Journal articles: 'Nuclear fuels – Computer programs'

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FAGHIHI, F., and M. R. NEMATOLLAHI. "NUCLEAR FUEL DEPLETION ANALYSIS USING MATLAB SOFTWARE." International Journal of Modern Physics C 17, no. 06 (June 2006): 805–15. http://dx.doi.org/10.1142/s0129183106009229.

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Coupled first order IVPs are frequently used in many parts of engineering and sciences. In this article, we presented a code including three computer programs which are joint with the Matlab software to solve and plot the solutions of the first order coupled stiff or non-stiff IVPs. Some engineering and scientific problems related to IVPs are given and fuel depletion (production of the 239 Pu isotope) in a Pressurized Water Nuclear Reactor (PWR) are computed by the present code.

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Seydaliev, M., and D. Caswell. "CORBA AND MPI-BASED “BACKBONE” FOR COUPLING ADVANCED SIMULATION TOOLS." AECL Nuclear Review 3, no. 2 (December 1, 2014): 83–90. http://dx.doi.org/10.12943/anr.2014.00036.

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There is a growing international interest in using coupled, multidisciplinary computer simulations for a variety of purposes, including nuclear reactor safety analysis. Reactor behaviour can be modeled using a suite of computer programs simulating phenomena or predicting parameters that can be categorized into disciplines such as Thermalhydraulics, Neutronics, Fuel, Fuel Channels, Fission Product Release and Transport, Containment and Atmospheric Dispersion, and Severe Accident Analysis. Traditionally, simulations used for safety analysis individually addressed only the behaviour within a single discipline, based upon static input data from other simulation programs. The limitation of using a suite of stand-alone simulations is that phenomenological interdependencies or temporal feedback between the parameters calculated within individual simulations cannot be adequately captured. To remove this shortcoming, multiple computer simulations for different disciplines must exchange data during runtime to address these interdependencies. This article describes the concept of a new framework, which we refer to as the “Backbone,” to provide the necessary runtime exchange of data. The Backbone, currently under development at AECL for a preliminary feasibility study, is a hybrid design using features taken from the Common Object Request Broker Architecture (CORBA), a standard defined by the Object Management Group, and the Message Passing Interface (MPI), a standard developed by a group of researchers from academia and industry. Both have well-tested and efficient implementations, including some that are freely available under the GNU public licenses. The CORBA component enables individual programs written in different languages and running on different platforms within a network to exchange data with each other, thus behaving like a single application. MPI provides the process-to-process intercommunication between these programs. This paper outlines the different CORBA and MPI configurations examined to date, as well as the preliminary configuration selected for coupling 2 existing safety analysis programs used for modeling thermal–mechanical fuel behavior and fission product behavior respectively. In addition, preliminary work in hosting both the Backbone and the associated safety analysis programs in a cluster environment are discussed.

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Okunev, V. S. "Fundamentally New Composite Materials of Fast Reactors Made on the Basis of Nanotechnology." Key Engineering Materials 887 (May 2021): 159–64. http://dx.doi.org/10.4028/www.scientific.net/kem.887.159.

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The main goal of the work is to identify the advantages of fast reactors when using nanotechnology in the manufacture of core materials. The research methods are based on the adaptation of known technologies (including powder metallurgy) to the design of fast reactors and on the numerical simulation of physical processes carried out using computer programs for the analysis of emergency conditions of fast reactors (including anticipated transient without scram - ATWS). The results of the research show that the use of structural materials based on steels hardened by nanooxides in combination with fundamentally new types of fuel based on composite materials can significantly improve the safety of nuclear technics. Sintered mixtures of ceramic microgranules (oxide, nitride) and nanoadditives of metallic beryllium or uranium are considered as nuclear fuel. Such composite nuclear fuel improves reactor safety and power. The following types of composite fuel were analyzed: mixed oxide with additives of a beryllium or uranium nanopowder, mixed mononitride with additives of a beryllium or uranium nanopowder. Most preferably, a ceramic-metal pellet fuel based on mononitride microgranules and uranium metal nanopowder. The use of such fuel (with a volume fraction of metallic uranium up to 20%) significantly increases the safety of the reactor, combining the advantages of metal and ceramics and completely neutralizing their disadvantages. The proposed materials are of practical importance in the development of new concepts of nuclear technics, in the transition to large-scale nuclear power and high-power reactors. The use of a new cermet-based composite fuel increases the power of the reactor and significantly increases the safety of the reactor.

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Byers, J. L. "Desktop Failure Analysis on a Microcomputer Using Weibull, Lognormal, and Renewal Data." Journal of Engineering for Gas Turbines and Power 112, no. 2 (April 1, 1990): 233–36. http://dx.doi.org/10.1115/1.2906168.

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Gas turbine components and parts are widely known to have many failure modes for which the failures correlate in either the Weibull or Lognormal probability distributions. This paper describes a typical case, which is handled by the new computer programs now being used by the U. S. Navy. These programs have brought the capability to make such analyses directly to the designer or analyst’s desk instead of having to be sent off to a central computer to wait in line. The programs are interactive with the user and extremely user friendly. Uses are expanding to cover almost every area in the life cycle of gas turbines where it would be beneficial to forecast future failures. This makes the programs useful to managers, logisticians, life cycle cost analysts, and a host of others. Wide applicability of the methods assures usage outside of the gas turbine field.

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Perz, E. "A Computer Method for Thermal Power Cycle Calculation." Journal of Engineering for Gas Turbines and Power 113, no. 2 (April 1, 1991): 184–89. http://dx.doi.org/10.1115/1.2906543.

