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2 edition of estimated data covariance files of ENDF/B - their uses. found in the catalog.

estimated data covariance files of ENDF/B - their uses.

F G. Perey

estimated data covariance files of ENDF/B - their uses.

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Published by [Brookhaven National Laboratory] in [New York] .
Written in English

Edition Notes

Paper prepared for Cross Section Evaluation Working Group meeting, Brookhaven National Laboratory, 17-19 June, 1974.

ID Numbers
Open LibraryOL20854059M

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estimated data covariance files of ENDF/B - their uses. by F G. Perey Download PDF EPUB FB2

Vi ESTIMATED DATA COVARIANCE FILES OF EVALUATED CROSS SECTIONS - EXAMPLES FOR 2 3 5 U AND 2 3 8u* F. Perey, G. de Saussure and R. Perez Oak Ridge National Laboratory, Oak Ridge, Tennessee ABSTRACT We review the status of development of formats and methods to represent uncertainty information of evaluated microscopic data in the ENDF/B Cited by: 2.

In addition, the impact of different covariance data is studied by comparing two of the presently most complete nuclear data covariance libraries (ENDF/B-VII.1 and SCALE ), which reveals a Author: Donald L. Smith. Comments on Covariance Data of JENDL and ENDF/B-VII.1 Ap M.

Ishikawa, JAEA (From Minutes of SG39 Meeting in Nov. ) C9. Methodology issues • Prepare a list of priority missing covariance data types (see also points C4 and C5) and list of “suspect” low values (file dependent) (Action on M.

Ishikawa). ENDF/B-VII.1 was released on Dec. 22, Many more full evaluations in neutron sublibrary than in any other release • ENDF/B-VII.0 contains evaluations • ENDF/B-VII.1 contains evaluations Extensive collection of covariance data ( evaluations) Library summarized in Dec.

issue of Nuclear Data Sheets. The Low-Fidelity Covariance Project has developed a complete set of covariance data estimates for all ENDF/B-VII.0 isotopes. Covariance data are provided for elastic scattering, inelastic.

Some examples of methods to obtain the data covariances of important cross sections for fertile and fissile nuclides are given.

We give some examples of typical group cross sections covariance matrices obtained by processing the ENDF/B estimated data covariance files. in a meaningful way one needs covariance data for the materials that play significant role in the considered design.

The covariances in ENDF/B-VII.0 are scarce and erratic that makes them inadequate for any application. The ENDF/B-VII.1 will satisfy covariance needs of one particular application - the Advanced Fuel Cycle Initiative (AFCI).

The nuclear data files are read directly by FISPACT-II without any further intermediate processing. Variance and covariance data are processed and used by FISPACT-II to compute uncertainties in collapsed cross sections, and these are in turn used to predict uncertainties in inventories and all derived radiological data.

new ENDF/B-VII.0 data, compared to ENDF/B-VI (see Fig. 23), appear to be supported by these measurements. However, it is worth noting that the uncertainties on the measured data can be large because experiments typi-cally are not able to measure the whole emission energy range because of detector cut-offs, and the unmeasured.

Here we present a methodology to propagate nuclear data covariance information in neutron source calculations from (α,n) reactions. The approach is applied to estimate the uncertainty in the neutron generation rates for uranium oxide fuel types due to uncertainties on 1) 17,18 O(α,n) reaction cross sections and 2) uranium and oxygen stopping.

(vii) Constructing new ENDF/B type data files based on modified reaction theory parameters for use by neutronic designers. Evaluation of Nuclear Physics Parameter Covariances. As indicated in the outline of the methodology, the first step is to provide estimated range of variation of nuclear physics parameters, including their covariance by: 7.

Covariance data The ENDF/B-VII.1 library contains over neutron evaluations with covariances, more than any previous ENDF library. A summary of these covariances is provided in Table I. Notable is the substantial increase of covariance data for structural materials and minor actinides (see Ref.

[4]).File Size: 44MB. These data were never fitted for nuclear astrophysics models and are essentially model-independent.

The product values of the ENDF/B-VII.1 hsMaxw g (30keV)itimes solar abundances [An-ders & Grevesse] are plotted in Fig.

They reveal that the ENDF/B-VII.1 library data closely replicate a two-plateau plot [Rolfs & Rodney1] and Author: Boris Pritychenko. The IAEA contributed to this work with the evaluations of U (in collaboration with IRMM, Belgium), U (in collaboration with ORNL, USA) and the iron isotopes (in collaboration with BNL, USA).

The evaluated nuclear data files were adopted in the ENDF/B-VIII library, which was released in February   This book presents the state of the art in reactor dosimetry as applied to nuclear power plants and to high performance research reactors, accelerator-driven systems and spallation sources.

The reader will also find the latest advances in computer code development for radiation transport and shielding. Integral data testing of ENDF/B fission-product data and comparisons of ENDF/B with other fission product data files: M: View PDF: LAMS: Analysis of ventilation system subjected to explosive transients: far-field analysis: K: View PDF: LAMS: Shipping containers for small samples of high explosives: K: View PDF: LAMS.

The subcritical polyethylene-reflected plutonium (PERP) metal fundamental physics benchmark, which is included in the Nuclear Energy Agency (NEA) International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook, has been selected to serve as a paradigm illustrative reactor physics system for the application of the Second-Order Adjoint Sensitivity Analysis Author: Dan G.

