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This study examines an important aspect of energy history and policy: the intertwinement of energy technologies with ideals. Ideals play an important role in energy visions and innovation pathways. Aspirations to realize technical, social, and political ideals indicate a long-term commitment in the design of energy systems, distinguishable from commitment to other abstract goals, such as values. This study offers an analytical scheme that could help to conceptualize these differences and their impact on energy policy. In the proposed model, two spheres of interaction are highlighted: a material sphere in which values and technologies co-evolve, and an imaginary sphere in which ideals interact with idealized technologies. Furthermore, the relation between these two spheres can be understood in different ways. This study examines three cases that are illustrative of the different roles of ideals in the development of energy technologies and visions: (1) the evolution of safety in nuclear reactor design; (2) visions of atomic power in France; (3) the political idealization of a tidal power scheme in the Severn Estuary. Finally, the developed model implies more general insights for the development of sociotechnical systems. Amongst others, it shows why certain projects and technologies remain a political, but not a techno–economic option. [ABSTRACT FROM AUTHOR]

The closing of the aging nuclear power plant of Fessenheim was eventually concretized in June 2020 after many years of controversy, reflecting the sensibility of closing nuclear power plants in France, the world's second largest producer of nuclear power. This paper provides insight into how this highly policy vexed issue was discussed on the local level during 2017, a period when the decision regarding the shutdown was still at stake. Here, I examine the discursive strategies mobilized by key actors lobbying for the shutdown or maintenance of the nuclear power plant to enhance their argumentations. Using political discourse analyses combined with the logics approach, the article shows that the argumentation of proponents and advocates of a shutdown is structured around the same concept of sustainability. However, economic growth, social prosperity, and environmental "cautiousness" are not articulated with the same chain of equivalence and do not activate the same fantasmatic logics. [ABSTRACT FROM AUTHOR]

The massive penetration of renewable energy sources (RES) that are variable and not "dispatchable", may weaken the power system supply-demand balance. Nuclear power plants (NPP) contribute in part to this daily and seasonal balance thanks to the "load-following" mode in France for example, but there are still limits to their use. These limits prevent a nuclear power modulation as efficient and quickly as the conventional thermal power plants. The need in terms of power ramps for nuclear in a constrained power system has been quantified in previous studies. Nuclear may compensate for the removal of thermal power plants, in order to fulfill energetic strategies of CO2 reduction. The possibility that nuclear reactors can achieve power ramps of significant values (>5%Pn/min) is put forward and could make possible to replace the services currently provided by thermal power plants. The objective of the study is then to use these power system requirements as the main input parameter for the modelling of a current simplified nuclear reactor capable of responding to frequency control within a specific hypothesis framework. In this paper, a French 1300 MW pressurized water reactor is modelled. Parametric studies are carried out in order to reveal technical and technological constraints when increasing electric power ramp. The study explores ways of design, which may influence reactor flexibility, such as the neutron parameter, Doppler coefficient, or the thermohydraulic parameter, delay in the primary loop. [ABSTRACT FROM AUTHOR]

Nuclear fission energy is a carbon-free source of electricity which makes particularly economical use of matter and space, and which has made France the “good student” in the fight against greenhouse gases. It is widely deployed in our country, which is an asset when we seriously ask ourselves the question of the trajectory to be constructed and not simply that of the objective to be achieved. As such, it fully has its place in the energy strategies to be implemented in the face of global warming. But the analysis of its strengths and weaknesses requires an approach integrating the issue of uranium resources, the issue of safety and that of aging of equipment, the problems associated with the dismantling of plants at the end of their life, and finally management. of the waste produced by this energy source. None of these aspects can be tackled in isolation from the others, none of these issues can be addressed without thinking about the timescales involved. Finally, the question of the coexistence of nuclear energy and other sources of electricity requires reflection on the nature of the networks, storage capacities and the flexibility of the energy mix. The question of the cost of nuclear power can be addressed within the framework of this global approach only. [ABSTRACT FROM AUTHOR]

