ACT-1000. Group activation cross-section library for WWER-1000 type reactors

Energy Technology Data Exchange (ETDEWEB)

Zolotarev, K I; Pashchenko, A B [National Research Centre - A.I. Leipunsky Institute for Physics and Power Engineering, Obninsk (Russian Federation)

2001-10-01

The ACT-1000, a problem-oriented library of group-averaged activation cross-sections for WWER-1000 type reactors, is based on evaluated microscopic cross-section data files. The ACT-1000 data library was designed for calculating induced activity for the main dose-generated nuclides contained in WWER-1000 structural materials. In preparing the ACT-1000 library, 47 group-averaged cross-section data for the 10{sup -9}-17.33 MeV energy range were used to calculate the spatial-energy neutron flux distribution. (author)

12G: code for conversion of isotope-ordered cross-section libraries into group-ordered cross-section libraries

International Nuclear Information System (INIS)

Resnik, W.M. II; Bosler, G.E.

1977-09-01

Many current reactor physics codes accept cross-section libraries in an isotope-ordered form, convert them with internal preprocessing routines to a group-ordered form, and then perform calculations using these group-ordered data. Occasionally, because of storage and time limitations, the preprocessing routines in these codes cannot convert very large multigroup isotope-ordered libraries. For this reason, the I2G code, i.e., ISOTXS to GRUPXS, was written to convert externally isotope-ordered cross section libraries in the standard file format called ISOTXS to group-ordered libraries in the standard format called GRUPXS. This code uses standardized multilevel data management routines which establish a strategy for the efficient conversion of large libraries. The I2G code is exportable contingent on access to, and an intimate familiarization with, the multilevel routines. These routines are machine dependent, and therefore must be provided by the importing facility. 6 figures, 3 tables

Generation of ENDF/B-IV based 35 group neutron cross-section library and its application in criticality studies

International Nuclear Information System (INIS)

Garg, S.B.; Sinha, A.

1985-01-01

A 35 group cross-section library with P/sub 3/-anisotropic scattering matrices and resonance self-shielding factors has been generated from the basic ENDF/B-IV cross-section files for 57 elements. This library covers the neutron energy range from 0.005 ev to 15 MeV and is well suited for the neutronics and safety analysis of fission, fusion and hybrid systems. The library is contained in two well known files, namely, ISOTXS and BRKOXS. In order to test the efficacy of this library and to bring out the importance of resonance self-shielding, a few selected fast critical assemblies representing large dilute oxide and carbide fueled uranium and plutonium based systems have been analysed. These assemblies include ZPPR/sub 2/, ZPR-3-48, ZPR-3-53, ZPR-6-6A, ZPR-6-7, ZPR-9-31 and ZEBRA-2 and are amongst those recommended by the US Nuclear Data Evaluation Working Group for testing the accuracy of cross-sections. The evaluated multiplication constants of these assemblies compare favourably with those calculated by others

ORACLE: an adjusted cross-section and covariance library for fast-reactor analysis

International Nuclear Information System (INIS)

Yeivin, Y.; Marable, J.H.; Weisbin, C.R.; Wagschal, J.J.

1980-01-01

Benchmark integral-experiment values from six fast critical-reactor assemblies and two standard neutron fields are combined with corresponding calculations using group cross sections based on ENDF/B-V in a least-squares data adjustment using evaluated covariances from ENDF/B-V and supporting covariance evaluations. Purpose is to produce an adjusted cross-section and covariance library which is based on well-documented data and methods and which is suitable for fast-reactor design. By use of such a library, data- and methods-related biases of calculated performance parameters should be reduced and uncertainties of the calculated values minimized. Consistency of the extensive data base is analyzed using the chi-square test. This adjusted library ORACLE will be available shortly

Comparison of integral cross section values of several cross section libraries in the SAND-II format

International Nuclear Information System (INIS)

Zijp, W.L.; Nolthenius, H.J.

1976-09-01

A comparison of some integral cross-section values for several cross-section libraries in the SAND-II format is presented. The integral cross-section values are calculated with the aid of the spectrum functions for a Watt fission spectrum, a 1/E spectrum and a Maxwellian spectrum. The libraries which are considered here are CCC-112B, ENDF/B-IV, DETAN74, LAPENAS and CESNEF. These 5 cross-section libraries used have all the SAND-II format. Discrepancies between cross-sections in the different libraries are indicated but not discussed

Testing of a JEF-1 based WIMS-D cross section library for migration area and k-infinity predictions for LWHCR lattices

International Nuclear Information System (INIS)

Pelloni, S.; Stepanek, J.

