Bibliographies thématiques / Partitioning, Transmutation, Nuclear Technology, Nuclear Reactors / Articles de revues
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Articles de revues sur le sujet « Partitioning, Transmutation, Nuclear Technology, Nuclear Reactors »

Auteur : Grafiati
Publié le 4 juin 2021
Mis à jour le 16 février 2022

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1

Ruskov, Ivan, Andrei Goverdovski, Walter Furman, Yury Kopatch, Oleg Shcherbakov, Franz-Josef Hambsch, Stephan Oberstedt et Andreas Oberstedt. « Neutron induced fission of 237Np – status, challenges and opportunities ». EPJ Web of Conferences 169 (2018) : 00021. http://dx.doi.org/10.1051/epjconf/201816900021.

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Nowadays, there is an increased interest in a complete study of the neutron-induced fission of 237Np. This is due to the need of accurate and reliable nuclear data for nuclear science and technology. 237Np is generated (and accumulated) in the nuclear reactor core during reactor operation. As one of the most abundant long-lived isotopes in spent fuel (“waste”), the incineration of 237Np becomes an important issue. One scenario for burning of 237Np and other radio-toxic minor actinides suggests they are to be mixed into the fuel of future fast-neutron reactors, employing the so-called transmutation and partitioning technology. For testing present fission models, which are at the basis of new generation nuclear reactor developments, highly accurate and detailed neutron-induced nuclear reaction data is needed. However, the EXFOR nuclear database for 237Np on neutron-induced capture cross-section, σγ, and fission cross-section, σf, as well as on the characteristics of capture and fission resonance parameters (Γγ, Γf, σoΓf, fragments mass-energy yield distributions, multiplicities of neutrons vn and γ-rays vγ), has not been updated for decades.
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KITAMOTO, Asashi, et MULYANTO. « Grouping in Partitioning of HLW for Burning and/or Transmutation, with Nuclear Reactors ». Journal of Nuclear Science and Technology 32, no 6 (juin 1995) : 565–76. http://dx.doi.org/10.1080/18811248.1995.9731744.

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Shlenskii, Mikhail, et Boris Kuteev. « System Studies on the Fusion-Fission Hybrid Systems and Its Fuel Cycle ». Applied Sciences 10, no 23 (26 novembre 2020) : 8417. http://dx.doi.org/10.3390/app10238417.

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This paper is devoted to applications of fusion-fission hybrid systems (FFHS) as a powerful neutron source implementing transmutation of minor actinides (MA: Np, Am, Cm) extracted from the spent nuclear fuel (SNF) of nuclear reactors. Calculations which simulated nuclide kinetics for the metallic fuel containing MA and neutron transport were performed for particular facilities. Three FFHS with fusion power equal to 40 MW are considered in this study: demo, pilot-industrial and industrial reactors. In addition, needs for a fleet of such reactors are assessed as well as future FFHSs’ impact on Russian Nuclear Power System. A system analysis of nuclear energy development in Russia was also performed with the participation of the FFHSs, with the help of the model created at AO “Proryv”. The quantity of MA that would be produced and transmuted in this scenario is estimated. This research shows that by the means of only one hybrid facility it is possible to reduce by 2130 the mass of MA in the Russian power system by about 28%. In the case of the absence of partitioning and transmutation of MA from SNF, 287 t of MA will accumulate in the Russian power system by 2130.
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Inoue, Tadashi, Masahiro Sakata, Hajime Miyashiro, Tetsuo Matsumura, Akihiro Sasahara et Nobuya Yoshiki. « Development of Partitioning and Transmutation Technology for Long-Lived Nuclides ». Nuclear Technology 93, no 2 (février 1991) : 206–20. http://dx.doi.org/10.13182/nt91-a34506.

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Bourg, Stéphane, Andreas Geist, Jean-Marc Adnet, Chris Rhodes et Bruce C. Hanson. « Partitioning and transmutation strategy R&D for nuclear spent fuel : the SACSESS and GENIORS projects ». EPJ Nuclear Sciences & ; Technologies 6 (2020) : 35. http://dx.doi.org/10.1051/epjn/2019009.

