycle of the nuclear power plant. To enable a smooth licensing process and therefore ensure the success of the new build nuclear power plant project, management processes and practices play a significant role. This study contributes to the theoretical understanding of how licensing processes are structured and how they are put into action in practice. The findings clarify the suitability of different licensing processes and their selected licensing steps for SMR licensing. The results combine the most suitable licensing steps into a new licensing process for SMRs. The results are also extended to the concept of licensing management practices and tools.

Rigorous development of safety-critical systems

Nowadays, computer-based systems tend to become more complex and control increasingly critical functions affecting different areas of human activities. Failures of such systems might result in loss of human lives as well as significant damage to the environment. Therefore, their safety needs to be ensured. However, the development of safety-critical systems is not a trivial exercise. Hence, to preclude design faults and guarantee the desired behaviour, different industrial standards prescribe the use of rigorous techniques for development and verification of such systems. The more critical the system is, the more rigorous approach should be undertaken. To ensure safety of a critical computer-based system, satisfaction of the safety requirements imposed on this system should be demonstrated. This task involves a number of activities. In particular, a set of the safety requirements is usually derived by conducting various safety analysis techniques. Strong assurance that the system satisfies the safety requirements can be provided by formal methods, i.e., mathematically-based techniques. At the same time, the evidence that the system under consideration meets the imposed safety requirements might be demonstrated by constructing safety cases. However, the overall safety assurance process of critical computerbased systems remains insufficiently defined due to the following reasons. Firstly, there are semantic differences between safety requirements and formal models. Informally represented safety requirements should be translated into the underlying formal language to enable further veri cation. Secondly, the development of formal models of complex systems can be labour-intensive and time consuming. Thirdly, there are only a few well-defined methods for integration of formal verification results into safety cases. This thesis proposes an integrated approach to the rigorous development and verification of safety-critical systems that (1) facilitates elicitation of safety requirements and their incorporation into formal models, (2) simplifies formal modelling and verification by proposing specification and refinement patterns, and (3) assists in the construction of safety cases from the artefacts generated by formal reasoning. Our chosen formal framework is Event-B. It allows us to tackle the complexity of safety-critical systems as well as to structure safety requirements by applying abstraction and stepwise refinement. The Rodin platform, a tool supporting Event-B, assists in automatic model transformations and proof-based verification of the desired system properties. The proposed approach has been validated by several case studies from different application domains.

Development and Effect Analysis of the Asteri Consultative Auditing Process - Safety and Security Management in Educational Institutions

The Finnish legislation requires for a safe and secure learning environment. However, the comprehensive, risk based safety and security management (SSM) and the management commitment in the implementation and development of the SSM are not mentioned in the legislation. Multiple institutions, operators and researchers have studied and developed safety and security in educational institutions over the past decade. Typically the approach has been fragmented and without bringing up the importance of the comprehensive SSM. The development needs of the safety and security operations in universities have been studied. However, in universities of applied sciences (UASs) and in elementary schools (ESs), the performance level, strengths and weaknesses of the comprehensive SSM have not been studied. The objective of this study was to develop the comprehensive, risk based SSM of educational institutions by developing the new Asteri consultative auditing process and study its effects on auditees. Furthermore, the performance level in the comprehensive SSM in UASs and ESs were studied using Asteri and the TUTOR model developed by the Keski-Uusimaa Department for Rescue Services. In addition, strengths, development needs and differences were identified. In total, 76 educational institutions were audited between the years 2011 and 2014. The study is based on logical empiricism, and an observational applied research design was used. Auditing, observation and an electronic survey were used for data collection. Statistical analysis was used to analyze the collected information. In addition, thematic analysis was used to analyze the development areas of the organizations mentioned by the respondents in the survey. As one of the main contributions, this research presents the new Asteri consultative auditing process. Organizations with low performance levels on the audited subject benefit the most from the Asteri consultative auditing process. Asteri may be usable in many different types of audits, not only in SSM audits. As a new result, this study provides new knowledge on attitudes related to auditing. According to the research findings, auditing may generate negative attitudes and the auditor should take them into account when planning and preparing for audits. Negative attitudes can be compensated by producing added value, objectivity and positivity for the audit and, thus, improve the positive effects of auditing on knowledge and skills. Moreover, as the results of this study shows, auditing safety and security issues do not increase feelings of insecurity, but rather increase feelings of safety and security when using the new Asteri consultative auditing process with the TUTOR model. The results showed that the SSM in the audited UASs was statistically significantly more advanced than that in the audited ESs. However, there is still room for improvement in the ESs and the UASs as the approach to the SSM was fragmented. It can be assumed that the majority of Finnish UASs and ESs do not likely meet the basic level of the comprehensive, risk based the SSM.

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.