In 2010, there were more nuclear power units under construction worldwide than in any year since 1988. Even before Fukushima, however, status indicators for the international nuclear industry were showing a negative trend. Fewer countries are operating nuclear fission reactors for energy purposes than in previous years, and many countries are now past their nuclear peak. Worldwide nuclear production is generally declining, and many new projects are experiencing construction delays. Even if reactors can be operated for an average of 40 years, 74 new plants would have to come on line by 2015 to maintain the status quo, which is impossible given current constraints on fabricating reactor components. Developments in Asia, particularly in China, do not fundamentally change the global picture. The dramatic post-Fukushima decisions in two of the four largest economies, Japan and Germany, and in several other nuclear countries could accelerate the decline of a rapidly aging industry. [ABSTRACT FROM AUTHOR]

Coherent elastic neutrino–nucleus scattering ( CE ν NS ) offers a unique way to study neutrino properties and to search for new physics beyond the Standard Model. Nuclear reactors are promising sources to explore this process at low energies since they deliver large fluxes of anti-neutrinos with typical energies of a few MeV. In this paper, a new-generation experiment to study CE ν NS is described. The NUCLEUS experiment will use cryogenic detectors which feature an unprecedentedly low-energy threshold and a time response fast enough to be operated under above-ground conditions. Both sensitivity to low-energy nuclear recoils and a high event rate tolerance are stringent requirements to measuring CE ν NS of reactor anti-neutrinos. A new experimental site, the Very-Near-Site (VNS), at the Chooz nuclear power plant in France is described. The VNS is located between the two 4.25 GW th reactor cores and matches the requirements of NUCLEUS. First results of on-site measurements of neutron and muon backgrounds, the expected dominant background contributions, are given. In this paper a preliminary experimental set-up with dedicated active and passive background reduction techniques and first background estimations are presented. Furthermore, the feasibility to operate the detectors in coincidence with an active muon veto at shallow overburden is studied. The paper concludes with a sensitivity study pointing out the physics potential of NUCLEUS at the Chooz nuclear power plant. [ABSTRACT FROM AUTHOR]

The article presents several statements that were read at various conferences held within the French Atomic Energy Commission toward the end of 1949. Professor F. Joliot-Curie discussed the Commissariat's efforts on completing and putting into operation the first French atomic pile of uranium oxide and heavy water. Dr. L. Kowarski elaborated on the purpose of the operation of the first pile. Dr. J. Gueron centered on the function of the General Chemistry division in analyzing and controlling of substances to be integrated in the pile. Dr. B. Goldschmidt explained the responsibility of Applied Chemistry division in the production of uranium compounds, oxide and metal.

The article presents a speech by L. Kowarski, Scientific Director of the French Atomic Energy Commission, delivered at the Brookhaven National Laboratory, February 6, 1948. He discusses the developments of atomic energy in France including the construction of nuclear reactor and cyclotron, and the development of physical testing methods and chemical research programs for preparation of graphite and uranium. Atomic energy developments in other European countries are also presented.

The present paper proposes an analysis concerning the impact of the reduction of the net electricity flow between France and Italy due to the phase out of French nuclear power plants. The analysis is performed by using a bid stack model which offers an approximate, but reliable representation of the Italian power system, as shown by extensive validation on historical data. The study takes into account sixteen scenarios given by the combination of different assumptions on the operating life of French nuclear reactors, fuel price, renewables development and demand level. Furthermore, a Business As Usual scenario is implemented as reference case. The results have shown that some scenarios determine tight conditions for the Italian power market and provoke an increase of the clean spark of 13 €/MWh with respect to the Business As Usual scenario. At the same time, an increase of the load factor of gas turbines from 0.5% to 4% is also detected. This situation requires substantial interventions in order to re-balance the system. On the contrary, scenarios which imply a more aggressive development of renewables and low increase of the demand, even in the case of a relevant phase out of nuclear capacity in France, do not determine tight conditions on the Italian power market, therefore it is not necessary to adopt particular measures. [ABSTRACT FROM AUTHOR]

