From 1976 to 1992 Portland General Electric (PGE) -- a private utility based in Portland, Oregon -- operated the Trojan Nuclear Plant near Rainier, Oregon, on the bank of the Columbia River. Trojan was the first commercial nuclear facility in the Pacific Northwest and was the largest such facility in U.S. history. From its origins, Trojan was the focus of growing conflict over atomic energy facilities and their environmental effects, risks, and costs. This thesis traces the history of Trojan, including the conditions in which PGE decided to build the plant as well as the changing conditions in which the environmental movement in Oregon worked to impact the operation of Trojan and the development of further atomic energy facilities in the region. Two sets of values, largely endemic to the region, came into conflict in the debate over Trojan: one which valued preservation of vital natural systems over all else, and another that elevated technological progress to supreme importance in achieving the ultimate social good. Supporters of Trojan and anti-nuclear activists both viewed misinformation about nuclear power as one of the central problems in the way that Oregon residents viewed nuclear power. Although there were many loyal supporters of Trojan, particularly in Columbia County, there were also a great number who viewed the technology cautiously. While both PGE and nuclear opponents worked diligently to sway public opinion, many activists did so by attempting to uncover and publicize hidden information about the design and operation of Trojan, and the nuclear fuel cycle in general. This included efforts throughout the plant's lifetime to develop opportunities for intervention in administrative proceedings, government hearings, and other arenas which often discourage citizen involvement. Related to the public debate over Trojan were ongoing operational difficulties and changing economic conditions, which contributed to the decision PGE announced in 1993 that Trojan would be permanently shut down. This study is based primarily on coverage from newspapers and periodicals, new and extant oral history interviews, documents from the personal files of activists, as well as various archival materials associated with PGE, activist groups, and government agencies.

Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975. / Vita. / Bibliography: leaves 460-462. / by Raymond Eng. / Ph.D.

With the initiative taken by the SUNRISE project (Sustainable Nuclear Energy Research in Sweden) to construct a Lead-cooled research reactor, this thesis intends to extend the knowledge within nuclear fuel development. By using integral iterative modelling and simulating techniques that mimic real-world phenomena, novel fuel materials like uranium nitride are assessed for future validation.  The work deals with the fuel performance analysis of the SUNRISE LFR, employing the TRANSURANUS fuel performance code. This code contains a collection of model parameters that simulate the thermo-mechanical behaviour of the fuel cladding system on an engineering scale of the reactor core. A comparative study is performed for UO$_2$ and UN fuels using the same input data such as fuel geometry. In addition, predefined information relating to the neutronics analysis for the reactor was used as input to the TRANSURANUS code along with literature reviews to select the accurate models on the reactor, fuel, and its behaviour. Furthermore, a sensitivity study is carried out to assess the models and parameters affected by more significant uncertainty.  The uncertainty analysis of the UN fuel's swelling models is performed using the Dakota toolkit. The sampling of input data using the Dakota software coupled with the nuclear simulation program TRANSURANUS produced partial rank correlation coefficients significant to the modelling. However, since the assessed models displayed the same correlation coefficients, the results conclude that a deeper understanding of the theoretical swelling model might be required. / I samverkan med initiativet av SUNRISEprojektet (Sustainable Nuclear Energy Research inSweden) som syftar att bygga en blykyld forskningsreaktor, avser denna avhandling att utökakunskapen inom kärnbränsleutveckling. Med användning av integral iterativ modellering ochsimuleringstekniker som efterliknar verkliga fenomen bedöms nya bränslematerial somuranmononitrid för framtida validering. Arbetet behandlar analysen av bränsleprestanda för SUNRISE LFR, med användning avTRANSURANUS bränsleprestandakod. Denna kod innehåller en samling modellparametrarsom simulerar det termomekaniska beteendet hos bränslebetäckningssystemet i en tekniskskala för reaktorkärnan. En jämförande studie utförs för UO2 och UN-bränslen med sammaingångsdata som t.ex bränslegeometrin. Dessutom användes fördefinierad information om denneutroniska analysen för reaktorn som ingångsdata till TRANSURANUSkoden tillsammans medgranskning av litteratur för att välja lämpliga modeller för reaktorn, bränslet och dess beteende.Därtill genomfördes en känslighetsstudie för att bedöma de modeller och parametrar sompåverkas av mer betydande osäkerhet. Osäkerhetsanalysen av UN-bränslets svällningsmodeller utförs med hjälp av Dakota-verktyget.Samlingen av indata med Dakota-programmet i kombination medkärnkraftssimuleringsprogrammet TRANSURANUS gav korrelationskoefficienter för partiell rangviktiga för modelleringen. Eftersom de utvärderade modellerna visade sammakorrelationskoefficienter, tyder slutsatsen på att en djupare förståelse av den teoretiskasvällningsmodellen krävs