1987-01-01

The cell code WIMSD4 is used for the analysis of PROTEUS-LWHCR experiments. A library for this code which is based on the European evaluation JEF-1 was produced at EIR using the Los Alamos NJOY system with its module WIMSR and the Canadian management code WILMA. In general, this library delivered more accurate eigenvalues and reaction rates than the WIMS-Standard and WIMS81 libraries did in comparison to experimental values from PROTEUS-LWHCR Cores 1-3. However, large discrepancies (up to about 10%) occured between calculated migration areas (M 2 ). Additional investigations have been undertaken to clarify this problem, since theoretical M 2 -values are needed for deducing k-infinity in the experiments. This has been done in the context of calculations for a reference LWHCR test lattice. The following major reasons for these deviations were found. First, the self-scattering term in non-moderators (P 0 matrix) in the JEF-1 library was not transport corrected. Second, Standard and JEF-1 libraries use infinite dilute cross sections for 238 U, whereas the WIMS81 library uses fully shielded cross sections. Third, the standard library uses the 'row' formula for the transport correction, whereas the 'inflow' formula is applied in the case of JEF-1 and WIMS81 libraries. Lastly, oxygen and 238 U scattering cross sections in the fast energy range are smaller in the case of the WIMS81 library. Differences in calculated k-infinity values between the currently used library and WIMS81 (up to 3%) come (in order of importance for the reference LWHCR lattice) mainly from resonance cross sections for 240 Pu capture, 238 U capture and 239 Pu fission. Recommendations have been made for generating a new JEF-1 library using updated versions of WIMSR and WILMA. (author)

Testing of cross section libraries for TRIGA criticality benchmark

International Nuclear Information System (INIS)

Snoj, L.; Trkov, A.; Ravnik, M.

2007-01-01

Influence of various up-to-date cross section libraries on the multiplication factor of TRIGA benchmark as well as the influence of fuel composition on the multiplication factor of the system composed of various types of TRIGA fuel elements was investigated. It was observed that keff calculated by using the ENDF/B VII cross section library is systematically higher than using the ENDF/B-VI cross section library. The main contributions (∼ 2 20 pcm) are from 235 U and Zr. (author)

Comparison of integral cross section values of several cross section libraries in the SAND-II format

International Nuclear Information System (INIS)

Zijp, W.L.; Nolthenius, H.J.

1978-01-01

A comparison of some integral cross section values for several cross section libraries in the SAND-II format is presented. The integral cross section values are calculated with aid of the spectrum functions for a Watt fission spectrum, a 1/E spectrum and a Maxwellian spectrum. The libraries which are considered here are CCC-112B, ENDF/B-IV, DETAN74, LAPENAS and CESNEF. These 5 cross section libraries used have all the SAND-II format. (author)

Role of ''standard'' fine-group cross section libraries in shielding analysis

International Nuclear Information System (INIS)

Weisbin, C.R.; Roussin, R.W.; Oblow, E.M.; Cullen, D.E.; White, J.E.; Wright, R.Q.

1977-01-01

The Divisions of Magnetic Fusion Energy (DMFE) and Reactor Development and Demonstration (DRDD) of the United States Energy Research and Development Administration (ERDA) have jointly sponsored the development of a 171 neutron, 36 gamma ray group pseudo composition independent cross section library based upon ENDF/B-IV. This library (named VITAMIN-C and packaged by RSIC as DLC-41) is intended to be generally applicable to fusion blanket and LMFBR core and shield analysis. The purpose of this paper is to evaluate this library as a possible candidate for specific designation as a ''standard'' in light of American Nuclear Society standards for fine-group cross section data sets. The rationale and qualification procedure for such a standard are discussed. Finally, current limitations and anticipated extensions to this processed data file are described

Cross-section library and processing techniques within the SCALE system

International Nuclear Information System (INIS)

Westfall, R.M.

1986-01-01

A summary of each of the SCALE system features involved in problem-dependent cross section processing is presented. These features include criticality libraries, shielding libraries, the Standard Composition Library, the SCALE functional modules: BONAMI-S, NITAWL-S, XSDRNPM-S, ICE-S, and the Material Information Processor. The automated procedure for cross-section processing is described with examples. 15 refs

Neutron cross section library production code system for continuous energy Monte Carlo code MVP. LICEM

International Nuclear Information System (INIS)

Mori, Takamasa; Nakagawa, Masayuki; Kaneko, Kunio.

1996-05-01

A code system has been developed to produce neutron cross section libraries for the MVP continuous energy Monte Carlo code from an evaluated nuclear data library in the ENDF format. The code system consists of 9 computer codes, and can process nuclear data in the latest ENDF-6 format. By using the present system, MVP neutron cross section libraries for important nuclides in reactor core analyses, shielding and fusion neutronics calculations have been prepared from JENDL-3.1, JENDL-3.2, JENDL-FUSION file and ENDF/B-VI data bases. This report describes the format of MVP neutron cross section library, the details of each code in the code system and how to use them. (author)

Neutron cross section library production code system for continuous energy Monte Carlo code MVP. LICEM

Energy Technology Data Exchange (ETDEWEB)

Mori, Takamasa; Nakagawa, Masayuki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kaneko, Kunio

1996-05-01

A code system has been developed to produce neutron cross section libraries for the MVP continuous energy Monte Carlo code from an evaluated nuclear data library in the ENDF format. The code system consists of 9 computer codes, and can process nuclear data in the latest ENDF-6 format. By using the present system, MVP neutron cross section libraries for important nuclides in reactor core analyses, shielding and fusion neutronics calculations have been prepared from JENDL-3.1, JENDL-3.2, JENDL-FUSION file and ENDF/B-VI data bases. This report describes the format of MVP neutron cross section library, the details of each code in the code system and how to use them. (author).