The article presents the author's opinion on the Franco-Iraqi project, according to which France has supplied two nuclear reactors to Iraq. Both Iraq and France have claimed the reactors to be research reactors. However, the larger of the two is capable of producing enough plutonium for several bombs every year. According to the author, Iraq's acquisition of this reactor, poses a threat of nuclear terrorism, which is the result of an irresponsible action on the part of the French government.

The article focuses on the British fast breeder program and discusses the government's attitude towards the breeder program and the international part that the program has been playing. The Thatcher government was enthusiastic towards the program. However, problems abound regarding the development of the commercial demonstration fast reactor. International discussions among breeder enthusiasts have been taking place in full swing. The United Kingdom, France and the Federal Republic of Germany have been investigating ways to intensify their cooperation on exchange of technical information about fast reactors and their fuel cycle.

In this article, the author discussed Advanced Sodium Technological Reactor for Industrial (ASTRID) programme of France as the keystone for sustainable nuclear energy. He states that French nuclear fuel cycle strategy is mainly driven by the fact that nuclear energy is to be maintained as a stable pillar of the French energy. Information on the role of nuclear power in sustainable development plan presupposes the development of a new generation of reactors is also offered.

Abstract: Radioactive fallout due to the Fukushima reactor explosion in Japan was detected in environmental samples collected in France. The presence of 131I in aerosols (200±6μBqm−3) collected at the Pic du Midi observatory, located at 2877m altitude in the French Pyrénées, indicated that the Japanese radioactive cloud reached France between 22 and 29 March, i.e. less than two weeks after the initial emissions, as suggested by a 137Cs/134Cs ratio of 1.4. Cesium radioisotopes (134Cs and 137Cs) were not detected in this sample but they were present in the aerosol sample collected the next week, i.e. between 29 March and 05 April (about 10μBqm−3). We also report 131I activities measured in grass (1.1–11Bqkg−1; fresh weight) and soil samples (0.4Bqkg−1) collected in the Seine River basin between 30 March and 10 April. The 134Cs from the damaged Fukushima power plant was also detected in grass collected in the Seine River basin between 31 March and 10 April (0.2–1.6Bqkg−1 fresh weight, with a 137Cs/134Cs ratio close to 1, which is consistent with Fukushima radioactive release). Despite the installation of a network of nested stations to collect suspended matter in the upstream part of the Seine River basin, 131I was only detected in suspended matter (4.5–60Bqkg−1) collected at the most upstream stations between 30 March and 12 April. Neither 131I nor 134Cs has been detected in environmental samples since the end of April 2011, because of the rapid decay of 131I and the very low activities of 134Cs (about 400 times lower than after Chernobyl accident). [Copyright &y& Elsevier]

Abstract: Although MOX fuel coming from reprocessed depleted uranium fuels has been used as a recycling strategy by countries like France and Japan it is not a common policy in the 30 countries that uses nuclear power, nowadays it seems to be a more direct alternative to reduce the depleted fuel interim storage. Previously, the spent fuel pools of Laguna Verde Nuclear Power plant were redesigned to host the total operating life depleted fuel under its original nominal power condition, however the plant has been up-rated to 120% of its original nominal power increasing the number of depleted fuel forecasted. This new situation makes necessary the analysis of alternatives, being one of them recycling. The current paper assesses the viability of using MOX fuel in the up-rated Power Plant; the design of the boiling water reactor MOX fuel addresses the two main constraints of its use: shutdown margin and reactor stability. Fuel design proposed sets the appropriate MOX enrichment and the maximum MOX fuel batch reload that does not imply any modification to the reactor control systems to avoid an extra economical cost due to its use. [Copyright &y& Elsevier]