Nuclear power is a foundational part of our electrical grid in the present and through our transition towards more sustainable and renewable alternatives. However, given the serious consequences of reckless and/or dangerous operation of nuclear power plants, they are subject to strict regulation and supervision by the Swedish radiation protection authority (SSM) and other regulating bodies (e.g. IAEA). In order to prove that a nuclear power plant is operating in a safe and accident preventative manner, the “Safety Analysis Report” (SAR) is created and submitted. The SAR categorizes and ranks all possible incidents and operation affecting events in terms of risk and available countermeasures to ensure that the radioactive release from the power plant and impact on a third party from any event is at acceptable levels. This projects limits its analysis to flooding of the reactor building or “internal flooding events” as described in the SAR. To determine the affected areas and impacted systems of any flooding event, deterministic safety analyses (DSA) are employed. The goal of this project is to develop a comprehensive thermohydraulic model of the Forsmark 2 reactor building and evaluate its performance with respect to the previously used MATLAB model. The model  should allow for a detailed nodalisation of the reactor building as well as realistic modelling of structural components such as doors, hatches, stairwells and drainage systems. The resulting thermohydraulic model  can be used to evaluate different flooding incidents dynamically and follow the spread of water and/or steam throughout the reactor building. Furthermore, the resulting pressure changes and heat generation in the reactor building can also be evaluated. The model allows for the possibility to couple the thermohydraulic reactor building model with the existing power plant systems model to holistically evaluate the power plant response to flooding related incidents. / Kärnkraft är en grundläggande del av vårt elnät i nuläget och under vår övergång mot mer hållbara och förnybara alternativ. Men med tanke på de allvarliga konsekvenserna av vårdslös och/eller farlig drift av kärnkraftverk, är de föremål för strikt reglering och tillsyn av Strålsäkerhetsmyndigheten (SSM) och andra reglerande organ (t.ex. IAEA). För att bevisa att ett kärnkraftverk drivs på ett säkert och olycksförebyggande sätt, upprättas och inlämnas "Strålsäkerhetsanalysrapport" (SAR). SAR kategoriserar och rangordnar alla möjliga incidenter och händelser som påverkar driften i termer av risk och tillgängliga motåtgärder för att säkerställa att radioaktiva utsläpp från kraftverket och påverkan på tredje person från någon händelse är på acceptabla nivåer. Detta projekt begränsar sin analys till översvämning av reaktorbyggnaden eller "interna översvämningshändelser" enligt beskrivningen i SAR. För att fastställa de påverkade områdena och drabbade systemen vid en översvämningshändelse, används deterministiska säkerhetsanalyser (DSA). Målet med detta projekt är att utveckla en omfattande termohydraulisk modell av Forsmark 2 reaktorbyggnad och utvärdera dess prestanda i förhållande till den tidigare använda MATLAB-modellen. Modellen ska möjliggöra en detaljerad nodalisering av reaktorbyggnaden samt realistisk modellering av strukturella komponenter som dörrar, luckor, trapphus och dräneringssystem. Den resulterande termohydrauliska modellen kan användas för att dynamiskt utvärdera olika översvämningsincidenter och följa spridningen av vatten och/eller ånga genom reaktorbyggnaden. Dessutom kan de resulterande tryckförändringarna och värmegenereringen i reaktorbyggnaden också utvärderas. Modellen möjliggör koppling av den termohydrauliska reaktorbyggnadsmodellen med den befintliga kraftverkssystemmodellen för att holistiskt utvärdera kraftverkets respons på översvämningsrelaterade händelser.

South Africa is in the critical process of determining the profile of its power composition for the next 30 years and beyond. From the IRP2010 it seems that too much emphasis is placed on renewable energy, coal and other technologies and too little on nuclear power. In the revision of the IRP2010, the renewable portion of the energy composition has been increased substantially from 11.4 to 17.8GW, where nuclear remains on 9.6GW (DME, 2011). The purpose of this research is to investigate and compare power-generating technologies. The investigation of the different technologies is corroborated through modelling the IRP2010 planned energy mix efficiency, as well as a proposed energy mix. These models will be built using Microsoft Excel. Topics not investigated are socio-economic impacts and politics around nuclear energy in South Africa. The main finding of the research is that nuclear power is the best option for base load energy in order to meet South Africa‟s growing demand for electricity. It has the highest load factor, longest economic life, best safety record, adheres to the Kyoto protocol, uses the least fresh water and is economically competitive. It addresses all the concerns stipulated in the IRP2010 and the technology also offers benefits outside the electricity industry, such as the mining, medical, agriculture and research sectors. This versatile, reliable and powerful technology holds great benefits and has the potential to uplift the quality of life for the whole South African nation. / MSc (Nuclear Engineering), North-West University, Potchefstroom Campus, 2015