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This paper describes a highly flexible computer method for thermodynamic power cycle calculations (PCC). With this method the user can model any cycle scheme by selecting components from a library and connecting them in an appropriate way. The flexibility is not restricted by any predefined cycle schemes. A power cycle is mathematically represented by a system of algebraic equations. The structure of mathematical cycle models as well as different approaches to set up and solve the resulting equations with computer programs are discussed in the first section. The second section describes the developed method. The mass and energy balance equations are set up and solved with a semiparallel algorithm. As input only the cycle’s topology and component parameters must be entered. Information about the calculation sequence and the convergence method can be omitted completely. The example of two simple steam cycles demonstrates the applied technique. The method requires only a few, if any, iterations. Calculation time and storage requirements can be kept low enough to calculate even very complex cycles on personal computers. At the end of the paper input data and results for a complex cycle scheme as it may occur in reality are given to demonstrate the performance finally.

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Fishbach, L. H., and S. Gordon. "NNEPEQ—Chemical Equilibrium Version of the Navy/NASA Engine Program." Journal of Engineering for Gas Turbines and Power 111, no. 1 (January 1, 1989): 114–16. http://dx.doi.org/10.1115/1.3240205.

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The Navy NASA Engine Program, NNEP, developed in 1975, currently is in use at a large number of government agencies, commercial companies, and universities. This computer code has been used extensively to calculate the design and off-design (matched) performance of a broad range of turbine engines, ranging from subsonic turboprops to variable cycle engines for supersonic transports. Recently, there has been increased interest in applications that NNEP was not capable of simulating, namely, high Mach applications, alternate fuels including cryogenics, and cycles such as the gas generator air-turbo-rocket (ATR). In addition, there is interest in cycles employing ejectors such as for military fighters. New engine component models had to be created for incorporation into NNEP, and it was also found necessary to include chemical dissociation effects of high-temperature gases. This paper discusses the incorporation of these extended capabilities of NNEP and illustrates some of the effects of these changes.

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Zhao, Xiaolu. "Stream Function Solution of Transonic Flow Along S2 Streamsurface of Axial Turbomachines." Journal of Engineering for Gas Turbines and Power 108, no. 1 (January 1, 1986): 138–43. http://dx.doi.org/10.1115/1.3239860.

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Based on Wu’s general equations of 3-D turbomachine flow, expressed with respect to nonorthogonal curvilinear coordinates, the conservative stream-function formulations of transonic flow along S2 streamsurface have been discussed. The problem of mixed flow can be solved by the use of the artificial compressibility method, and the passage shock on the S2 streamsurface can be captured. The distribution of the fluid velocity from hub to shroud can be obtained directly by integrating the velocity gradient equation, after the principal equation has been solved, so that the difficulty of the nonuniqueness of density-mass flux relation is avoided. The density is determined after the velocity has been obtained. Two computer programs have been coded; one can be used to compute the hybrid or design problems, the other is suitable to compute the analysis problem. The former has been used to compute the transonic flow field along a mean S2 streamsurface in the DFLVR compressor rotor at design speed. The numerical results agree well with L2F measurement data.

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Barber, D. H. "Implementation of A Gibbs Energy Minimizer In A Fission-Product Release Computer Program." AECL Nuclear Review 2, no. 1 (June 1, 2013): 39–48. http://dx.doi.org/10.12943/anr.2013.00005.

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SOURCE 2.0 is the Canadian computer program for calculating fractional release of fission products from the UO2 fuel matrix. In nuclear accidents, fission-product release from fuel is one of the physical steps required before radiation dose from fission products can affect the public. Fission-product release calculations are a step in the analysis path to calculating dose consequences to the public from postulated nuclear accidents. SOURCE 2.0 contains a 1997 model of fission-product vaporization by B.J. Corse et al. based on lookup tables generated with the FACT computer program. That model was tractable on computers of that day. However, the understanding of fuel thermochemistry has advanced since that time. Additionally, computational resources have significantly improved since the time of the development of the Corse model and now allow incorporation of the more-rigorous thermodynamic treatment. Combining the newer Royal Military College of Canada (RMC) thermodynamic model of irradiated uranium dioxide fuel, a new model for fission-product vaporization from the fuel surface, a commercial user-callable thermodynamics subroutine library (ChemApp), an updated nuclide list, and updated nuclear physics data, a prototype computer program based on SOURCE IST 2.0P11 has been created that performs thermodynamic calculations internally. The resulting prototype code (with updated and revised data) provides estimates of 140La releases that are in better agreement with experiments than the original code version and data. The improvement can be quantified by a reduction in the mean difference between experimental and calculated release fractions from 0.70 to 0.07. 140La is taken to be representative of “low-volatile” fission products. To ensure that the existing acceptable performance for noble gases and volatile fission products is not adversely affected by the changes, comparisons were also made for a representative noble gas, 85Kr, and a representative volatile fission-product, 134Cs. These nuclides have the largest dataset in the SOURCE 2.0 validation test suite. This improvement provides increased confidence in the safety margin for equipment qualification in Loss-of-Coolant Accidents with Loss of Emergency Core Cooling.

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Bachhav, Mukesh, Brandon Miller, Jian Gan, Dennis Keiser, Ann Leenaers, S. Van den Berghe, and Mitchell K. Meyer. "Microstructural Changes and Chemical Analysis of Fission Products in Irradiated Uranium-7 wt.% Molybdenum Metallic Fuel Using Atom Probe Tomography." Applied Sciences 11, no. 15 (July 27, 2021): 6905. http://dx.doi.org/10.3390/app11156905.

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Understanding the microstructural and phase changes occurring during irradiation and their impact on metallic fuel behavior is integral to research and development of nuclear fuel programs. This paper reports systematic analysis of as-fabricated and irradiated low-enriched U-Mo (uranium-molybdenum metal alloy) fuel using atom probe tomography (APT). This study is carried out on U-7 wt.% Mo fuel particles coated with a ZrN layer contained within an Al matrix during irradiation. The dispersion fuel plates from which the fuel samples were extracted are irradiated at Belgian Nuclear Research Centre (SCK CEN) with burn-up of 52% and 66% in the framework of the SELENIUM (Surface Engineering of Low ENrIched Uranium-Molybdenum) project. The APT studies on U-Mo particles from as-fabricated fuel plates enriched to 19.8% revealed predominantly γ-phase U-Mo, along with a network of the cell boundary decorated with α-U, γ’-U2Mo, and UC precipitates along the grain boundaries. The corresponding APT characterization of irradiated fuel samples showed formation of fission gas bubbles enriched with solid fission products. The intermediate burnup sample showed a uniform distribution of the typical bubble superlattice with a radius of 2 nm arranged in a regular lattice, while the high burnup sample showed a non-uniform distribution of bubbles in grain-refined regions. There was no evidence of remnant α-U, γ’-U2Mo, and UC phases in the irradiated U-7 wt.% Mo samples.