This paper presents the capabilities of the International Database on Reactor Pressure Vessel (RPV) Materials (the Database) for precise and comprehensive RPV lifetime assessment, aimed at supporting the long-term operation of nuclear power plants. The Database was created in the framework of the International Atomic Energy Agency activities. Fourteen countries, including the United States, France, and Russia, supplied large amounts of surveillance results and data from national and international research programs. The recent achievements and open issues in the area of RPV radiation embrittlement assessment are considered. They concern mainly the effects resulting from long irradiation times and high neutron fluences (neutron flux influence, late blooming phases), nickel and manganese synergism, and further validation of appropriate safety concepts (the Master Curve approach). New information from ongoing surveillance and research programs has to be incorporated into the Database for the most effective RPV radiation embrittlement prediction. These additional data will greatly support the development of embrittlement correlations and embrittlement trend curves valid for long irradiation times. [ABSTRACT FROM AUTHOR]

Abstract: Nuclear waste management has to be taken into account for fusion machine in tritium experimentations. Soft housekeeping waste is produced during both operating and dismantling phases and is contaminated by tritium under reduced (HT) and oxidized (HTO) forms. At CEA Cadarache, a lab-scaled facility has been built for soft housekeeping detritiation. The tritiated gas exhausted from the process described above is foreseen to be treated by a tubular Pd–Ag membrane reactor, for gaseous tritium recovery. Since this membrane reactor uses hydrogen as swamping gas the compatibility toward explosive hazard has to be taken into account. Then, this work presents a double objective. A first study is presented in order to identify the best conditions for the declassification of soft housekeeping waste, without tritium recovery. Experiments carried out at 120°C are not efficient enough and do not allow one to choose the most efficient carrier gas. Some other tests are being currently performed at higher temperatures (150°C). Moreover, due to safety issues, the use of air has to be avoided during membrane reactor implementation phase. Preliminary results obtained with hydrogen hazard-free carrier gases are also presented. [Copyright &y& Elsevier]

Abstract: In France, the ASTRID prototype is a sodium-cooled fast neutron industrial demonstrator, fulfilling the criteria for Generation IV reactors. ASTRID will meet safety requirements as stringent as for 3rd generation reactors, and take into account lessons from the Fukushima accident. The objectives are to reinforce the robustness of the safety demonstration for all safety functions. ASTRID will feature an innovative core with a negative sodium void coefficient, take advantage of the large thermal inertia of SFRs for decay heat removal, and provide for a design either eliminating the sodium–water reaction, or guaranteeing no consequences for safety in case such reaction would take place. [Copyright &y& Elsevier]

High temperature fission chambers are key instruments for the control and protection of the sodium-cooled fast reactor. First, the developments of those neutron detectors, which are carried out either in France or abroad are reviewed. Second, the French realizations are assessed with the use of the technology readiness levels in order to identify tracks of improvement. [ABSTRACT FROM AUTHOR]

The Double Chooz experiment presents an indication of reactor electron antineutrino disappearance consistent with neutrino oscillations. An observed-to-predicted ratio of events of 0.944 ± 0.016(stat) ± 0.040(syst) was obtained in 101 days of running at the Chooz nuclear power plant in France, with two 4.25 GWth reactors. The results were obtained from a single 10 m3 fiducial volume detector located 1050 m from the two reactor cores. The reactor antineutrino flux prediction used the Bugey4 flux measurement after correction for differences in core composition. The deficit can be interpreted as an indication of a nonzero value of the still unmeasured neutrino mixing parameter sin22&thgr;13. Analyzing both the rate of the prompt positrons and their energy spectrum, we find sin22&thgr;13 = 0.086 ± 0.041(stat) ± 0.030(syst), or, at 90% C.L., 0.017 < sin22&thgr;13 < 0.16. [ABSTRACT FROM AUTHOR]

In this article, the author discusses several developments in the energy industry and challenges associated with the working of nuclear fusion reactors. It is mentioned that, generation of high temperature during the nuclear fusion reaction has been the main challenge of energy industry. It also includes information on experimental fusion apparatus ITER, to be built in partnership by several countries including France, Japan, South Korea.