ZZ CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for Candu Reactor Fuels

International Nuclear Information System (INIS)

2002-01-01

1 - Historical background and information: - 28-element fuel cross-section library: Format: Designed for use with the ORIGEN-S isotope generation and depletion code. Materials: Co, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Ta, W, Re, Au, Th, Pa, U, Np, Pu, Am, Cm. Origin: ENDSF, ENDF/B-IV, -V and -VI Weighting spectrum: determined using WIMS-AECL transport code. - 37-element fuel cross-section library: Format: Designed for use with the ORIGEN-S isotope generation and depletion code. Materials: Co, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Ta, W, Re, Au, Th, Pa, U, Np, Pu, Am, Cm. Origin: ENDSF, ENDF/B-IV, -V and -VI Weighting spectrum: determined using WIMS-AECL transport code. In 1995, updated ORIGEN-S cross-section libraries were created as part of a program to upgrade and standardize the computer codes and nuclear data employed for used fuel characterization. This effort was funded through collaboration between Atomic Energy of Canada Limited and the Canadian Nuclear Power Utilities, under the Candu Owners Group (COG). The updated cross sections were generated using the WIMS-AECL lattice code and ENDF/B-V and -VI based data to provide cross section consistency with reactor physics codes. 2 - Application of the data: The libraries in this data collection are designed for characterising used fuel from Candu pressurized heavy water reactors. Two libraries are provided: one for the standard 28-element fuel bundle design, the other for the 37-element fuel bundle design. The libraries were generated for typical reactor operating conditions. The libraries are designed for use with the ORIGEN-S isotope generation and depletion code. 3 - Source and scope of data: The Candu libraries are updated with cross sections from a variety of different sources. Capture

Specifications for adjusted cross section and covariance libraries based upon CSEWG fast reactor and dosimetry benchmarks

International Nuclear Information System (INIS)

Weisbin, C.R.; Marable, J.H.; Collins, P.J.; Cowan, C.L.; Peelle, R.W.; Salvatores, M.

1979-06-01

The present work proposes a specific plan of cross section library adjustment for fast reactor core physics analysis using information from fast reactor and dosimetry integral experiments and from differential data evaluations. This detailed exposition of the proposed approach is intended mainly to elicit review and criticism from scientists and engineers in the research, development, and design fields. This major attempt to develop useful adjusted libraries is based on the established benchmark integral data, accurate and well documented analysis techniques, sensitivities, and quantified uncertainties for nuclear data, integral experiment measurements, and calculational methodology. The adjustments to be obtained using these specifications are intended to produce an overall improvement in the least-squares sense in the quality of the data libraries, so that calculations of other similar systems using the adjusted data base with any credible method will produce results without much data-related bias. The adjustments obtained should provide specific recommendations to the data evaluation program to be weighed in the light of newer measurements, and also a vehicle for observing how the evaluation process is converging. This report specifies the calculational methodology to be used, the integral experiments to be employed initially, and the methods and integral experiment biases and uncertainties to be used. The sources of sensitivity coefficients, as well as the cross sections to be adjusted, are detailed. The formulae for sensitivity coefficients for fission spectral parameters are developed. A mathematical formulation of the least-square adjustment problem is given including biases and uncertainties in methods

Multigroup cross section library; WIMS library

International Nuclear Information System (INIS)

Kannan, Umasankari

2000-01-01

The WIMS library has been extensively used in thermal reactor calculations. This multigroup constants library was originally developed from the UKNDL in the late 60's and has been updated in 1986. This library has been distributed with the WIMS-D code by NEA data bank. The references to WIMS library in literature are the 'old' which is the original as developed by the AEA Winfrith and the 'new' which is the current 1986 WIMS library. IAEA has organised a CRP where a new and fully updated WIMS library will soon be available. This paper gives an overview of the definitions of the group constants that go into any basic nuclear data library used for reactor calculations. This paper also outlines the contents of the WIMS library and some of its shortcomings

ZZ ANSLV, Multigroup Cross Sections Library for ANS Reactor Design Studies

International Nuclear Information System (INIS)

2000-01-01

a proposed reactor which would be fueled with highly enriched uranium and cooled with heavy water. The libraries, designated ANSL-V (Advanced Neutron Source Cross Section Libraries based on ENDF/B-V) are data based in AMPX master format. Although the ANS project was canceled, the libraries are being released because they may be utilized in other applications. ANSL-V data are to be used for the subsequent generation of problem-dependent fine- and/or broad-group cross sections for a wide range of applications, such as core and shield analysis, activation analyses after irradiation of certain elements in the reactor environment, and safety analyses. Problem-dependent cross sections can be derived from the ANSL-V data with AMPX modules included in PSR-0315/AMPX-77, PSR-0352/SCAMPI, or CCC-0545/SCALE-4.3 packages. The derived data libraries in either ANISN or AMPX working library format can be used with codes such as KENO, ANISN, XSDRNPM, DORT, TORT, MORSE. B - Method of solution: ANSL-V consists of the following fine and broad groups: 1. Fine Group (99 energy groups) General Purpose Neutron Library (FGGPN); 2. Broad Group (39 energy groups) General Purpose Neutron Library (BGGPN); 3. Gamma-Ray Interaction (GRI) Library containing data in 44-group gamma-ray structure. 4. Coupled Library containing (CNG) 99-group neutron and 44-group gamma-ray data. 5. Coupled neutron-gamma (CNG) Library containing 39-group, and 44-group gamma-ray data. Neutron and secondary gamma-ray production data in the ANSL-V library were generated primarily from evaluations in the ENDF/B-V General Purpose Library. Where evaluations for specified materials were not available in the ENDF/B-V library, ANSL-V GPN and SGRP data sets were generated from evaluations from other ENDF-formatted libraries. Gamma-ray interaction data sets were generated from evaluations in the ENDF/B-V Photon Interaction Library (DLC-0099/ZZ-HUGO). Because some important materials in the ENDF/B-V library do not have gamma