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Processes such as PUREX allow the recovery and reuse of the uranium and the plutonium of GEN II/GEN III reactors and are being adapted for the recycling of the uranium and the plutonium of GEN IV MOX fuels. However, it does not fix the sensitive issue of the long-term management of the high active nuclear waste (HAW). Indeed, only the recovery and the transmutation of the minor actinides can reduce this burden down to a few hundreds of years. In this context, and in the continuity of the FP7 EURATOM SACSESS project, GENIORS focuses on the reprocessing of MOX fuel containing minor actinides, taking into account safety issues under normal and mal-operation. By implementing a three-step approach (reinforcement of the scientific knowledge => process development and testing => system studies, safety and integration), GENIORS will provide more science-based strategies for nuclear fuel management in the EU.
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Varlachev, Valery A., Evgeny G. Emets et Yana A. Butko. « Technology for Silicon NTD Using Pool-Type Research Reactors ». Advanced Materials Research 1084 (janvier 2015) : 333–37. http://dx.doi.org/10.4028/www.scientific.net/amr.1084.333.

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Neutron transmutation doped silicon is an important material for electronics that is based on the conversion of30Si into31P through a30Si (n,γ) →31Si reaction taking place during the neutron irradiation and followed by the beta decay of31Si into31P. The production of such silicon requires high homogeneity. The paper describes a new facility for NTD of silicon ingots of up to 5 inches in diameter and presents the experimental results that were obtained at IRT-T research nuclear reactor.
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Bergelson, B. R., A. S. Gerasimov et G. V. Tikhomirov. « Transmutation of actinides in power reactors ». Radiation Protection Dosimetry 116, no 1-4 (20 décembre 2005) : 675–78. http://dx.doi.org/10.1093/rpd/nci249.

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Maltseva, T., А. Shyshuta et S. Lukashyn. « Modern Methods of Radiochemical Reprocessing of Spent Nuclear Fuel ». Nuclear and Radiation Safety, no 1(81) (12 mars 2019) : 52–57. http://dx.doi.org/10.32918/nrs.2019.1(81).09.

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The paper is devoted to the history of development and the current state of technological and scientific advances in radiochemical reprocessing of spent nuclear fuel from water-cooled power reactors. Regarding spent nuclear fuel (SNF) of NPP power reactors, long-term energy security involves adopting a version of its radiochemical treatment, conditioning and recirculation. Recycling SNF is required for the implementation of a closed fuel cycle and the re-use of regeneration products as energy reactor fuels. The basis of modern technological schemes for the reprocessing of the spent nuclear fuel is the “Purex” process, developed since the 60s in the USA. The classic approach to the use of U and Pu nuclides contained in spent nuclear fuel is to separate them from fission products, re-enrich regenerated uranium and use plutonium for the production of mixed-oxide (MOX) fuel with depleted uranium. The modern reprocessing plants are able to deal with fuel with further increase of its main characteristics without significant changes in the initial project. In order to close the fuel cycle, it is needed to add the following technological steps: (1) removal of high-level and long-lived components and minor actinides; (2) return of actinides to the technological cycle; (3) safe disposal of unused components. Each of these areas is under investigation now. Several new promising multi-cycle hydrometallurgical processes based on the joint extraction of trivalent lanthanides and minor actinides with their subsequent separation have been developed. A number of promising materials is suggested to be potential matrices for the immobilization of high-level components of radioactive wastes. To improve the compatibility of fuel processing with the environment, non-aqueous technologies are being developed, for instance, pyro-chemical methods for the reprocessing of various types of highly active fuels based on metals, oxides, carbides, or nitrides. An important scientific and technological task under investigation is transmutation of actinides. The results of international large-scale experiments on the partitioning and transmutation of fuel with various minor actinides and long-lived fission products confirm the real possibility and expediency of closing the nuclear fuel cycle.
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François, J. L., J. J. Dorantes, C. Martín-del-Campo et J. J. E. Herrera. « LWR spent fuel transmutation with fusion-fission hybrid reactors ». Progress in Nuclear Energy 65 (mai 2013) : 50–55. http://dx.doi.org/10.1016/j.pnucene.2013.02.005.

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Takeda, Toshikazu, Toshihisa Yamamoto et Maiko Miyauchi. « Interpretation of actinide transmutation in thermal and fast reactors ». Progress in Nuclear Energy 40, no 3-4 (avril 2002) : 449–56. http://dx.doi.org/10.1016/s0149-1970(02)00037-9.