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El-Sayed, Y. M. "A Second-Law-Based Optimization: Part 2—Application." Journal of Engineering for Gas Turbines and Power 118, no. 4 (October 1, 1996): 698–703. http://dx.doi.org/10.1115/1.2816982.

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This paper deals with an application of the second-law-based optimization methodology described in Part 1 of this paper. The methodology is applied to a simple energy system of 10 components and 19 manipulated decision parameters. The system is treated once as a single-purpose combined cycle and once as a power-heat cogenerating system. The results of the application are summarized and evaluated. The required computer programs are described. Further investigations are suggested.

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Guo, Zenglin, Toshio Hirano, and R. Gordon Kirk. "Application of CFD Analysis for Rotating Machinery—Part I: Hydrodynamic, Hydrostatic Bearings and Squeeze Film Damper." Journal of Engineering for Gas Turbines and Power 127, no. 2 (April 1, 2005): 445–51. http://dx.doi.org/10.1115/1.1807415.

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The traditional method for bearing and damper analysis usually involves a development of rather complicated numerical calculation programs that may just focus on a simplified and specific physical model. The application of the general CFD codes may make this analysis available and effective where complex flow geometries are involved or when more detailed solutions are needed. In this study, CFX-TASCflow is employed to simulate various fixed geometry fluid-film bearing and damper designs. Some of the capabilities in CFX-TASCflow are applied to simulate the pressure field and calculate the static and dynamic characteristics of hydrodynamic, hydrostatic, and hybrid bearings as well as squeeze film dampers. The comparison between the CFD analysis and current computer programs used in industry has been made. The results show reasonable agreement in general. Some of the possible reasons for the differences are discussed. It leaves room for further investigation and improvement on the methods of computation.

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Zimmermann, H. "Some Aerodynamic Aspects of Engine Secondary Air Systems." Journal of Engineering for Gas Turbines and Power 112, no. 2 (April 1, 1990): 223–28. http://dx.doi.org/10.1115/1.2906166.

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Internal cooling air systems of turbomachines contain various fluid flow components, i.e., rotating holes, tapping configurations, coverplates, labyrinth seals, etc., for which only the basic aerodynamics are known. Numerical calculations for these elements are carried out and compared with test results showing fair agreement in general. For most of the components of internal air systems there is a serious lack of test data. It is shown that the situation can be relieved by applying numerical methods, which also should be used to improve and extend the empirical correlations in the air systems computer programs.

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McKnight, R. L. "Structural Analysis Applications." Journal of Engineering for Gas Turbines and Power 111, no. 2 (April 1, 1989): 271–78. http://dx.doi.org/10.1115/1.3240248.

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The programs in the structural analysis area of the HOST program emphasized the generation of computer codes for performing three-dimensional inelastic analysis with more accuracy and less manpower. This paper presents the application of that technology to Aircraft Gas Turbine Engine (AGTE) components: combustors, turbine blades, and vanes. Previous limitations will be reviewed and the breakthrough technology highlighted. The synergism and spillover of the program will be demonstrated by reviewing applications to thermal barrier coatings analysis and the SSME HPFTP turbine blade. These applications show that this technology has increased the ability of the AGTE designer to be more innovative, productive, and accurate.

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Niering, E. "Simulation of Bird Strikes on Turbine Engines." Journal of Engineering for Gas Turbines and Power 112, no. 4 (October 1, 1990): 573–78. http://dx.doi.org/10.1115/1.2906207.

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External components of aeroengines, such as casings and intake blades, must be capable of withstanding bird strikes. Various methods of computer simulation that have been developed are presented in summary. The most accurate and meaningful results are obtained with finite element programs specifically developed for impact events. Bird and component are divided into finite elements. The component model must allow for great elastic-plastic deformation, where the yield strength is a function of the strain rate. A model shape and a homogeneous substitute material must be defined for the complicated and nonhomogeneous structure of the bird. Bird strikes on a rotating spinner and an intake blade are investigated with the finite element program DYNA3D.

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Cofer, J. I. "Advances in Steam Path Technology." Journal of Engineering for Gas Turbines and Power 118, no. 2 (April 1, 1996): 337–52. http://dx.doi.org/10.1115/1.2816595.

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For many years, GE has been conducting research to understand better the loss mechanisms that degrade the aerodynamic performance of steam turbine stages, and to develop new computational fluid dynamics (CFD) computer programs to predict these losses accurately. This paper describes a number of new steam path design features that have been introduced in the GE steam turbine product line to improve turbine performance and reliability. These features include diaphragms with contoured sidewalls, advanced vortex blading with compound tangential lean, new continuously coupled last-stage buckets with improved aerodynamic efficiency and reliability, improved downward and axial flow exhaust hoods, and better steam leakage control devices. The benefits of these new features for both new units and retrofits of existing units are discussed. In addition, the paper discusses the new generation of three-dimensional viscous CFD analysis codes being used to develop new design concepts, including codes developed by GE as well as those obtained externally. Also described are the extensive laboratory test programs being conducted to validate the CFD codes and verify the predicted efficiency gains for new design features. Last, the paper describes new and unique state-of-the-art steam path design automation and optimization tools that dramatically reduce the design cycle time for new advanced aerodynamic designs.

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Haddad, S. D. "Piston Motion and Thermal Loading Analyses of Two-Stroke and Four-Stroke Cycle Engines for Locomotives." Journal of Engineering for Gas Turbines and Power 111, no. 3 (July 1, 1989): 536–42. http://dx.doi.org/10.1115/1.3240288.