Abstract: A measurement of the ratio of the inclusive 3-jet to 2-jet cross sections as a function of the total jet transverse momentum, , in the range is presented. The data have been collected at a proton–proton centre-of-mass energy of 7 TeV with the CMS detector at the LHC, and correspond to an integrated luminosity of 36 pb−1. Comparisons are made between the data and the predictions of different QCD-based Monte Carlo models for multijet production. All models considered in this study are consistent with the data for . This measurement extends to an range that has not been explored before. [Copyright &y& Elsevier]

The article reports that France is now pressing forward with Gen-III nuclear reactors while planning for Gen- IV because of the lessons taken from the tsunami-struck Fukushima I nuclear plant accident in Japan, and the Chernobyl disaster in Ukraine. As reported, France chose early in the development of its nuclear program in the 1970s to focus on water-cooled pressurized water reactors (PWRs), which have been proved highly effective.

The article discusses the Fast Breeder Reactor (FBR) Program in France. Several pressurized water reactors (PWRs) were built in France as the main source for its electricity production during the 1970s. FBR development programs started in various European countries such as France, Great Britain and the Federal Republic of Germany from 1950 to 1955. According to the article, international cooperation which was developed for the basic research and development (R&D) need to be amplified to cover technology improvements and prototype demonstrations.

This article explores the history of the International Thermonuclear Experimental Reactor (ITER), a fusion energy megaproject currently being built in southern France. It examines three main aspects of the project's history, focusing largely on the European research community's perspective. First, it explores how European scientists and science managers constructed a transnational research community around fusion energy after 1960 that was part of Europe's larger technological integration. This article also expands Gabrielle Hecht's concept of 'technopolitics' to the larger international dimension and explores how the political environment of the late Cold War and the post-9/11 era helped shape ITER's history, sometimes in ways not entirely within researchers' control. Finally, this essay considers ITER as a technological project that gradually became globalized. At various stages in the project's 30-year history, we discover processes whereby national borders became less important while social, economic, legal and technological linkages created a shared social space for fusion research on an expanding scale. [ABSTRACT FROM AUTHOR]

Abstract: Severe accident analysis of a reactor is an important aspect for evaluation of source term. This in turn helps in emergency planning and severe accident management (SAM). Analyses have been carried out for VVER-1000 (V320) reactor following LOCA along with station blackout (SBO) to generate information on these aspects. Availability and unavailability of hydro-accumulators (HAs) are also considered for this study. Integral code ASTEC V1.3 (jointly developed by IRSN, France, and GRS, Germany) is used for analysing the transients. The predictions of different severe accident parameters like vessel rupture time, hydrogen and corium production and radioactivity release to containment have been compared for a spectrum of break sizes to provide information for probabilistic safety analysis (PSA) level-2 and severe accident management (SAM) guidelines. [Copyright &y& Elsevier]

Abstract: The planned luminosity upgrade of the large hadron collider at CERN (Super-LHC) will provide a challenging environment for the tracking and vertexing detector systems. The innermost devices at a radius about 4cm from the interaction region will have to be able to withstand a combined charged and neutron hadron dose in the order of neutron equivalent particles () per square centimeter over the anticipated 5 year lifespan of the SLHC experiments. Planar, segmented silicon detectors with n-strip readout are one of the many radiation tolerant technologies under consideration for use for the Super-LHC tracking detectors in either pixel or strip geometries. This paper details charge collection efficiency measurements made with silicon sensors that have been irradiated to doses as high as with reactor neutrons and as high as with 26MeV protons and 24GeV protons. In this study, segmented strip readout in either n-bulk (n-in-n) or p-bulk (n-in-p) substrates are considered. Both diode configurations were processed in substrates grown with float zone (FZ) and magnetic Czochralski (MCz) techniques. For the fluences studied, all the strip readout technologies are still viable assuming that adequate bias voltage and cooling can be supplied and low noise, low threshold readout electronics can be designed. [Copyright &y& Elsevier]