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Aoki, Sanae. « Research and development in Japan on long-lived nuclide partitioning and transmutation technology ». Progress in Nuclear Energy 40, no 3-4 (avril 2002) : 343–48. http://dx.doi.org/10.1016/s0149-1970(02)00027-6.

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Ikeda, Kazumi, Shin-ichi Koyama, Masaki Kurata, Yasuji Morita, Kazufumi Tsujimoto et Kazuo Minato. « Technology readiness assessment of partitioning and transmutation in Japan and issues toward closed fuel cycle ». Progress in Nuclear Energy 74 (juillet 2014) : 242–63. http://dx.doi.org/10.1016/j.pnucene.2013.12.009.

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KITAMOTO, Asashi. « New Linkage of P&T(Partitioning and Transmutation) Treatment with Methodology of Geologic Disposal. A Possible Breakthrough for Nuclear Technology in Tomorrow. » Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 41, no 3 (1999) : 219–35. http://dx.doi.org/10.3327/jaesj.41.219.

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UMEZAWA, Hirokazu. « Outline of OMEGA Project. Research and development on partitioning and transmutation of actinoids and fission-products searching for new possibilities of nuclear technology. » Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 31, no 12 (1989) : 1317–23. http://dx.doi.org/10.3327/jaesj.31.1317.

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Jeong, Chang Joon, et Won Il Ko. « Scenario analysis for a transuranic transmutation by using fast reactors compared to accelerator driven systems ». Energy Conversion and Management 49, no 7 (juillet 2008) : 1917–21. http://dx.doi.org/10.1016/j.enconman.2007.12.014.

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Egorov, Alexander V., Yurii S. Khomyakov, Valerii I. Rachkov, Elena A. Rodina et Igor R. Suslov. « Minor actinides transmutation in equilibrium cores of next generation FRs ». Nuclear Energy and Technology 5, no 4 (10 décembre 2019) : 353–59. http://dx.doi.org/10.3897/nucet.5.46517.

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The Russian Federation is developing a number of technologies within the «Proryv» project for closing the nuclear fuel cycle utilizing mixed (U-Pu-MA) nitride fuel. Key objectives of the project include improving fast reactor nuclear safety by minimizing reactivity changes during fuel operating period and improving radiological and environmental fuel cycle safety through Pu multi-recycling and МА transmutation. This advanced technology is expected to allow operating the reactor in an equilibrium cycle with a breeding ratio equaling approximately 1 with stable reactivity and fuel isotopic composition. Nevertheless, to reach this state the reactor must still operate in an initial transient state for a lengthy period (over 10 years) of time, which requires implementing special measures concerning reactivity control. The results obtained from calculations show the possibility of achieving a synergetic effect from combining two objectives. Using МА reprocessed from thermal reactor spent fuel in initial fuel loads in FR ensures a minimal reactivity margin during the entire fast reactor fuel operating period, comparable to the levels achieved in equilibrium state with any kind of relevant Pu isotopic composition. This should be combined with using reactivity compensators in the first fuel micro-campaigns. In the paper presented are the results of simulation of the overall life cycle of a 1200 MWe fast reactor, reaching equilibrium fuel composition, and respective changes in spent fuel nuclide and isotopic composition. It is shown that МА from thermal and fast reactors spent fuel can be completely utilized in the new generation FRs without using special actinide burners.
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Stanisz, Przemysław, Jerzy Cetnar et Grażyna Domańska. « Modeling minor actinide multiple recycling in a lead-cooled fast reactor to demonstrate a fuel cycle without long-lived nuclear waste ». Nukleonika 60, no 3 (1 septembre 2015) : 581–90. http://dx.doi.org/10.1515/nuka-2015-0111.