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Two-stroke cycle and four-stroke cycle diesel engines are in use in rail traction, with the four-stroke cycle design dominating the field. Cycle simulations using computer programs have shown that the conventional two-stroke cycle is somewhat inferior to its four-stroke cycle counterpart in combustion efficiency and thermal loading. Research at Sulzer concluded that the conventional two-stroke cycle engine is not very suitable for locomotive application. A survey by Ricardos, based on an investigation of engines in current production for traction application, suggested that there are potentials in two-stroke cycle design. This paper presents a summary of the results of a research project concerned with comparison of two well-proven typical locomotive diesel engines, one with a two-stroke cycle and the other with a four-stroke cycle. Performance, mechanical loading, thermal loading, and vibration were chosen as parameters to be investigated to provide information on the status of the two cycles in relation to power range, fuel consumption, reliability, and durability, with a view to assisting the users of locomotive engines to make the correct choice.

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Conway, L., H. F. Martin, A. L. Stock, and F. R. Vaccaro. "A Ruggedized Design Approach to Reduce Maintenance and Enhance the Efficiency of High and Intermediate Pressure Steam Turbines." Journal of Engineering for Gas Turbines and Power 111, no. 4 (October 1, 1989): 619–24. http://dx.doi.org/10.1115/1.3240298.

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The industry issues of minimizing maintenance and maintaining turbine performance with operating time have been systematically addressed using creative approaches to control wear, erosion, vibration, and distortion of critical High-Pressure (HP) and Intermediate-Pressure (IP) Steam Turbine components. The important components were identified utilizing a new technique to analyze turbine high maintenance areas. New technology advances were utilized to understand the causes of the maintenance, and to reduce or eliminate it. The technology advances discussed in the paper are in the area of three-dimensional computer programs, materials, coatings, modern computer-aided drafting, and verification testing. These, in conjunction with new creative design approaches for the critical components, have resulted in a ruggedized HP and HP/IP turbine design, which is retrofittable in today’s operating units. Of special interest are the steps taken to give rapid and individually customized attention from design through manufacturing to each unique situation and utility. Among the benefits achieved are up to a 50 percent overall reduction in maintenance, up to 120 Btu/kWh (30 kcal/kWh) reduction in heat rate, and an increased cyclic duty capability for the ruggedized turbines.

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Cue, R. W., and D. E. Muir. "Engine Performance Monitoring and Troubleshooting Techniques for the CF-18 Aircraft." Journal of Engineering for Gas Turbines and Power 113, no. 1 (January 1, 1991): 11–19. http://dx.doi.org/10.1115/1.2906519.

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The F404-GE-400 engines of the CF-18 aircraft are the first engines of the Canadian Forces to be maintained under a formal on-condition maintenance program. In support of this program, the Canadian Forces are developing advanced troubleshooting and performance monitoring procedures based on information recorded by the aircraft In-flight Engine Condition Monitoring System (IECMS). A suite of computer programs has been developed that enables maintenance personnel to access, display, and analyze in-flight event data recorded by the IECMS and to track the performance of individual engines based on “health indices” derived from the IECMS take-off ground roll recordings. The new techniques have been under evaluation at each of the CF-18 main operating bases for a period of approximately 14 months. Results to date indicate that the IECMS recordings provide a considerable amount of information of benefit to engine technicians and maintenance planners.

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Aiello, R. A., and S. Chi. "Advanced Composite Turboprops: Modeling, Structural, and Dynamic Analyses." Journal of Engineering for Gas Turbines and Power 110, no. 2 (April 1, 1988): 306–11. http://dx.doi.org/10.1115/1.3240122.

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This paper presents a structural and dynamic analysis of a scaled-down wind tunnel model prop-fan blade made from fiber composites. This blade is one of a series of prop-fan blades that have been tested at the Lewis Research Center wind tunnel facilities. The blade is highly swept and twisted and of the spar/shell construction. Due to the complexity of the blade geometry and its high performance, it is subjected to much higher loads and tends to be much less stable than conventional blades. The structural and dynamic analyses of the blade were performed using the NASA-Lewis COBSTRAN computer code. COBSTRAN is designed to generate the mesh and calculate the anisotropic material properties for composite blade analysis. Comparison of analytical and experimental mode shapes and frequencies are shown, verifying the model development and analysis techniques used. The methodologies and programs developed for this analysis are directly applicable to other prop-fan blades.

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Ovdiienko, I., O. Kuchyn, M. Ieremenko, and P. Vlasenko. "Adaptation of HELIOS Models for WWER-440 Fuel Assemblies to Application by the TRACE/PARCS Program." Nuclear and Radiation Safety, no. 1(81) (March 12, 2019): 46–51. http://dx.doi.org/10.32918/nrs.2019.1(81).08.

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The preparation of a few-group neutron cross-section library is an important step in implementation of the computer packages that are based on solution of the neutron transport equation in the few-group diffusion approximation into the safety analysis practices. The accuracy of modelling the physical neutron kinetic processes in the reactor core directly depends on the quality of few-group cross-section library. It is important to note that such cross-section library should be prepared in the format applied in the computer package and with use of a spectral code that models the fuel assembly quite adequately. The best option for preparing the few-group neutron crosssection library for the PARCS few-group diffusion code, which is being introduced into SSTC NRS safety analysis practices as a part of the TRACE/PARCS coupled neutron kinetic/thermal hydraulic package, is to adapt the previously developed and validated models of fuel assemblies for the HELIOS spectral program. The adaptation procedure for HELIOS models for WWER-440 including the fuel follower and transition part forming the input file structure required for correct work of the GenPMAXS program is presented. The approaches to the choice of reference states and branch parameters in the PARCS code format are presented. The results from correctness analysis of the adaptation of the HELIOS WWER-440 fuel assembly computer models are presented. The results are based on a comparative analysis of the fuel assembly multiplication properties obtained by the HELIOS model that was developed for preparation of the cross-section libraries for the DYN3D program (validated and widely used at SSTC NRS at present), and by the HELIOS model that was adapted for the GENPMAX program.