South Africa is in the critical process of determining the profile of its power composition for the next 30 years and beyond. From the IRP2010 it seems that too much emphasis is placed on renewable energy, coal and other technologies and too little on nuclear power. In the revision of the IRP2010, the renewable portion of the energy composition has been increased substantially from 11.4 to 17.8GW, where nuclear remains on 9.6GW (DME, 2011). The purpose of this research is to investigate and compare power-generating technologies. The investigation of the different technologies is corroborated through modelling the IRP2010 planned energy mix efficiency, as well as a proposed energy mix. These models will be built using Microsoft Excel. Topics not investigated are socio-economic impacts and politics around nuclear energy in South Africa. The main finding of the research is that nuclear power is the best option for base load energy in order to meet South Africa‟s growing demand for electricity. It has the highest load factor, longest economic life, best safety record, adheres to the Kyoto protocol, uses the least fresh water and is economically competitive. It addresses all the concerns stipulated in the IRP2010 and the technology also offers benefits outside the electricity industry, such as the mining, medical, agriculture and research sectors. This versatile, reliable and powerful technology holds great benefits and has the potential to uplift the quality of life for the whole South African nation. / MSc (Nuclear Engineering), North-West University, Potchefstroom Campus, 2015

Thesis (MScEng)--Stellenbosch University, 2014. / ENGLISH ABSTRACT: Traditionally nuclear reactor power plants have been optimised for electrical power generation only. In the light of the ever-rising cost of dwindling fossil fuel resources as well the global polluting effects and consequences of their usage, the use of nuclear energy for process heating is becoming increasingly attractive. In this study the use of a so-called cogeneration plant in which a nuclear reactor energy source is optimised for the simultaneous production of superheated steam for electrical power generation and process heat is considered and analysed. The process heat superheated steam is generated in a once-through steam generator of heat pipe heat exchanger with intermediate fluid while steam for power generation is generated separately in a once-through helical coil steam generator. A 750 °C, 7 MPa helium cooled HTMR has been conceptually designed to simultaneously provide steam at 540 °C, 13.5 MPa for the power unit and steam at 430 °C, 4 MPa for a coal-to-liquid fuel process. The simulation and dynamic control of such a typical cogeneration plant is considered. In particular, a theoretical model of a typical plant will be simulated with the aim of predicting the transient and dynamic behaviour of the HTMR in order to provide guideline for the control of the plant under various operating conditions. It was found that the simulation model captured the behaviour of the plant reasonably well and it is recommended that it could be used in the detailed design of plant control strategies. It was also found that using a 1500 MW-thermal HTMR the South African contribution to global pollution can be reduced by 1.58%. / AFRIKAANSE OPSOMMING: Tradisioneel is kernkragaanlegte vir slegs elektriese kragopwekking geoptimeer. In die lig van die immer stygende koste van uitputbare fossielbrandstohulpbronne asook die besoedelingsimpak daarvan wêreldwyd, word die gebruik van kernkrag vir prosesverhitting al hoe meer aanlokliker. In hierdie studie word die gebruik van ‘n sogenaamde mede-opwekkingsaanleg waarin ‘n kernkragreaktor-energiebron vir die gelyktydige produksie van oorverhitte stoom vir elektriese kragopwekking en proseshitte oorweeg ontleed word. Die oorvehitte stoom word in ‘n enkeldeurvloei-stoomopwekking van die hittepyp-hitteruiler met tussenvloeistof opgewek en stoom vir kragopwekking word apart in ‘n enkeldeurvloei-spiraalspoel-stoomopwekker opgewek. ‘n 750 °C, 7 MPa heliumverkoelde HTMR is konseptueel ontwerp vir die gelytydige veskaffing van stoom by 540 °C, 13.5 MPa, vir die kragopwekkings eenheid, en stoom by 430 °C, 4 MPa, vir ‘n steenkool-tot-vloeibare (CTL) brandstoff proses. Die simulasie en dinamiese beheer van ‘n tipiese HTMR mede-opwekkingsaanleg word beskou. ‘n die besonder word ‘n teoretiese model van die transiënte en dinamiese gedrag van die aanleg gesimuleer om sodoene riglyne te identifiseer vir die ontwikkeling van dinamiese beheer strategië vir verskillende werkstoestande van die aanleg. Daar was ook gevind dat die simulasie model van die aanleg se gedrag goed nageboots word en dat dit dus gebruik kan word vir beheer strategie doeleindes. Indien so ‘n 1500 MW-termies HTMR gebruik word sal dit die Suid Afrikaanse besoedling met 1.58% sal kan verminder.