AFCI-2.0 Neutron Cross Section Covariance Library

Energy Technology Data Exchange (ETDEWEB)

Herman, M.; Herman, M; Oblozinsky, P.; Mattoon, C.M.; Pigni, M.; Hoblit, S.; Mughabghab, S.F.; Sonzogni, A.; Talou, P.; Chadwick, M.B.; Hale, G.M.; Kahler, A.C.; Kawano, T.; Little, R.C.; Yount, P.G.

2011-03-01

The cross section covariance library has been under development by BNL-LANL collaborative effort over the last three years. The project builds on two covariance libraries developed earlier, with considerable input from BNL and LANL. In 2006, international effort under WPEC Subgroup 26 produced BOLNA covariance library by putting together data, often preliminary, from various sources for most important materials for nuclear reactor technology. This was followed in 2007 by collaborative effort of four US national laboratories to produce covariances, often of modest quality - hence the name low-fidelity, for virtually complete set of materials included in ENDF/B-VII.0. The present project is focusing on covariances of 4-5 major reaction channels for 110 materials of importance for power reactors. The work started under Global Nuclear Energy Partnership (GNEP) in 2008, which changed to Advanced Fuel Cycle Initiative (AFCI) in 2009. With the 2011 release the name has changed to the Covariance Multigroup Matrix for Advanced Reactor Applications (COMMARA) version 2.0. The primary purpose of the library is to provide covariances for AFCI data adjustment project, which is focusing on the needs of fast advanced burner reactors. Responsibility of BNL was defined as developing covariances for structural materials and fission products, management of the library and coordination of the work; LANL responsibility was defined as covariances for light nuclei and actinides. The COMMARA-2.0 covariance library has been developed by BNL-LANL collaboration for Advanced Fuel Cycle Initiative applications over the period of three years, 2008-2010. It contains covariances for 110 materials relevant to fast reactor R&D. The library is to be used together with the ENDF/B-VII.0 central values of the latest official release of US files of evaluated neutron cross sections. COMMARA-2.0 library contains neutron cross section covariances for 12 light nuclei (coolants and moderators), 78 structural

AFCI-2.0 Neutron Cross Section Covariance Library

International Nuclear Information System (INIS)

Herman, M.; Oblozinsky, P.; Mattoon, C.M.; Pigni, M.; Hoblit, S.; Mughabghab, S.F.; Sonzogni, A.; Talou, P.; Chadwick, M.B.; Hale, G.M.; Kahler, A.C.; Kawano, T.; Little, R.C.; Yount, P.G.

2011-01-01

The cross section covariance library has been under development by BNL-LANL collaborative effort over the last three years. The project builds on two covariance libraries developed earlier, with considerable input from BNL and LANL. In 2006, international effort under WPEC Subgroup 26 produced BOLNA covariance library by putting together data, often preliminary, from various sources for most important materials for nuclear reactor technology. This was followed in 2007 by collaborative effort of four US national laboratories to produce covariances, often of modest quality - hence the name low-fidelity, for virtually complete set of materials included in ENDF/B-VII.0. The present project is focusing on covariances of 4-5 major reaction channels for 110 materials of importance for power reactors. The work started under Global Nuclear Energy Partnership (GNEP) in 2008, which changed to Advanced Fuel Cycle Initiative (AFCI) in 2009. With the 2011 release the name has changed to the Covariance Multigroup Matrix for Advanced Reactor Applications (COMMARA) version 2.0. The primary purpose of the library is to provide covariances for AFCI data adjustment project, which is focusing on the needs of fast advanced burner reactors. Responsibility of BNL was defined as developing covariances for structural materials and fission products, management of the library and coordination of the work; LANL responsibility was defined as covariances for light nuclei and actinides. The COMMARA-2.0 covariance library has been developed by BNL-LANL collaboration for Advanced Fuel Cycle Initiative applications over the period of three years, 2008-2010. It contains covariances for 110 materials relevant to fast reactor R and D. The library is to be used together with the ENDF/B-VII.0 central values of the latest official release of US files of evaluated neutron cross sections. COMMARA-2.0 library contains neutron cross section covariances for 12 light nuclei (coolants and moderators), 78

ANSL-V: ENDF/B-V based multigroup cross-section libraries for Advanced Neutron Source (ANS) reactor studies. Supplement 1

Energy Technology Data Exchange (ETDEWEB)

Wright, R.Q.; Renier, J.P.; Bucholz, J.A.