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Mohd Fadzil, Syazwani, Shafi Qureshi, Sekhar Basu, K. Kasturirangan, Anil Kakodkar, Kushal D. Badgujar, and Prakash M. Duxit. "Nuclear policy-nuclear fuels for peaceful, safer co-generation and environmentally benign applications." International Journal of Engineering & Technology 9, no. 3 (August 24, 2020): 724. http://dx.doi.org/10.14419/ijet.v9i3.30930.

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Here, safer nuclear fuels which can sustain in the high temperature and fluence environment of the reactor core are investigated to utilize nuclear energy peacefully. At Nuclear Fuel Complex in Hyderabad, nuclear fuels are being manufactured which are best suited for high temperature and fluence environment of the reactor core even in accidental scenarios. In this paper, nuclear fuels manufactured at NFC, Hyderabad are presented. The developed nuclear fuels have higher equivalent hydraulic diameter and breeding capability to produce U^233. Nuclear fuels having higher equivalent hydraulic diameter reduce the reactor core temperature substantially. These fuels have negative temperature coefficient of reactivity. Thus, in case of an accident, the fuel temperature never exceeds the safety limit. Therefore, the thermal heat available across the secondary of a heat exchanger can be utilized for different industrial processes. This allows the development of key technologies, such as safer co-generation of electricity and Hydrogen. The Three-Stage Indian Nuclear Power Program has been explained for nuclear disarmament. The product Hydrogen gas has been utilized in many ways for different applications. Moreover, the processing of iron ore with the energy obtained from the IHX secondary side, eliminates the burning of coals and CO2 emissions into the environment. Several radioisotopes have been developed for medical applications from spent fuel.

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Simpson, J. C. B., and L. G. Earwaker. "Computer simulation programs for nuclear reaction analysis." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 15, no. 1-6 (April 1986): 502–7. http://dx.doi.org/10.1016/0168-583x(86)90351-4.

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Sakagami, M., K. Hiramoto, and M. Ishida. "BEAF - a computer program for analysis of light water reactor fuel rod behavior." Nuclear Engineering and Design 86, no. 2 (May 1985): 241–52. http://dx.doi.org/10.1016/0029-5493(85)90225-0.

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KUROSAKI, Ken, Jun ADACHI, Masahito KATAYAMA, Masayoshi UNO, and Shinsuke YAMANAKA. "Computer Simulation Makes Atomic-Design of Nuclear Fuel ; Molecular Dynamic Studies of Nuclear Fuels." Journal of the Atomic Energy Society of Japan 49, no. 10 (2007): 676–80. http://dx.doi.org/10.3327/jaesjb.49.10_676.

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Väth, L. "Modeling Transient Fission Gas Behavior for Solid, Melting, and Molten Fuel in the Computer Program LAKU." Nuclear Technology 98, no. 1 (April 1992): 44–53. http://dx.doi.org/10.13182/nt92-a34649.

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Peerenboom, James P., William A. Buehring, and Timothy W. Joseph. "OR Practice—Selecting a Portfolio of Environmental Programs for a Synthetic Fuels Facility." Operations Research 37, no. 5 (October 1989): 689–99. http://dx.doi.org/10.1287/opre.37.5.689.

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Zaidel’, R. M. "New computer programs for data processing." Atomic Energy 103, no. 2 (August 2007): 657–59. http://dx.doi.org/10.1007/s10512-007-0105-0.

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EZURE, Hideo. "Vaiidition of ORIGEN Computer Code by Measurements on Nuclear Fuels of JPDR-1." Journal of Nuclear Science and Technology 26, no. 8 (August 1989): 777–86. http://dx.doi.org/10.1080/18811248.1989.9734382.

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Guéneau, C., N. Dupin, L. Kjellqvist, E. Geiger, M. Kurata, S. Gossé, E. Corcoran, et al. "TAF-ID: An international thermodynamic database for nuclear fuels applications." Calphad 72 (March 2021): 102212. http://dx.doi.org/10.1016/j.calphad.2020.102212.

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Shahabuddin, Syed, and Sayeda Daud. "http://habibiaislamicus.com/index.php/hirj/article/view/181." Habibia Islamicus 4, no. 2 (December 27, 2020): 43–56. http://dx.doi.org/10.47720/hi.2020.0402e07.

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Peaceful atomic production is generally separated into five fundamental territories: extraction and preparing of atomic crude materials, the creation of advanced uranium, generation of atomic fuel components, development and task of atomic reactors and reprocessing of energizes. Notwithstanding utilizing atomic vitality to produce power from control reactors, it is likewise generally utilized in agribusiness, prescription, industry, science and hydrology. Power is right now produced by the iota in created nations. Different nations are additionally attempting endeavors to create power from modest atomic power plants, which utilize little amounts of radioactive substances to deliver power on a substantial scale. Radiation from atomic reactors is at times used to regard sicknesses, for example, tumor. These beams are likewise used to eliminate germs and destructive creepy crawlies in farmland and nourishment items. In the atomic division, organizations or associations can work in various parts of the Muslim world. Pakistan facing difficulty to keep nuclear plant powered due to shortage of nuclear electricity and other challenges are concerns are regarding its security and protection from natural disasters due to climate change which would triple energy consumption of nuclear plant. Although generating electricity from nuclear energy is cost effective as compared to generating electricity from oil and gas or coal, and nuclear radiation can be used to diagnose, treat critical diseases like cancer. Most importantly it can be used in neuropsychiatry to produce brain imaging using gamma camera and single photon emission computed tomography to diagnose depression, anxiety and stress. Pakistan has potential to facilitate its nation and can avail benefit by seeking nuclear technology for mass development programs. The objective of the study is to discuss the Civil Nuclear institute of Technology and what are their contributions and its scope in Pakistan. Atomic researchers can progress toward becoming individuals from these social orders to cooperate on the tranquil utilization of atomic vitality. The researchers should make the best utilization of atomic vitality for vitality purposes to serve all in Pakistan which is begin highlighted the areas in this research and concluded Pakistan facing difficulty to keep nuclear plant powered due to shortage of nuclear electricity and other challenges are concerns are regarding its security and protection from natural disasters due to climate change which would triple energy consumption of nuclear plant. Although generating electricity from nuclear energy is cost effective as compared to generating electricity from oil and gas or coal, and nuclear radiation can be used to diagnose, treat critical diseases like cancer. Most importantly it can be used in neuropsychiatry to produce brain imaging using gamma camera and single photon emission computed tomography to diagnose depression, anxiety and stress. It is concluded that Pakistan has effectively connected with atomic science and technology to innovate and help the society while it is improving as well for implementation as well.

