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Comparisons of HELIOS, ORIGEN2, and Monteburns calculated ²⁴¹Am and ²⁴³Am concentrations to measured values for PWR, BWR, and VVER spent fuel

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JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 2000年第7期37卷 615-623页

作者： Charlton, WS Stanbro, WD Perry, RT Los Alamos Natl Lab Los Alamos NM 87545 USA

A study was performed at Los Alamos National Laboratory to explore the accuracy of several reactor analysis codes in calculating Am-241 and Am-243 concentrations in light water reactor spent fuel. Calculated higher-actinide concentrations were compared to measured values from the literature for three reactor fuels. The fuel samples were taken from the Mihama Unit 3 pressurized water reactor, the Garigliano boiling water reactor, and a VVER-440. The Am-241 and Am-243 concentrations were calculated using the HELIOS-1.4 lattice-physics code, the ORIGEN2 burnup code, and a linked MCNP/ORIGEN2 code named Monteburns 3.01. Comparisons were made between the calculated and measured values. It was determined that all codes performed consistently well for the Mihama Unit 3 measurements (within +/- 5% for Am-241 and +/- 20% for Am-243) and the Garigliano measurements (within +/- 12% for Am-241 and +/- 12% for Am-243). It was determined that the ORIGEN2 pressurized water reactor libraries are insufficient for the VVER-440 measurements, The HELIOS and MONTEBURNS codes both demonstrated good ability to calculate these isotopes for VVER-440 fuel (+/- 10% for Am-241 and +/- 12% for Am-243). The accuracies of these codes and the associated radiochemical measurements of these higher-actinide isotopes may be insufficient for safeguards and fuel management purposes;thus, development, of new methods and modification to existing data libraries may be necessary in order to enable cost-effective safeguarding of these higher-actinide materials.

关键词： spent fuels BWR type reactors PWR type reactors americium 241 VVER-type pressurized water reactor americium 243 calculation methods monte carlo method concentration ratio computer code evaluations accuracy

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Complexity measurement of natural and artificial languages

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COMPLEXITY 2015年第6期20卷 25-48页

作者： Febres, Gerardo Jaffe, Klaus Gershenson, Carlos Univ Simon Bolivar Lab Evoluc Caracas Miranda Venezuela Univ Nacl Autonoma Mexico Inst Invest Matemat Aplicadas & Sistemas Mexico City 04510 DF Mexico Univ Nacl Autonoma Mexico Ctr Ciencias Complejidad Mexico City 04510 DF Mexico

We compared entropy for texts written in natural languages (English, Spanish) and artificial languages (computer software) based on a simple expression for the entropy as a function of message length and specific word diversity. code text written in artificial languages showed higher entropy than text of similar length expressed in natural languages. Spanish texts exhibit more symbolic diversity than English ones. Results showed that algorithms based on complexity measures differentiate artificial from natural languages, and that text analysis based on complexity measures allows the unveiling of important aspects of their nature. We propose specific expressions to examine entropy related aspects of tests and estimate the values of entropy, emergence, self-organization, and complexity based on specific diversity and message length. (c) 2014 Wiley Periodicals, Inc. Complexity 20: 25-48, 2015

关键词： Information entropy emergence self-organization complexity natural language artificial language computer code software power law

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Emissivity: A Program for Atomic Transition Calculations

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Communications in Computational Physics 2010年第5期7卷 1118-1130页

作者： Taha Sochi University College London Department of Physics&AstronomyGower StreetLondonWC1E 6BTUK

In this article we report the release of a new program for calculating emissivity and other physical parameters in atomic transition *** program,which can be downloaded with its documentation and a sample of input and output files from ***/***,passed various rigorous tests and was used alongside R-matrix and Autostructure codes to generate theoretical data and analyze observational *** is particularly useful for investigating atomic transition lines in astronomical context as the program is capable of generating a huge amount of theoretical data and comparing it to observational line list.A number of atomic transition algorithms and analytical techniques are implemented within the program and can be very useful in various *** program can be described as fast and ***,it requires modest computational resources.

关键词： Atomic transition recombination autoionization emissivity computer code thermodynamic equilibrium decay routes Saha population

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Locating the ephemeral: capturing the fleeting moment in digital arts

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INTERNATIONAL JOURNAL OF ARTS AND TECHNOLOGY 2009年第1-2期2卷 40-50页

作者： Kaminska, Aleksandra York Univ Toronto ON Canada

The idea of ephemerality is often used to describe digital art and digital artefacts. The impulse behind this paper is to try to understand what exactly we mean when we refer to ephemerality and suggests how we can locate the ephemeral moment in the material construction of the digital artefact. The problematic division between material/immaterial and software/hardware is revisited through the languages and codes that constitute the basis of software. This paper suggests that we can trace ephemerality to moments of translation, the disjunctures of rhythms between various languages and to the reusability of digital materials. The ephemeral is not just a consequence of an immaterial nature ascribed to digital objects or problems of storage. Rather, it emerges from the very material nature of the digital and occurs in the minutiae of its hidden processes that make transmission and communication possible.