1995-08-01

The original ANSL-V cross-section libraries (ORNL-6618) were developed over a period of several years for the physics analysis of the ANS reactor, with little thought toward including the materials commonly needed for shielding applications. Materials commonly used for shielding applications include calcium barium, sulfur, phosphorous, and bismuth. These materials, as well as {sup 6}Li, {sup 7}Li, and the naturally occurring isotopes of hafnium, have been added to the ANSL-V libraries. The gamma-ray production and gamma-ray interaction cross sections were completely regenerated for the ANSL-V 99n/44g library which did not exist previously. The MALOCS module was used to collapse the 99n/44g coupled library to the 39n/44g broad- group library. COMET was used to renormalize the two-dimensional (2- D) neutron matrix sums to agree with the one-dimensional (1-D) averaged values. The FRESH module was used to adjust the thermal scattering matrices on the 99n/44g and 39n/44g ANSL-V libraries. PERFUME was used to correct the original XLACS Legendre polynomial fits to produce acceptable distributions. The final ANSL-V 99n/44g and 39n/44g cross-section libraries were both checked by running RADE. The AIM module was used to convert the master cross-section libraries from binary coded decimal to binary format (or vice versa).

Generation of broad-group neutron/photon cross-section libraries for shielding applications

International Nuclear Information System (INIS)

Ingersoll, D.T.; Roussin, R.W.; Fu, C.Y.; White, J.E.

1989-01-01

The generation and use of multigroup cross-section libraries with broad energy group structures is primarily for the economy of computer resources. Also, the establishment of reference broad-group libraries is desirable in order to avoid duplication of effort, both in terms of the data generation and verification, and to assure a common data base for all participants in a specific project. Uncertainties are inevitably introduced into the broad-group cross sections due to approximations in the grouping procedure. The dominant uncertainty is generally with regard to the energy weighting function used to average the pointwise or fine-group data within a single broad group. Intelligent choice of the weighting functions can reduce such uncertainties. Also, judicious selection of the energy group structure can help to reduce the sensitivity of the computed responses to the weighting function, at least for a selected set of problems. Two new multigroup cross section libraries have been recently generated from ENDF/B-V data for two specific shielding applications. The first library was prepared for use in sodium-cooled reactor systems and is available in both broad-group structures. The second library, just recently completed, was prepared for use in air-over-ground environments and is available in a broad-group (46-neutron, 23-photon) energy structure. The selection of the specific group structures and weighting functions was an important part of the generation of both libraries

Neutron cross-section library for SAND-2 and its service program

International Nuclear Information System (INIS)

Berzonis, M.A.; Bondars, Kh.Ya.; Lapenas, A.A.

1978-01-01

The logical structure of the neutron cross-section library used in the SAND-2 program complex is considered. The organization of the DSIG01 program creating and servicing the neutron cross section library is described. The DSIG 01 program is written on FORTRAN and permits to create the neutron cross section library on the ES computer magnetic discs operating under the control of the ES operating system and to perform certain manipulations therewith

SHAMSI, 48 group cross-section library for fusion nucleonics analysis

International Nuclear Information System (INIS)

Ponti, C.; Abbas, Tayyab.

1982-01-01

A P 3 48 group coupled neutron gamma-ray (34 N - 14 G) cross-section library is produced and validated for neutronic studies in fusion reactor blanket/shield. This report describes the library content, the procedure adopted and the results of the calculations performed for testing the cross sections

Basis calculation of phase cross section library in a low power fast reactor neutronic simulation

International Nuclear Information System (INIS)

Jachic, J.

1993-09-01

In order to implement the utilization of the efficient multidimensional cubic SPLINE interpolation, we determine the phase library bases for net like relevant state components. A generic cubic surface and a weighted plane pertinent alternative interpolating methods used capable to generate cross sections values for fixed coordinates from cell code calculated data points is used. It is verified that the phase library bases increases or decrease smoothly and monotonically with the spectrum asymmetry and total flux buckling. This justifies its use in cross section updating avoiding cell calculations. (author)

Remarks on the comparison of cross section libraries for neutron metrology

International Nuclear Information System (INIS)

Zijp, W.L.; Nolthenius, H.J.; Appelman, K.H.

1977-01-01

Cross section libraries in a 620 group structure were available from different origin: CCC-112B, DETAN-74 and ENDF/B-IV. For a few well known neutron spectra (CFRMF spectrum, ΣΣ spectrum, fission neutron spectrum, HFR neutron spectrum) a comparison was made of the available experimental reaction rates in foil detectors and the reaction rates as calculated with the different cross section libraries. This investigation is dealing with the consistency of cross section data within a library, and the consistency of activity data in actual reaction rate determinations. Some preliminary conclusions are given

Status of standard cross section library and future plan

International Nuclear Information System (INIS)

Zukeran, Atsushi

2001-01-01

JSSTDL-300 multi-group cross section library with 300 neutron energy groups coupled with 104 group γ-ray cross sections was developed for general users in nuclear reactor physics and/or design, whose source data is the evaluated nuclear data library JENDL-3.2. For the purpose of a standard or common use, several famous cross section libraries worldwide used, i.e., ABBN-25, GAM-123, VITAMIN-C/J(E+C), MGCL-137, BERMUDA-12 and FNS-125 for neutron, and LANL-12, -24-, -48, and CSEWG-94 for γ-ray, are consulted about setting the common energy group structure. Furthermore, in order to expand the applicability, the top energy is set on 20 MeV and the lowest energy is 10 -5 eV. In the thermal neutron energy region, the JSSTDL-300 has about 20 energy groups. Besides, many utility codes for group collapsing and for data format transformation are provided for general users. (author)

ARP: A PC-compatible scheme for generating ORIGEN-S cross section library

International Nuclear Information System (INIS)

Leal, L.C.; Hermann, O.W.; Parks, C.V.