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Ponomarev-Stepnoi, N. N., V. I. Bryzgalov, E. S. Glushkov, E. A. Gomin, M. I. Gurevich, V. E. Demin, G. V. Kompaniets, et al. "Using the MCU computer program to analyze the results of critical experiments with HTGR fuel pellets on the Astra testing stand." Atomic Energy 97, no. 4 (October 2004): 669–77. http://dx.doi.org/10.1007/s10512-005-0046-4.

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Bezir, N. C., I. Akkurt, and N. Özek. "The Development of a Computer Program for Estimating Solar Radiation." Energy Sources, Part A: Recovery, Utilization, and Environmental Effects 32, no. 11 (March 26, 2010): 995–1003. http://dx.doi.org/10.1080/15567030902937234.

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Choi, Heui-Joo, Dongkeun Cho, Donghak Kook, and Jongwon Choi. "Current status of spent fuels and the development of computer programs for the PWR spent fuel management in Korea." Progress in Nuclear Energy 53, no. 3 (April 2011): 290–97. http://dx.doi.org/10.1016/j.pnucene.2010.12.006.

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Zakirov, S. Yu. "Calculating the thermal-hydraulic characteristics of a fuel assembly at supercritical parameters of coolant using the KEDR computer program." Thermal Engineering 57, no. 5 (May 2010): 370–75. http://dx.doi.org/10.1134/s0040601510050022.

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Ahluwalia, Rajesh K., and Howard K. Geyer. "The GC Computer Code for Flow Sheet Simulation of Pyrochemical Processing of Spent Nuclear Fuels." Nuclear Technology 116, no. 2 (November 1996): 180–95. http://dx.doi.org/10.13182/nt96-a35299.

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Vidal, T., L. Gallais, J. Faucheux, H. Capdevila, and Y. Pontillon. "Using laser remote heating to simulate extreme thermal heat loads on nuclear fuels." EPJ Web of Conferences 225 (2020): 08002. http://dx.doi.org/10.1051/epjconf/202022508002.

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Up to now, predicting accurately the Fission Gas Release (FGR) from high burn up UO2 and/or MOX (Mixed Oxide) fuels at off-normal conditions, such as power transient, reactivity-initiated accident (RIA) and loss-of-coolant accident (LOCA), is still a significant and very challenging task. For this purpose, different R&D programs have been carried out in France, as well as in other countries. This has been done with a specific emphasis on mechanisms which promote the FGR under accidental conditions. These studies can be performed thanks to dedicated integral experiments conducted in-pile (i.e. in Materials Testing Reactor) with the corresponding cost and constraints, or at the laboratory scale with annealing tests which allow to be representative of specific parameters (thermal history for instance). During these annealing tests under well-known conditions (temperature, atmosphere), both the absolute level and the time dependence of the released gases should be monitored, together with the corresponding fuel micro-structural changes, since experimental knowledge of fission gas release alone is not efficient enough. This approach requires more and more accurate on-line measurements. This corresponds to the driving force of the present work. In this contribution, we will present our progress in developing an experimental platform that can submit nuclear fuel and cladding samples to annealing tests involving very high temperatures (up to 2500°C) and very fast temperature ramp (up to thousands of °C/s) with controlled thermal gradients and temporal dynamics. This new platform implements innovative instrumentation, such as optical diagnostics to measure fuel fragmentation kinetics and infrared pyrometry for temperature monitoring. This experiment is based on a high-power laser (1.5kW) coupled to an experimental chamber with controlled atmosphere (Ar, N2, or vacuum) and specific optical components. Based on the spatial beam profile and temporal power function of the laser, it is possible which such a system to produce complex spatio-temporal temperature gradients, relevant for addressing different research needs. It provides access to extreme conditions that are very difficult to reach with other means. Particularly, one of main objectives of this work is to investigate conditions of Reactivity Initiated Accident (RIA). The first experiments performed on inactive materials, non-irradiated uranium dioxide, is presented in order to highlight the capabilities of this technique.

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JONES, KENDALL M., TIM B. HUNTER, and WILLIAM L. BOREN. "Computer Use and Education in Radiology Residency Programs." INVESTIGATIVE RADIOLOGY 25, no. 5 (May 1990): 596–98. http://dx.doi.org/10.1097/00004424-199005000-00022.

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Jones, K. M., T. B. Hunter, and W. L. Boren. "COMPUTER USE AND EDUCATION IN RADIOLOGY RESIDENCY PROGRAMS." Investigative Radiology 24, no. 12 (December 1989): S132. http://dx.doi.org/10.1097/00004424-198912000-00234.

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Moriarty, Patrick, and Damon Honnery. "Energy Efficiency or Conservation for Mitigating Climate Change?" Energies 12, no. 18 (September 16, 2019): 3543. http://dx.doi.org/10.3390/en12183543.

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Given that global energy use today is still dominated by fossil fuels, there is an urgent need to rapidly reduce its use in order to avert serious climate change. However, the alternatives to fossil fuels—renewable and nuclear energy—are more expensive, and have so far done little to displace fossil fuels. Accordingly, reducing energy use must play an important part in both averting climate change and avoiding the depletion of high energy return easily recoverable fossil fuel reserves. This paper examined both the potential and barriers to the adoption of energy reduction measures, with particular attention to domestic energy and passenger transport. The main finding was that energy efficiency approaches alone are unlikely to deliver anywhere near the energy reductions needed in the limited time available. Instead, most energy reductions will have to come from energy conservation, involving less use of energy-using devices, including private vehicles. Achieving such reductions will require changes in lifestyles, especially for residents of OECD nations.