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Abstract The concept of closed nuclear fuel cycle seems to be the most promising options for the efficient usage of the nuclear energy resources. However, it can be implemented only in fast breeder reactors of the IVth generation, which are characterized by the fast neutron spectrum. The lead-cooled fast reactor (LFR) was defined and studied on the level of technical design in order to demonstrate its performance and reliability within the European collaboration on ELSY (European Lead-cooled System) and LEADER (Lead-cooled European Advanced Demonstration Reactor) projects. It has been demonstrated that LFR meets the requirements of the closed nuclear fuel cycle, where plutonium and minor actinides (MA) are recycled for reuse, thereby producing no MA waste. In this study, the most promising option was realized when entire Pu + MA material is fully recycled to produce a new batch of fuel without partitioning. This is the concept of a fuel cycle which asymptotically tends to the adiabatic equilibrium, where the concentrations of plutonium and MA at the beginning of the cycle are restored in the subsequent cycle in the combined process of fuel transmutation and cooling, removal of fission products (FPs), and admixture of depleted uranium. In this way, generation of nuclear waste containing radioactive plutonium and MA can be eliminated. The paper shows methodology applied to the LFR equilibrium fuel cycle assessment, which was developed for the Monte Carlo continuous energy burnup (MCB) code, equipped with enhanced modules for material processing and fuel handling. The numerical analysis of the reactor core concerns multiple recycling and recovery of long-lived nuclides and their influence on safety parameters. The paper also presents a general concept of the novel IVth generation breeder reactor with equilibrium fuel and its future role in the management of MA.
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Pham Quang, Huy, Dien Nguyen Nhi, Cuong Nguyen Kien, Duong Tran Quoc, Dang Vo Doan Hai, Dat Trang The et Dat Trang The. « Design of an irradiation rig using screen method for silicon transmutation doping at the Dalat research reactor ». Nuclear Science and Technology 9, no 1 (15 mars 2019) : 1–8. http://dx.doi.org/10.53747/jnst.v9i1.54.

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The neutron transmutation doping of silicon (NTD-Si) at research reactors has beensuccessfully implemented in many countries to produce high-quality semiconductors. In the late 1980s, NTD-Si has been tested at the Dalat Nuclear Research Reactor (DNRR) but the results have been limited. Therefore, the design and testing of an irradiation rig for NTD-Si at the DNRR are necessary to have a better understanding in order to apply the NTD-Si in a new research reactor of the Research Centre for Nuclear Science and Technology (RCNEST), which has planned to be built in Viet Nam. This paper presents the design and testing of a new irradiation rig using screen method for testing NTD-Si at the DNRR. The important parameters in the rig such as neutron spectrum and thermal neutron flux distribution were determined by both calculation using MCNP5 computer code and experiment. The aluminum ingots, which have similar neutronic characteristics with silicon ingots, were irradiated in the rig to verify the appropriate design. The uniformity of thermal neutron flux in the rig is less than 5% in axial and 2% in radial directions, respectively. However, the thermal/fast flux ratio of the irradiation rig is 4.38/1 would affect target resistivity of testing Silicon ingots after irradiation.
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Pesic, Milan, Yury Titarenko, Viacheslav Batyaev, Kirill Pavlov, Alexey Titarenko, Valeriy Zhivun, Mikhail Igumnov, Viacheslav Konev et Vladimir Legostaev. « Validation of minor actinides fission neutron cross-sections ». Nuclear Technology and Radiation Protection 30, no 1 (2015) : 1–10. http://dx.doi.org/10.2298/ntrp1501001p.

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Verification of neutron fission cross-sections of minor actinides from some recently available evaluated nuclear data libraries was carried out by comparison of the reaction rates calculated by the MCNP6.1 computer code to the experimental values. The experimental samples, containing thin layers of 235U, 237Np, 238,239,240,241Pu, 242mAm, 243Cm, 245Cm, and 247Cm, deposited on metal support and foils of 235U (pseudo-alloy 27Al + 235U), 238U, natIn, 64Zn, 27Al, and multi-component sample alloy 27Al + 55Mn + natCu + natLu + 197Au, were irradiated in the channels of the tank containing fluorine salts 0.52NaF + 0.48ZrF4, labelled as the Micromodel Salt Blanket, inserted in the lattice centre of the MAKET heavy water critical assembly at the Institute for Theoretical and Experimental Physics, Moscow. This paper is a continuation of earlier initiated scientific-research activities carried out for validation of the evaluated fission cross-sections of actinides that were supposed to be used for the quality examination of the fuel design of the accelerator driven systems or fast reactors, and consequently, determination of transmutation rates of actinides, and therefore, determination of operation parameters of these reactor facilities. These scientific-research activities were carried out within a frame of scientific projects supported by the International Science and Technology Center and the International Atomic Energy Agency co-ordinated research activities, from 1999 to 2010. Obtained results confirm that further research is needed in evaluations in order to establish better neutron cross-section data for the minor actinides and selected nuclides which could be used in the accelerator driven systems or fast reactors.
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Cetnar, Jerzy, Grażyna Domańska, Paweł Gajda et Jerzy Janczyszyn. « Assessment of the control rods shadow effect in the VENUS-F core ». Nukleonika 59, no 4 (1 décembre 2014) : 137–43. http://dx.doi.org/10.2478/nuka-2014-0020.