1995-01-01

The SAS2H sequence of the SCALE code system has been widely used for treating problems related to the characterization of nuclear systems for disposal, storage, and shipment. The calculations, in general, consist of determining the isotope compositions of the different materials present in the problem as a function of time, which subsequently enable determination of the heat generation and radiation source terms. In the SAS2H scheme, time-dependent material concentrations are obtained using the ORIGEN-S code based on a point-depletion calculation that utilizes problem-dependent cross-section libraries generated by distinct codes of the SAS2H sequence. In this paper we will be concerned with the methodology utilized in the SAS2H control module to create cross-section libraries for point-depletion calculations with the ORIGEN-S code. A brief description of the SAS2H scheme will be given, and a new capability, the automatic rapid processing (ARP), for generating problem-dependent ORIGEN-S cross-section libraries will be presented. Use of ARP can enable execution of ORIGEN-S on a personal computer with identical accuracy to that obtained with SAS2H

BARC 75 - A 75 group neutron-photon coupled cross-section library with P5- anisotropic scattering matrices

International Nuclear Information System (INIS)

Garg, S.B.

1990-01-01

A 75 group neutron-photon coupled cross-section library has been developed for 42 reactor nuclides utilizing the basic cross-section files - ENDF/B-IV for neutrons and DLC-7F for photons. 50 neutron energy groups and gamma energy groups are included in this library which should be well suited to carry out safety, shielding and core physics studies of nuclear reactors based on fission or fusion processes. This library is also adequate for oil logging and mineral exploration investigations. (author). 11 refs., 3 tabs

Improvement of decay and cross-section data libraries for activation calculations

International Nuclear Information System (INIS)

Attaya, H.

1993-01-01

A new decay data library has been completed. The new library contains up-to-date decay information (half-lives, branching ratios, decay energies, γ's energies and intensities). Activation responses such as the air and water biological hazard potentials, the waste disposal rating, and the biological dose are also included in this library. Recently developed cross-section libraries have been acquired to be used together with the decay data library

Energy-balance check for continuous energy cross section library CENACE-1.0

International Nuclear Information System (INIS)

Zhao Qiujuan; Wu Haicheng; Ge Zhigang

2014-01-01

In order to verify the reliability of the multiple-temperature continuous energy cross section library CENACE-1.0 when used for calculating nuclear heating in reactor core, NJOY99/HEATR module and auxiliary code chkACEheat developed locally were used to perform energy-balance check for all materials in the library. The test results show that the pass rate of KERMA factors and heat production cross sections of the CENACE-1.0 library is better than that of the other ACE libraries used as comparison. However, unreasonable KERMA factors still exist in various evaluation libraries, and methods to directly revise the calculation results of KERMA factors need to be developed. (authors)

New evaluated neutron cross section libraries for the GEANT4 code

International Nuclear Information System (INIS)

Mendoza, E.; Cano-Ott, D.; Guerrero, C.; Capote, R.

2012-04-01

The so-called High Precision neutron physics model implemented in the GEANT4 simulation package allows simulating the transport of neutrons with energies up to 20 MeV. It relies on the G4NDL cross section libraries, prepared by the GEANT4 collaboration from evaluated cross section files and distributed freely together with the code. Even though the performance of the G4NDL library has been improved over the time, users running complex simulations which involve the transport of neutrons do need more flexibility, in particular when assessing the uncertainties in the simulation results due to the neutron (and hence the nuclear) data library used. For this reason, a software tool has been developed for transforming any evaluated neutron cross section library in the ENDF-6 format into the G4NDL format. Furthermore, eight different releases of ENDF-B, JEFF, JENDL, CENDL and BROND national libraries have been translated into the G4NDL format and are distributed by the IAEA nuclear data service at www-nds.iaea.org/geant4. In this way, GEANT4 users have access to the complete list of standard evaluated neutron data libraries when performing Monte Carlo simulations with GEANT4. Consistency checks and a first validation of the libraries have been made following the methods described in this report. (author)

Up to date cross sections library for Thermos and Record codes

International Nuclear Information System (INIS)

Hernandez Lopez, H.

1993-01-01

Reactor cell analysis is the first step in determining reactor core behavior and is required in the reload licensing process. For best results, reactor cell analysis should be carried out with libraries of up to date, accurate cross sections produced with well described methods from standard evaluated nuclear data. At first step in this work were determined the library structure for RECORD and THERMOS and were prepared the cross sections libraries using the NJOY nuclear data processing system and the ENDF-B/IV evaluated nuclear data. These libraries were used by the codes and some samples were perform, the result show some differences against the results obtained using the previous libraries. By other hand the libraries contain various adjustments to correct for deficiencies in nuclear data or analytical methods. These adjustments doesn't have any documentation, although some of them were identified in this work. (Author). 25 refs, 78 figs, 55 tabs

ENEA-Bologna production and testing of JEF-2.2 multi-group cross section libraries for nuclear fission applications

International Nuclear Information System (INIS)

Pescarini, M.; Orsi, R.; Martinelli, T.; Sinitsa, V.; Blokhin, A.I.