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Gorshenev, A. A., and Yu M. Pis’mak. "Scaling laws in evolution of large computer programs." Physics of Particles and Nuclei Letters 5, no. 3 (May 2008): 201–6. http://dx.doi.org/10.1134/s1547477108030138.

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Paraschiv, Florentina, and Dima Mohamad. "The Nuclear Power Dilemma—Between Perception and Reality." Energies 13, no. 22 (November 20, 2020): 6074. http://dx.doi.org/10.3390/en13226074.

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Motivated by the environmental challenges and the increase in energy demand, this review assesses the suitability of nuclear power production as an alternative option to using fossil fuels. First, we assess the competitiveness of nuclear power compared to other power sources considering its economic efficiency, environmental impact and implications for health, and conclude that this is a viable option to serve in addition to and as a backup to renewable sources. Second, we review previous findings in various fields on advantages and disadvantages of nuclear power technology and conclude that there is a gap between reality and perception. Third, we discuss challenges related to nuclear weapons proliferation and misperceived public opinion on nuclear power. We conclude that the gap between perception and reality stems from a lack of consolidated interdisciplinary view, media communications focusing mainly on unilateral assessments.

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Tokarski, Stanisław, Małgorzata Magdziarczyk, and Adam Smoliński. "Risk Management Scenarios for Investment Program Delays in the Polish Power Industry." Energies 14, no. 16 (August 23, 2021): 5210. http://dx.doi.org/10.3390/en14165210.

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The introduction of the Green Deal in 2019 by the European Commission poses a significant challenge for EU member states whose power generation is based primarily on fossil fuels. In Poland, nearly 80% of the electricity is produced from fossil fuels. This paper presents an analysis of the risks related to the delays in the accomplishment of investment programs in the Polish power industry. Three scenarios were prepared for balancing the deficiency of about 3 GW of power and 20 TWh of electricity in the national power grid in the years 2031–2040, which may emerge as a result of the delayed accomplishment of investment programs, particularly in nuclear energy. The first scenario presents a variant entailing the rapid phasing out of coal and the replacement of the decommissioned power units with new gas-powered units, where the missing power volume would be partially balanced by import, and partially through gas-based production in the new power units. The second scenario assumes that the missing power would be balanced by retaining the existing, older coal-powered units, whereas the required electricity would be compensated by import. The third scenario involves the production of the missing volume of electricity using coal with CO2 capture in existing or new coal-powered units.

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Keane, Robert E. "Describing wildland surface fuel loading for fire management: a review of approaches, methods and systems." International Journal of Wildland Fire 22, no. 1 (2013): 51. http://dx.doi.org/10.1071/wf11139.

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Wildland fuelbeds are exceptionally complex, consisting of diverse particles of many sizes, types and shapes with abundances and properties that are highly variable in time and space. This complexity makes it difficult to accurately describe, classify, sample and map fuels for wildland fire research and management. As a result, many fire behaviour and effects software prediction systems use a generalised description of fuels to simplify data collection and entry into various computer programs. There are several major fuel description systems currently used in the United States, Canada and Australia, and this is a source of confusion for many in fire management. This paper (1) summarises the challenges of describing fuels, (2) contrasts approaches (association, classification and abstraction) for developing fuel description systems and (3) discusses possible future directions in wildland fuel description and science to transition to a universal fuel description system. Most discussion centres on surface fuel loadings as the primary descriptive characteristic. This synthesis paper is intended to provide background for understanding surface fuel classification and description systems and their use in simulating fire behaviour and effects, quantifying carbon inventories and evaluating site productivity.

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Albright, Norman. "Computer Programs for the Analysis of Cellular Survival Data." Radiation Research 112, no. 2 (November 1987): 331. http://dx.doi.org/10.2307/3577260.

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Nikezic, Dragoslav, Jelena M. Stajic, and Kwan Ngok Yu. "Updates to TRACK_TEST and TRACK_VISION Computer Programs." Polymers 13, no. 4 (February 13, 2021): 560. http://dx.doi.org/10.3390/polym13040560.

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The computer programs TRACK_TEST and TRACK_VISION were previously developed to model profiles and optical appearances of tracks developed in solid-state nuclear track detectors. The programs were based on a track development model that involved the bulk etch rate Vb and the track etch rate Vt or the V function (i.e., Vt/Vb). The present work reported our work to update and modify these two programs. In the revised TRACK_TEST, two new V functions were added and enabled. Sample results for the CR-39 detector obtained using the three original and the two new V functions were compared. Discrepancies were within ~10% and <14% for incident alpha-particle energies of 1 MeV and >1 MeV, respectively. Another major revision of TRACK_TEST was to enable calculations for the Makrofol detector. In the revised TRACK_VISION, the two new V functions, as well as the option for the Makrofol detector, were also added. The experimental results on the Makrofol detectors were obtained (irradiated with 3.6-MeV alpha particles under normal incidence and then etched to achieve a removed detector thickness of 30 μm) for comparisons with the modeled results using the revised TRACK_VISION. The track diameters obtained from the experiment and model were 24.7 and 23.2 μm, respectively. Moreover, a bright area in the central parts, together with an outer dark ring, were present in both the simulated and experimental tracks. The track-opening diameters and the general optical appearances of the tracks were in good agreement.

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Lisin, Evgeny, Galina Kurdiukova, Pavel Okley, and Veronika Chernova. "Efficient Methods of Market Pricing in Power Industry within the Context of System Integration of Renewable Energy Sources." Energies 12, no. 17 (August 23, 2019): 3250. http://dx.doi.org/10.3390/en12173250.