The thesis presents an investigation of the direct and indirect impact of environmental legal principles on international nuclear law and the regulation of nuclear activities, seeking to offer an up-to-date material for decision-making institutions and society on the main challenges that are necessary to overcome in order to reach the situation where nuclear energy could in the most effective way contribute to the implementation of environmental aims and where the environment could be adequately protected against any risks of the possible transboundary damage caused by nuclear activities developed for peaceful purposes (the analysis carried out in the thesis adopts an ecocentric rather than anthropocentric approach). The environmental legal principles chosen as an object for the analysis are those that provide for the guidelines and directions for the development of the international norms of nuclear law as well as lay down the regime for protecting natural environment (environmental safeguards) and international liability for environmental damage caused as a result of nuclear activities (i.e., the principles of cooperation, sustainable development, prevention, precaution, polluter pays, and the principle of information). After defining the points of interaction between international environmental law and nuclear law, the analysis proceeds with the examination of problems related to the evolution of environmental legal principles and their perspectives in the area of the... [to full text] / Disertacijoje nagrinėjama tiesioginė ir netiesioginė aplinkos teisės principų įtaka tarptautinei branduolinei teisei ir branduolinės energetikos objektų reguliavimui, siekiant informuoti sprendimus priimančias institucijas ir visuomenę apie pagrindinius iššūkius, kuriuos reikia įveikti siekiant, kad branduolinė energetika kiek įmanoma veiksmingiau prisidėtų įgyvendinant aplinkosauginius tikslus, o aplinka būtų tinkamai apsaugota nuo taikiais tikslais vystomos branduolinės veiklos keliamos tarpvalstybinės žalos rizikos (analizės metu vyrauja ekocentrinis, o ne antropocentrinis požiūris). Analizės objektu pasirinkti tie aplinkos teisės principai, kurie numato gaires tarptautinėms branduolinės teisės normoms plėtotis, nustato gamtos apsaugos režimą (saugiklius) bei tarptautinę atsakomybę, atsirandančią dėl branduolinės energetikos objektų sukelto žalingo poveikio aplinkai (t.y. bendradarbiavimo, darnaus vystymosi, prevencijos, atsargumo, teršėjas moka ir informavimo principai). Nurodžius tarptautinės aplinkos teisės ir branduolinės teisės sąlyčio taškus, toliau nagrinėjamos problemos dėl aplinkos teisės principų raidos ir perspektyvų branduolinės energetikos objektų reglamentavimo srityje, pateikiama susijusi nacionalinių ir tarptautinių ginčų sprendimo institucijų dėl branduolinės energetikos objektų praktika, atsakoma į klausimą, kuris iš minėtų aplinkos teisės principų veikimo modelių – tiesioginis ar netiesioginis – yra veiksmingesnis siekiant įgyvendinti užsibrėžtus... [toliau žr. visą tekstą]

This thesis examines the opposition to civil nuclear energy in France and West Germany during the 1970s, arguing that small-scale interactions among its diverse participants led to broad changes in their personal lives and political environments. Drawing extensively on oral history interviews with former activists as well as police reports, media coverage and protest ephemera, this thesis shows how individuals at the grassroots built up a movement that transcended national (and social) borders. They were able to do so in part because nuclear power was such a multivalent symbol at the time. Residents of towns near planned power stations felt that nuclear technology represented an intervention in their community by state and industry, a potential threat to their health, wealth and way of life. In the decade after 1968, concerns like these coalesced with criticisms of capitalism, the state, militarism and consumer society that were being made by a more politicised constituency. This made the anti-nuclear movement both broad-based and highly fragmented. Activist networks linked people across existing national, political and social boundaries, but the social world of activism was subject to its own divisions (such as between locals and outsiders or between militant and non-violent activists). By analysing both the transnational dimensions and internal divisions of the anti-nuclear movement, this thesis revises the homogenising concepts of social movements that are prevalent in much of the existing sociological and political science literature. At the same time, it situates the anti-nuclear movement historically within the decade of upheaval that was the 1970s, while moving individual activists from the margins to the centre of protest history.

This paper studies the nuclear technology and evaluates the most likely technical developments to come until 2030. It examines the features of Czech and French nuclear programs, compares the structures of nuclear sectors and estimates the advantages & drawbacks of further developments in both countries. The paper assesses if certain developments of the nuclear sector in one country can be used in the other country and vice-versa. Finally, proposes a set of recommendations for both countries regarding the development of their nuclear program.