Abstract: The upcoming high energy experiments at the LHC are one of the most outstanding efforts for a better understanding of nature. It is associated with great hopes in the physics community. But there is also some fear in the public, that the conjectured production of mini black holes might lead to a dangerous chain reaction. In this Letter we summarize the most straightforward arguments that are necessary to rule out such doomsday scenarios. [Copyright &y& Elsevier]

France is the only country in the world ever to operate a commercial scale (1,200 MWe) sodium cooled, plutonium fuelled fast breeder reactor, the Superphenix at Creys-Malville. However, the French fast breeder reactor program turned out to be too costly and could never compete with light water reactor technology. Numerous technical problems, low uranium prices and massive opposition exacerbated the poor economic and operational performance of the fast breeder reactor. Superphenix only operated about half of the time that it was officially connected to the grid and was shut down in 1998 with a lifetime load factor of less than 7%. The Superphenix predecessor, Phenix at Marcoule, which began operating in 1973 and will be shut down later in 2009, has experienced numerous sodium leaks and fires and a series of potentially serious reactivity incidents. The lifetime load factor of approximately 45% is one of the lowest in the world. [ABSTRACT FROM AUTHOR]

Abstract: The ITER Nuclear Buildings include the Tokamak, Tritium and Diagnostic Buildings (Tokamak Complex) and the Hot Cell and Low Level Radioactive Waste Buildings (Hot Cell Complex). The Tritium Confinement strategy of the Nuclear Buildings comprises key features of the atmosphere and vent detritiation systems and the heating, ventilation and air conditioning systems. The designs developed during the ITER EDA (engineering design activities) for these systems need to be adapted to the specific conditions of the Cadarache site and modified to conform with the regulatory requirements applicable to installations nucléaires de base (INB) – basic nuclear installations – in France. The highest priority for such adaptation has been identified as the Tritium Confinement of the Tokamak Complex and the progress in development of a robust, coherent design concept compliant with French practice is described in the paper. [Copyright &y& Elsevier]

As a follow-up of the work presented at the ND-2007 conference in Nice, additional fast reactor benchmarks were analyzed. Adjustment to the cross sections in the keV region was necessary. Evaluated neutron cross section data files for 180,182,183,184,186W isotopes were produced. Covariances were generated for all isotopes except 180W. In the resonance range the retro-active method was used. Above the resolved resonance range the covariance prior was generated by the Monte Carlo technique from nuclear model calculations with the Empire-II code. Experimental data were taken into account through the GANDR system using the generalized least-squares technique. Introducing experimental data results in relatively small changes in the cross sections, but greatly constrains the uncertainties. The covariance files are currently undergoing testing. [Copyright &y& Elsevier]

The article provides an analysis on the subcooled flow boiling regime of a pressurized water reactor at critical heat flux (CHF) conditions conducted at the Arizona State University (ASU) and DEBORA facility in Grenoble, France. It reveals that the Neptune_CFD computer code was utilized to assess flow boiling process in the near-wall region. It was found that the code was effective in predicting wall temperature increase and sharp void fraction in CHF conditions.

The article presents information on the International Thermonuclear Experimental Reactor (ITER), a fusion power station to be constructed in Cadarache, France. ITER project plans to produce 500 megawatts of power. Scientists believe that energy can be created through the process of fusion and could be formed from the sun's energy. However, there are certain limitations. The construction of ITER through fusion science is regarded as a wastage of money by some plasma scientists. It would be costing around $12 billion. INSET: How to Squeeze a Plasma.