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Abstract The partitioning and transmutation (P&T) of spent nuclear fuel is an important field of present development of nuclear energy technologies. One of the possible ways to carry out the P&T process is to use the accelerator driven systems (ADS). This technology has been developed within the EURATOM Framework Programmes for several years now. Current research in this field is carried out within the scope of 7th FP project FREYA. Important parts of the project are experiments performed in the GUINEVERE facility devoted to characterising the subcritical core kinetics and development of reactivity monitoring techniques. The present paper considers the effects of control rods use on the core reactivity. In order to carry out the evaluation of the experimental results, it is important to have detailed core characteristics at hand and to take into consideration the differences in the effect of control rods acting separately or together (the so-called shadow effect) on both the reactivity value and the measured neutron flux. Also any core asymmetry should be revealed. This goal was achieved by both MCNP simulations and the experimental results. However, in the case of experimental results, the need for calculating respective correction factors was unavoidable.
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Ohe, Toshiaki. « Simple assignment of partitioning & ; transmutation objectives to reduce the overall repository impacts due to thermal load and nuclide migration ». Progress in Nuclear Energy 40, no 3-4 (avril 2002) : 423–30. http://dx.doi.org/10.1016/s0149-1970(02)00034-3.

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Warin, Dominique. « Status of the French Research on Partitioning and Transmutation ». MRS Proceedings 985 (2006). http://dx.doi.org/10.1557/proc-985-0985-nn14-01.

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AbstractThe global energy context pleads in favour of a sustainable development of nuclear energy since the demand for energy will likely increase, whereas resources will tend to get scarcer and the prospect of global warming will drive down the consumption of fossil fuel sources.How we deal with radioactive waste is crucial in this context. The production of nuclear energy in France has been associated, since its inception, with the optimization of radioactive waste management, including the partitioning and the recycling of recoverable energetic materials. The public's concern regarding the long-term waste management made the French Government to prepare and pass the December 1991 Law, requesting in particular the study for fifteen years of solutions for still minimizing the quantity and the hazardousness of final waste, via partitioning and transmutation.At the end of these fifteen years of research, it is considered that partitioning techniques which have been validated on real solutions are at disposal. Indeed, aqueous process for separation of minor actinides from the PUREX raffinate has been brought to a point where there is reasonable assurance that industrial deployment can be successful. A key experiment has been the kilogram scale successful trials in the CEA-Marcoule Atalante facility in 2005 and this result, together with the results obtained in the frame of the successive European projects, constitutes a considerable step forward. For transmutation, CEA has conducted programmes proving the feasibility of the elimination of minor actinides and fission products: fabrication of specific targets and fuels for transmutation tests in the HFR and Phénix reactors, neutronics and technology studies for critical reactors and ADS developments. Scenario studies have also allowed assessing the feasibility, at the level of cycle and fuel facilities, and the efficiency of transmutation in terms of the quantitative reduction of the final waste inventory depending of the reactor fleet (PWR-FR-ADS).Important results are now available concerning the possibility of significantly reducing the quantity and the radiotoxicity of long-lived waste in association with a sustainable development of nuclear energy. As France has confirmed its long-term approach to nuclear energy, the most effective implementation of P and T of minor actinides relies on the fast neutron GEN IV systems which are designed to recycle and manage their own actinides. The perspective to deploy a first series of such systems around 2040 supports the idea that progress is being made: the long-term waste would only be made up of fission products, with very low amounts of minor actinides.In this sense, the new waste management Law passed by the French Parliament on June 28, 2006, demands that P and T research continues in strong connection to GEN IV systems and ADS development and allowing to assess the industrial perspectives of such systems in 2012 and to put into operation a transmutation demo facility in 2020.
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« Maturity of Partitioning and Transmutation Technology ». Journal of the Atomic Energy Society of Japan 52, no 12 (2010) : 796–800. http://dx.doi.org/10.3327/jaesjb.52.12_796.