Cacuci, Ruixian Fang, Jeffrey A. Favorite. Co-ordination of the Nuclear Reaction Data Centers Report on an IAEA Advisory Group Meeting hosted by the NEA Data Bank Paris, April Edited by O. Schwerer, C.L. Dunford, H.D. Lemmel July IAEA NUCLEAR DATA SECTION, WAGRAMERSTRASSE 5, A VIENNA.

Full text of "Neutron Thermal Cross Sections, Westcott Factors, Resonance Integrals, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Calculated from Major Evaluated Data Libraries" See other formats. Various new evaluated data libraries, files and programs for data checking, processing and graphical presentation were added to the NDS IAEA Web-site and distributed on CD-ROM: • NuDat for interactive searching and plotting of nuclear structure and decay data • PREPRO ENDF/B Pre-Processing Codes, Novemberupdated June Files and Options are described below.

Their order on the execution line is irrelevant. If there are no changes in default file names, nothing need be entered for Files and Options.

Files MCNP uses several files for input and output. The file names cannot be longer than eight characters. The files pertinent to the sample problem are shown in. The total uncertainty of calculated keff induced by XS data is in our calculation estimated to %.

The additional margin from uncovered sensitivities was determined to be % The similarity assessment identified 9 partly comparable experiments where only one reaches acceptable values of similarity indices. This book gives the state of the art in the field of reactor dosimetry as applied in nuclear power plants and research reactors.

Surveillance programs are presented for nuclear power plants in Europe, including Russia and Ukraine, USA, Argentina and Korea. Perspectives on Nuclear Data fo - OECD OCDE код для вставки. Full text of "Analytical methods for safeguards and accountability measurements of special nuclear materials" See other formats.

вход по аккаунту. doc me. Каталог. ENDF/B-VII Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology Nuclear Data Sheets, vol.pp. [4] D.

KLIR, J. KRAVARIK, P. KUBES, K. REZAC ET AL.: Neutron emission generated during wire-array Z-pinch implosion onto deuterated fiber, Physics of Plasmas,in Size: 16MB. See Appendix E for a list of data modules and their purposes.

which is used to store evaluated nuclear data files, and created the US ENDF/B library that contains the set of data evaluations currently recommended by CSEWG. Each update of the ENDF/B library receives a unique identifier and fluorescence data derived from the ENDF/B-VI.8 data.

Workshop - Free ebook download as PDF File .pdf), Text File .txt) or read book online for free. ENDF-6 Formats Manual Data Formats and Procedures for the Evaluated Nuclear Data File ENDF /B-VI and ENDF /B-VII. SciTech Connect. Herman, M.; Members of the Cross Sections Evaluation Working Group.

In Decemberthe Cross Section Evaluation Working Group (CSEWG) of the United States released the new ENDF /B-VII.0. These sections provide a summary of the conclusions and recommendations that emerged for the following areas: Nuclear Data Needs for Generation IV Nuclear Energy Systems (Section 2); Nuclear Data Processing, Applications, and Validation (Section 3); A working paper on Nuclear Data for Gen IV was submitted by A.

Koning et al. of the Nuclear. To transmit the preevaluated data from the device software to the Project ADE, the exported XML report files are detected and the included data are imported into the entities database using the Data Upload software. Different calculation types of a sample within one measurement series (e.g., method validation) are identified using information.

Data Testing: Critical Experiments Data Testing: Thermal Reactor Lattices Effect of ENDF/B-VI Release 3 for Data Testing: Time-of-Flight Measurements Conclusions and Recommendations Acknowledgements References System Dynamics: An Introduction and Applications to the Nuclear Industry K.F.

Hansen and M.W. Golay 1. The “/B” in ENDF/B is used to indicate the US data library as recommended by CSEWG. (There was at one time an ENDF/A that was a repository for other, possibly useful, data.

However, this is no longer used.) The major version of the library is indicated by a Roman numeral, e.g. INDC(CCP) Distr.: on the basis of the estimated data of various libraries also.

The experimental and calculated values of the group neutron capture cross-sections for niobium and uranium are shown in Table 1. These data were compared with ENDF/B-VI data in terms of the average halflife of the delayed neutron precursors and on.

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We present a data-fusion method that uses a radiograph to provide an estimate of the radiation-transport environment for gamma rays from potential sources. This approach makes quantitative use of radiographic images without relying on image interpretation, and results in a probabilistic description of likely source locations and strengths.

These data were complemented with qualitative diary entries from students (n 1/4 7) who reflected on their learning at different stages of their ESP course. Results point to overall satisfaction with ESP courses and greater awareness of the nature of specialized communication and yield deeper insights into students’ strategies and areas where.

(3) The ENDF/BIV data provides a better fit to the NISUS evaluated spectrometry data than does the SAND-II data. uated spectrometry data is not improved.

The fit to EZ eval- (4) The currently recommended NISUS spectrum is that obtained from SIMMM and shown in Table 3, with the reservation that the value for the energy group keV keV is. A.i,’. CCC MCNPK OAK RIDGE NATIONAL LABORATORY managed by UT-BATTELLE, LLC l-or the U.S.

DEPARTMENT OF ENERGY RSICC COMPUTER CODE COLLECTION MCNP4C Monte Carlo N-Particle Transport Code System Contributed by: Los Alamos National Laboratory Los Alamos, New Mexico RADIATION SAFETY INFORMATION .