关键词： computer code digital aesthetics digital art digital immateriality digital languages digital manipulability digital materiality digital rhythms digital poetics digital temporality ephemerality software languages transcoding

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Calculation of the heat of combustion of hydrocarbon components of fuels

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HIGH TEMPERATURE 2004年第3期42卷 421-425页

作者： Sagadeev, EV Sagadeev, VV Kazan State Acad Architecture & Construct Kazan 420043 Tatarstan Russia Kazan State Univ Technol Kazan 420015 Tatarstan Russia

Development is continued of the empirical method for the calculation of the heat of combustion of organic compounds and, in particular, of hydrocarbons of different structures by the additive scheme based on their che... 详细信息

关键词： combustion, vaporizatiom computer code enthalpy, heat

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Design of an experimental breeder reactor run 138B reactor physics benchmark evaluation management application

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JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 2020年第3期57卷 323-334页

作者： Stewart, Ryan Lum, Edward Pope, Chad Idaho State Univ Nucl Engn Pocatello ID 83209 USA Los Alamos Natl Lab Engn Anal Los Alamos NM USA

Reactor Monte Carlo simulations present numerous challenges including input file generation and processing output files for relevant results. Creating an input file for a heterogeneous core is further complicated when using depleted fuel. Performing perturbations to geometry and material characteristics exacerbates the challenge due to human errors if the input files are manually generated. The difficulty of generating input files is often encountered during the process of performing a reactor physics benchmark evaluation. These challenges were encountered when performing a reactor physics benchmark evaluation for the Experimental Breeder Reactor II (EBR-II), a sodium cooled fast reactor. The EBR-II Monte Carlo input file uses more than 1,000 unique material specifications and similar to 8,000 regions. To address the input file generation challenge, a computer application was designed to automate the input file generation process. The application utilizes user input from a graphical user interface in conjunction with spreadsheets containing material and geometric data to generate Monte Carlo input files. The application, called MICKA, was used to generate input files to support the reactor physics benchmark evaluation for EBR-II. This paper describes the reactor configuration and provides information about the application design and capabilities for addressing challenges often encountered in reactor physics benchmark evaluations.

关键词： Benchmark computer code MCNP reactor physics sodium cooled fast reactor

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Circuit optimization via sequential computer experiments: design of an output buffer

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JOURNAL OF THE ROYAL STATISTICAL SOCIETY SERIES C-APPLIED STATISTICS 1998年第1期47卷 31-48页

作者： Aslett, R Buck, RJ Duvall, SG Sacks, J Welch, WJ Univ Waterloo Dept Stat & Actuarial Sci Waterloo ON N2L 3G1 Canada Intel Corp Hillsboro OR 97124 USA Western Michigan Univ Kalamazoo MI 49008 USA Intel Corp Santa Clara CA 95051 USA Natl Inst Stat Sci Res Triangle Pk NC USA

In electrical engineering, circuit designs are now often optimized via circuit simulation computer models. Typically, many response variables characterize the circuit's performance. Each response is a function of many input variables, including factors that can be set in the engineering design and noise factors representing manufacturing conditions. We describe a modelling approach which is appropriate for the simulator's deterministic input-output relationships. Non-linearities and interactions are identified without explicit assumptions about the functional form. These models lead to predictors to guide the reduction of the ranges of the designable factors in a sequence of experiments. Ultimately, the predictors are used to optimize the engineering design. We also show how a visualization of the fitted relationships facilitates an understanding of the engineering tradeoffs between responses. The example used to demonstrate these methods, the design of a buffer circuit, has multiple targets for the responses, representing different trade-offs between the key performance measures.

关键词： circuit simulator computer code computer model engineering design parameter design stochastic process visualization

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MEASUREMENT AND ANALYSIS OF CADMIUM RATIOS OF ACTIVATION FOILS IN THERMAL CRITICAL ASSEMBLY (KUCA-B-3/8'' P36EU-NU-EU)

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JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 1993年第7期30卷 628-637页

作者： HIRAKAWA, N NARA, H IWASAKI, T MATSUYAMA, S TSUJIMOTO, K KOBAYASHI, K KUDOH, K KYOTO UNIV REACTOR RES INST OSAKA 59004 JAPAN KYUSHU UNIV DEPT NUCL ENGN HIGASHI KU FUKUOKA 812 JAPAN