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« Status and Perspectives of Partitioning and Transmutation Technology ». Journal of the Atomic Energy Society of Japan 50, no 3 (2008) : 158–63. http://dx.doi.org/10.3327/jaesjb.50.3_158.

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Popa-Simil, Liviu. « Recoil Based Fuel Breeding Fuel Structure ». MRS Proceedings 1104 (2008). http://dx.doi.org/10.1557/proc-1104-nn07-21.

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AbstractNuclear transmutation reactions are based on the absorption of a smaller particle as neutron, proton, deuteron, alpha, etc. The resulting compound nucleus gets out of its initial lattice mainly by taking the recoil, also with help from its sudden change in chemical properties. The recoil implantation is used in correlation with thin and ultra thin materials mainly for producing radiopharmaceuticals and ultra-thin layer radioactive tracers. In nuclear reactors, the use of nano-particulate pellets could facilitate the recoil implantation for breeding, transmutation and partitioning purposes. Using enriched 238U or 232Th leads to 239Pu and 233U production while using other actinides as 240Pu, 241Am etc. leads to actinide burning. When such a lattice is immersed into a radiation resistant fluid (water, methanol, etc.), the recoiled product is transferred into the flowing fluid and removed from the hot area using a concentrator/purifier, preventing the occurrence of secondary transmutation reactions. The simulation of nuclear collision and energy transfer shows that the impacted nucleus recoils in the interstitial space creating a defect or lives small lattices. The defect diffuses, and if no recombination occurs it stops at the lattices boundaries. The nano-grains are coated in thin layer to get a hydrophilic shell to be washed by the collection liquid the particle is immersed in. The efficiency of collection depends on particle magnitude and nuclear reaction channel parameters. For 239Pu the direct recoil extraction rate is about 70% for 238UO2 grains of 5 nm diameters and is brought up to 95% by diffusion due to 239Neptunium incompatibility with Uranium dioxide lattice. Particles of 5 nm are hard to produce so a structure using particles of 100 nm have been tested. The particles were obtained by plasma sputtering in oxygen atmosphere. A novel effect as nanocluster radiation damage robustness and cluster amplified defects rejection will be discussed. The advantage of the method and device is its ability of producing small amount of isotopic materials easy to separate, using the nuclear reactors, with higher yield than the accelerator based methods and requiring less chemistry. It also represents a reliable candidate for nuclear fuel breeding reducing the cost of super-grade Plutonium and Thorium toward the price of urania and thoria.
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Liem, Peng Hong, Yoshihisa Tahara, Naoyuki Takaki et Donny Hartanto. « Performance indices optimization of l ong‐lived fission products transmutation in fast reactors ». International Journal of Energy Research, 6 septembre 2021. http://dx.doi.org/10.1002/er.7250.

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Zou, Chunyan, Chenggang Yu, Jianhui Wu, Xiangzhou Cai et Jingen Chen. « Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors ». International Journal of Energy Research, janvier 2021. http://dx.doi.org/10.1002/er.6368.

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Banerjee, S., et H. P. Gupta. « Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India ». Journal of Nuclear Engineering and Radiation Science 3, no 2 (1 mars 2017). http://dx.doi.org/10.1115/1.4035435.

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The technology of pressurized heavy water reactors (PHWRs) which was developed with prime objectives of using natural uranium fuel, implementing on power fuelling, utilizing mined uranium most effectively, and achieving excellent neutron economy has demonstrated impressive performance in terms of high capacity factors and an impeccable safety record. The safety features and several technology advancements evolved over the years in which Indian contributions that are considerable are briefly discussed in the first part of the paper. Unique features of PHWR such as flexibility of fuel management, distribution of pressure boundaries in multiple pressure tubes (PTs), and a large inventory of coolant-moderator heat sink in close proximity of the core provide inherent safety and fuelling options to these reactors. PHWRs, in India have demonstrated to have the advantage of lower capital cost per megawatt even in small size reactors. Low burn up associated with natural uranium fuel, higher level of tritium in the heavy water coolant, and a slightly positive coolant void coefficient in present generation PHWRs have all been addressed in the design of advanced heavy water reactor (AHWR). The merit of adopting closed fuel cycle with partitioning of minor actinides in reducing the burden of radio-toxicity of nuclear waste and of deploying light water reactors (LWRs) in tandem with PHWRs in the evolving nuclear fuel cycle in India are also discussed.
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Balbaud-Célérier, F., et L. Martinelli. « Modeling of Fe–Cr Martensitic Steels Corrosion in Liquid Lead Alloys ». Journal of Engineering for Gas Turbines and Power 132, no 10 (7 juillet 2010). http://dx.doi.org/10.1115/1.4000865.