2005-01-01

The ENEA-Bologna Nuclear Data Group produced the VITJEF22.BOLIB (NEA-1699/01 ZZ VITJEF22.BOLIB) and MATJEF22.BOLIB (NEA-1740/01 ZZ MATJEF22.BOLIB) fine-group coupled neutron and photon (199 n + 42 γ) cross section libraries for nuclear fission applications, respectively in AMPX and MATXS format and based on the JEF-2.2 European nuclear data file. Both the libraries were produced from the same set of cross section files in GENDF format, generated with the NJOY-94.66 nuclear data processing system. The present libraries can be considered as European counterparts of the VITAMIN-B6 (DLC-0184 ZZ VITAMIN-B6) American library in AMPX format, based on the ENDF/B-VI Release 3 American nuclear data file. In fact they have the same general features and the same neutron and photon energy group structures as VITAMIN-B6. In particular, all these libraries are pseudo-problem-independent and based on the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. Each ENEA-Bologna library contains a set of 133 nuclide cross section files processed at 4 temperatures (300 K, 600 K, 1000 K and 2100 K) and obtained for the most part with 6 to 8 values of the background cross section σ 0 . Thermal scattering cross sections were processed at all the temperatures available in the JEF-2.2 thermal scattering law data file for 5 additional bound nuclides: H-1 in light water, H-1 in polyethylene, H-2 in heavy water, C in graphite and Be in beryllium metal. Collapsed working libraries of self-shielded cross sections in the formats used by the deterministic transport codes of the DANTSYS and DOORS systems can be generated from VITJEF22.BOLIB and MATJEF22.BOLIB through, respectively, further problem-dependent data processing with the AMPX or SCAMPI nuclear data processing systems and with the TRANSX code. (authors)

Nuclear cross section library for oil well logging analysis

International Nuclear Information System (INIS)

Kodeli, I.; Kitsos, S.; Aldama, D.L.; Zefran, B.

2003-01-01

As part of the IRTMBA (Improved Radiation Transport Modelling for Borehole Applications) Project of the EU Community's 5 th Programme a special purpose multigroup cross section library to be used in the deterministic (as well as Monte Carlo) oil well logging particle transport calculations was prepared. This library is expected to improve the prediction of the neutron and gamma spectra at the detector positions of the logging tool, and their use for the interpretation of the neutron logging measurements was studied. Preparation and testing of this library is described. (author)

National Libraries Section. General Research Libraries Division. Papers.

Science.gov (United States)

International Federation of Library Associations, The Hague (Netherlands).

Papers on national library services and activities, which were presented at the 1983 International Federation of Library Associations (IFLA) conference, include: (1) "The National Library of China in its Gradual Application of Modern Technology," a discussion by Zhu Nan and Zhu Yan (China) of microform usage and library automation; (2)…

Library of neutron cross sections of the Thermos code

International Nuclear Information System (INIS)

Alonso V, G.; Hernandez L, H.

1991-10-01

The present work is the complement of the IT.SN/DFR-017 report in which the structure and the generation of the library of the Thermos code is described. In this report the comparison among the values of the cross sections that has the current library of the Thermos code and those generated by means of the ENDF-B/NJOY it is shown. (Author)

A computer program with graphical user interface to plot the multigroup cross sections of WIMS-D library

International Nuclear Information System (INIS)

Thiyagarajan, T.K.; Ganesan, S.; Jagannathan, V.; Karthikeyan, R.

2002-01-01

As a result of the IAEA Co-ordinated Research Programme entitled 'Final Stage of the WIMS Library Update Project', new and updated WIMS-D libraries based upon ENDF/B-VI.5, JENDL-3.2 and JEF-2.2 have become available. A project to prepare an exhaustive handbook of WIMS-D cross sections from old and new libraries has been taken up by the authors. As part of this project, we have developed a computer program XnWlup with user-friendly graphical interface to help the users of WIMS-D library to enable quick visualization of the plots of the energy dependence of the multigroup cross sections of any nuclide of interest. This software enables the user to generate and view the histogram of 69 multi-group cross sections as a function of neutron energy under Microsoft Windows environment. This software is designed using Microsoft Visual C++ and Microsoft Foundation Classes Library. The current features of the software, on-line help manual and future plans for further development are described in this paper

VITAMIN E: a multipurpose ENDF/B-V coupled neutron-gamma cross section library

International Nuclear Information System (INIS)

Barhen, J.; Cacuci, D.G.; Ford, W.E. III; Roussin, R.W.; Wagschal, J.J.; Weisbin, C.R.; White, J.E.; Wright, R.Q.