To examine the applicability of foil activation technique for the estimation of neutron spectrum in a thermal reactor, Cd ratios of 8 activation foils (Au, Th, Dy, In, Mn, W, D.U. and E.U.) were measured in the void at the core center of KUCA B3/8''P36 EU-NU-EU assembly. The Cd ratios were analyzed with SRAC code system using 107 group cross sections based on ENDF/B4. To make the correction for polyethylene plates facing to the void to the calculated spectrum with 2-dimensional (r-z) diffusion model, softening factor calculated with 1-dimensional infinite slab model was introduced. This model gave almost same neutron spectrum as that without this correction. For the model which distributes atoms of Al sheath and support cylinder homogeneously into simulating materials, and using pointwise (fine group) cross sections for Au, Th, W and D.U., the calculated values except for W and D.U. almost agreed with the experimental ones. For W and D. U. C/E values were approximately 1. 1. Since Cd ratios are sensitive to the change in neutron spectrum except for D. U., this method is useful to judge the appropriateness of calculated neutron spectrum.

关键词： THERMAL CRITICAL ASSEMBLIES NEUTRON SPECTRA ACTIVATION FOIL CADMIUM RATIO SELF-SHIELDING TRANSMISSION FACTOR 107-GROUP computer code computer CALCULATION SRAC code ENDF/B4 2-DIMENSIONAL DIFFUSION MODEL SOFTENING FACTOR POLYETHYLENE POINTWISE CALCULATION

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Prediction of uncatalysed calcium bisulphite oxidation under operating conditions relevant to wet flue gas desulphurization plants

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CHEMICAL ENGINEERING RESEARCH & DESIGN 2004年第A7期82卷 927-932页

作者： Pisu, M Cincotti, A Cao, G Pepe, F Univ Cagliari Dipartimento Ingn Chim & Mat I-09123 Cagliari Italy POLARIS Cagliari Italy Univ Sannio Dipartimento Ingn Benevento Italy

W et limestone scrubbing is the most common flue gas desulphurization (FGD) process. In this process, oxidation of calcium bisulphite plays a major role both by determining the dewatering properties of the obtained sludge and the production of gypsum of high quality. In order to contribute to the simulation of the wet limestone FGD process, in the present paper a comprehensive model for isothermal gas-liquid stirred tank reactors has been used. Based on the assumption that the reactions are zeroth order with respect to gaseous reactants, the model requires appropriate physico-chemical parameters which are taken from the literature. The model was used to quantitatively interpret some literature experimental data concerning uncatalysed calcium bisulphite oxidation performed in a continuous stirred tank reactor. In particular, the model is capable of confidently predicting the transition from chemically to mass transfer controlled regime occurring when changing the operating conditions.

关键词： gas-liquid reactors bisulphite oxidation diffusional regime chemically controlled regime modelling computer code

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FLASSH 1.0: Thermal Scattering Law Evaluation and Cross-Section Generation for Reactor Physics Applications

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NUCLEAR SCIENCE AND ENGINEERING 2023年第8期197卷 1887-1901页

作者： Fleming, N. Colby Manring, Cole A. Laramee, Briana K. Crozier, Jonathan P. W. Lee, Eunji Hawari, Ayman I. North Carolina State Univ Dept Nucl Engn Raleigh NC 27695 USA

The Full Law Analysis Scattering System Hub (FLASSH) is a modern, advanced code that evaluates the thermal scattering law (TSL) along with accompanying cross sections. FLASSH features generalized methods that accommodate any material structure. Historical approximations including incoherent and cubic approximations have been removed. Instead, the latest release of FLASSH features advanced physics options including distinct effect corrections (one-phonon contributions) and noncubic formulations. Noncubic elastic and inelastic contributions are necessary to accurately evaluate one-phonon contributions. Both noncubic and one-phonon calculations require high-density sampling of the various scattering directions. Optimization and parallelization of these routines were therefore necessary to produce results in a reasonable computational time frame. With these notable improvements to the generalized TSL, FLASSH 1.0 can meet benchmark requirements by permitting realistic comparisons with experiments for both TSLs and the resulting integrated cross sections. Within FLASSH, these high-fidelity TSLs can be applied also to the resonance region to evaluate accurate, material structure-dependent Doppler broadening that captures the observed experimental behavior. Additional features including a graphical user interface (GUI), plotting diagnostics, and formatted output options including ACE files allow users to complete a TSL evaluation with minimal input and maximum flexibility. The user GUI creates input files for FLASSH, reducing user error and also providing built-in error checks. Autofill options and suggested input values help make TSL evaluation accessible to novice users. The FLASSH code is compiled to run on both Windows and Linux platforms with automatic parallelization.

关键词： FLASSH computer code thermal scattering law neutron evaluation

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