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Among the Generation IV systems, sodium fast reactors (SFRs) are promising and benefits of considerable technological experience. However, the availability and acceptability of the SFR are affected by the problems linked with the sodium-water reaction. One innovative solution to this problem is the replacement of the sodium in the secondary loops by an alternative liquid fluid. Among the fluids considered, lead-bismuth is at the moment being evaluated. Liquid lead-bismuth has been considerably studied in the frame of the research program on accelerator driven systems for transmutation applications. However, lead alloys are corrosive toward structural materials. The main parameters impacting the corrosion rate of Fe–Cr martensitic steels (considered as structural materials) are the nature of the steel (material side), temperature, liquid alloy velocity, and dissolved oxygen concentration (liquid alloy side). In this study, attention is focused on the behavior of Fe-9Cr steels, and more particularly, T91 martensitic steel. It has been shown that in the case of Fe–Cr martensitic steels, the corrosion process depends on the concentration of oxygen dissolved in Pb–Bi. For an oxygen concentration lower than the one necessary for magnetite formation (approximately <10−8 wt % at T≈500°C for Fe-9Cr steels), corrosion proceeds by dissolution of the steel. For a higher oxygen content dissolved in Pb–Bi, corrosion proceeds by oxidation of the steel. These two corrosion processes have been experimentally and theoretically studied in CEA Saclay and also by other partners, leading to some corrosion modeling in order to predict the life duration of these materials as well as their limits of utilization. This study takes into account the two kinds of corrosion processes: dissolution and oxidation. In these two different processes, the lead alloy physico-chemical parameters are considered: the temperature and the liquid alloy velocity for both processes and the oxygen concentration for oxidation.
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McGlashan, Niall R., Peter R. N. Childs, Andrew L. Heyes et Andrew J. Marquis. « Producing Hydrogen and Power Using Chemical Looping Combustion and Water-Gas Shift ». Journal of Engineering for Gas Turbines and Power 132, no 3 (3 décembre 2009). http://dx.doi.org/10.1115/1.3159371.

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A cycle capable of generating both hydrogen and power with “inherent” carbon capture is proposed and evaluated. The cycle uses chemical looping combustion to perform the primary energy release from a hydrocarbon, producing an exhaust of CO. This CO is mixed with steam and converted to H2 and CO2 using the water-gas shift reaction (WGSR). Chemical looping uses two reactions with a recirculating oxygen carrier to oxidize hydrocarbons. The resulting oxidation and reduction stages are preformed in separate reactors—the oxidizer and reducer, respectively, and this partitioning facilitates CO2 capture. In addition, by careful selection of the oxygen carrier, the equilibrium temperature of both redox reactions can be reduced to values below the current industry standard metallurgical limit for gas turbines. This means that the irreversibility associated with the combustion process can be reduced significantly, leading to a system of enhanced overall efficiency. The choice of oxygen carrier also affects the ratio of CO versus CO2 in the reducer’s flue gas, with some metal oxide reduction reactions generating almost pure CO. This last feature is desirable if the maximum H2 production is to be achieved using the WGSR reaction. Process flow diagrams of one possible embodiment using a zinc based oxygen carrier are presented. To generate power, the chemical looping system is operated as part of a gas turbine cycle, combined with a bottoming steam cycle to maximize efficiency. The WGSR supplies heat to the bottoming steam cycle, and also helps to raise the steam necessary to complete the reaction. A mass and energy balance of the chemical looping system, the WGSR reactor, steam bottoming cycle, and balance of plant is presented and discussed. The results of this analysis show that the overall efficiency of the complete cycle is dependent on the operating pressure in the oxidizer, and under optimum conditions exceeds 75%.
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