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Currently, the majority of world economies (even those located in the sunbelt (+/− 35 degrees of latitude with good sunshine with low seasonality) uses various types of fossil fuels as the main source of energy for their economies. However, this represents a very volatile and unsustainable strategy, since according to various estimates, the fossil fuel era will inevitably end as all carbon fuels are going to be spent in the next few centuries. Unlike traditional energy, renewable energy sources (RES) are not based on energy resources, but rather rely upon natural energy flows. With regard to its unique property, there has been an active construction of power plants of renewable energy and their gradual integration into national energy supply systems in recent decades. At the same time, the existing models of electricity markets were unprepared for their wide distribution. Hence, determination of the market value of energy generated by power plants using renewable energy sources becomes a particularly significant issue. This market value has to take into account the prevention of costs from the use of fossil fuels, as well as the resulting environmental benefits. Our paper proposes methods for solving this problem, contributing to the increase of economic efficiency of investment projects for the construction of renewable energy facilities and the formation of economic incentives for their propagation in energy supply systems. The proposed methods are based on the dynamic differentiation of tariffs for consumers with renewable energy sources depending on their structure of electricity consumption. Its effectiveness is demonstrated by calculating the cost of electricity for households located in the Krasnodar region using renewable energy sources. It is shown that this approach to the formation of tariffs for consumers allows the household to receive additional savings from the efficient use of energy installations on RES and energy storage devices in terms of alignment of the energy consumption schedule. This creates a significant incentive for households to use them and contributes to increasing the effectiveness of government renewable energy support programs, including by solving the acute problem of raising electricity tariffs from the grid.

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Arslan, Alper Buğra, İlayda Yilmaz, Gizem Bakir, and Hüseyin Yapici. "Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System." Science and Technology of Nuclear Installations 2019 (October 20, 2019): 1–13. http://dx.doi.org/10.1155/2019/4930274.

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This study presents the time-dependent analyses of transmutations of long-lived fission products (LLFPs) and medium-lived fission products (MLFPs) occurring in thermal reactors in a conceptual helium gas-cooled accelerator-driven system (ADS). In accordance with this purpose, the CANDU-37 and PWR 15 × 15 spent fuels are separately considered. The ADS consists of LBE-spallation neutron target, subcritical fuel zone, and graphite reflector zone. While the considered ADS is fueled with the spent nuclear fuels extracted from each thermal reactor without the use of additional fuel, fission products extracted from same thermal reactor are also placed into transmutation zone in graphite reflector zone. The LLFP transmutation performance of the modified ADS is analyzed by considering three different spent fuels extracted from the thermal reactors. Spent fuels are extracted from CANDU-37 in case A, from PWR-15 × 15 in case B, and from CANDU-37 fueled with mixture of PWR 15 × 15 spent fuel and 46% ThO2 in case C. The LBE target is bombard with protons of 1000 MeV. The proton beam power is assumed as 20 MW, which corresponds to 1.24828·1017 protons per second. MCNPX 2.7 and CINDER 90 computer codes are used for the time-dependent burn calculations. The ADS is operated under subcritical mode until the value of keff increases to 0.984, and the maximum operation times are obtained as 3400, 3270, and 5040 days according to the spent fuel cases of A, B, and C, respectively. The calculations bring out that in the modified ADS, LLFPs and MLFPs, which are extracted from thermal reactors, can be transformed to stable isotopes in significant amounts along with energy production.

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Chertkov, N. K., and V. N. Chertkov. "A package of computer programs for tuning automatic control systems." Thermal Engineering 54, no. 9 (September 2007): 734–38. http://dx.doi.org/10.1134/s004060150709011x.

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Lemm, Renato, Raphael Haymoz, Astrid Björnsen Gurung, Vanessa Burg, Tom Strebel, and Oliver Thees. "Replacing Fossil Fuels and Nuclear Power with Renewable Energy: Utopia or Valid Option? A Swiss Case Study of Bioenergy." Energies 13, no. 8 (April 20, 2020): 2051. http://dx.doi.org/10.3390/en13082051.

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The transition towards a reliable, sustainable, low-carbon energy system is a major challenge of the 21st century. Due to the lower energy density of many renewable energy sources, a future system is expected to be more decentralized, leading to significant changes at the regional scale. This study analyzes the feasibility of the energy transition in the Swiss canton of Aargau as an illustrative example and explores different strategies to satisfy the local demand for electricity, heat, and fuel by 2035. In particular, we assess the potential contribution of biomass. Four scenarios demonstrate what energy demand proportion could be covered by bioenergy if different priorities were given to the provision of heat, electricity, and fuel. The impact of improved conversion technologies is also considered. The results show that the sustainably available renewable energy sources in canton Aargau will probably not be sufficient to cover its forecasted energy demand in 2035, neither with present nor future biomass conversion technologies. At best, 74% of the energy demand could be met by renewables. Biomass can increase the degree of autarky by a maximum of 13%. Depending on the scenario, at least 26–43% (2500–5700 GWh) of total energy demand is lacking, particularly for mobility purposes.

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Okubo, Toshihiro, Daiju Narita, Katrin Rehdanz, and Carsten Schroeder. "Preferences for Nuclear Power in Post-Fukushima Japan: Evidence from a Large Nationwide Household Survey." Energies 13, no. 11 (June 8, 2020): 2938. http://dx.doi.org/10.3390/en13112938.

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Utilizing the data of a large nationwide household survey conducted in 2014, we investigate public preferences on nuclear power in Japan after the Fukushima nuclear accident and the role of four sets of factors: (1) household/individual socioeconomic characteristics, (2) psychological status, (3) geographical aspects, and (4) Fukushima accident-related experiences. The preferred energy mix, according to the averaged responses from the survey, includes 0.59 for renewables, 0.29 for fossil fuels, and 0.12 for nuclear—much more skewed towards the renewables than the actual national share of renewables of less than 0.2. Male, older, unmarried, less educated, high-income people, and government party supporters have a preference towards a higher share of nuclear power, except if they live near nuclear power plants. The experience of blackout and aversion to nuclear power during the Great East Japan Earthquake of 2011 lowers the share of nuclear power in the preferred mix.

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Journal articles on the topic 'Nuclear fuels – Computer programs'

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