1979-01-01

The US Department of Energy Office of Fusion Energy and the Division of Reactor Research and Technology jointly sponsored the development of a coupled fine-group cross section library (VITAMIN-C). The experience gained in the generation, validation, and utilization of the VITAMIN-C library along with its broad range of applicability has led to the request for updating this data set using ENDF/B-V. Additional support in this regard has been provided by the Defense Nuclear Agency (DNA) and by EPRI in support of weapons analyses and light water reactor shielding and dosimetry problems, respectively. The rationale for developing the multipurpose ENDF/B-V-based VITAMIN-E library is presented, with special emphasis on new models used in the data generation algorithms. The library specifications and testing procedures are also discussed in detail. The distribution of the VITAMIN-E library is currently subject to the same restrictions as the distribution of the ENDF/B-V data. 2 tables

How to Use Benchmark and Cross-section Studies to Improve Data Libraries and Models

Science.gov (United States)

Wagner, V.; Suchopár, M.; Vrzalová, J.; Chudoba, P.; Svoboda, O.; Tichý, P.; Krása, A.; Majerle, M.; Kugler, A.; Adam, J.; Baldin, A.; Furman, W.; Kadykov, M.; Solnyshkin, A.; Tsoupko-Sitnikov, S.; Tyutyunikov, S.; Vladimirovna, N.; Závorka, L.

2016-06-01

Improvements of the Monte Carlo transport codes and cross-section libraries are very important steps towards usage of the accelerator-driven transmutation systems. We have conducted a lot of benchmark experiments with different set-ups consisting of lead, natural uranium and moderator irradiated by relativistic protons and deuterons within framework of the collaboration “Energy and Transmutation of Radioactive Waste”. Unfortunately, the knowledge of the total or partial cross-sections of important reactions is insufficient. Due to this reason we have started extensive studies of different reaction cross-sections. We measure cross-sections of important neutron reactions by means of the quasi-monoenergetic neutron sources based on the cyclotrons at Nuclear Physics Institute in Řež and at The Svedberg Laboratory in Uppsala. Measurements of partial cross-sections of relativistic deuteron reactions were the second direction of our studies. The new results obtained during last years will be shown. Possible use of these data for improvement of libraries, models and benchmark studies will be discussed.

C4P cross-section libraries for safety analyses with SIMMER and related studies

International Nuclear Information System (INIS)

Rineiski, A.; Sinitsa, V.; Gabrielli, F.; Maschek, W.

2011-01-01

A code and data system, C 4 P, is under development at KIT. It includes fine-group master libraries and tools for generating problem-oriented cross-section libraries, primarily for safety studies with the SIMMER code and related analyses. In the paper, the 560-group master library and problem oriented 40-group and 72-group cross-section libraries, for thermal and fast systems, respectively, are described and their performances are investigated. (author)

FCXSEC: multigroup cross-section libraries for nuclear fuel cycle shielding calculations

International Nuclear Information System (INIS)

Ford, W.E. III; Webster, C.C.; Diggs, B.R.; Pevey, R.E.; Croff, A.G.

1980-05-01

Starting with the pseudo-composition-independent VITAMIN-C cross-sectin library, composition-dependent fine-(171n-36γ) and broad-group (22n-21γ) self-shielded AMPX master, broad-group microscopic ANISN-formatted, and broad-group macroscopic ANISN-formatted cross-section libraries were generated to be used for nuclear fuel cycle shielding calculations. The specifications for the data and the procedure used to prepare the libraries are described

Comparative analysis of the neutron cross-sections of iron from various evaluated data libraries

International Nuclear Information System (INIS)

Bychkov, V.M.; Vozyakov, V.V.; Manokhin, V.N.; Smoll, F.; Resner, P.; Seeliger, D.; Hermsdorf, D.

1983-09-01

The comparative analysis of neutron cross-sections of iron from evaluated nuclear data libraries SOKRATOR, KEDAK, ENDL is done in energy interval from 0.025 eV to 20 MeV. Some of iron cross-sections from SOKRATOR library are revised and new data, which are obtained by using new experimental data and more comprehensive theoretical methods, are recommended. As a result the new version of the iron neutron cross-section file (BNF-2012) is produced for SOKRATOR library. (author)

Index of Nuclear Data Libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1994-01-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, or through the online Nuclear Data Information System (NDIS). (author)

Analysis of benchmark experiments for testing the IKE multigroup cross-section libraries based on ENDF/B-III and IV

International Nuclear Information System (INIS)

Keinert, J.; Mattes, M.

1975-01-01

Benchmark experiments offer the most direct method for validation of nuclear cross-section sets and calculational methods. For 16 fast and thermal critical assemblies containing uranium and/or plutonium of different compositions we compared our calculational results with measured integral quantities, such as ksub(eff), central reaction rate ratios or fast and thermal activation (dis)advantage factors. Cause of the simple calculational modelling of these assemblies the calculations proved as a good test for the IKE multigroup cross-section libraries essentially based on ENDF/B-IV. In general, our calculational results are in excellent agreement with the measured values. Only with some critical systems the basic ENDF/B-IV data proved to be insufficient in calculating ksub(eff), probably due to Pu neutron data and U 238 fast capture cross-sections. (orig.) [de

ZZ TEMPEST/MUFT, Thermal Neutron and Fast Neutron Multigroup Cross-Section Library for Program LEOPARD

International Nuclear Information System (INIS)

Kim, Jung-Do; Lee, Jong Tai

1986-01-01

Description of problem or function: Format: TEMPEST and MUFT; Number of groups: 246 thermal groups in TEMPEST Format and 54 fast groups in MUFT Format. From this library, the program SPOTS4 generates a 172-54 group library as input to the code LEOPARD. Nuclides: H, O, Zr, C, Fe, Ni, Al, Cr, Mn, U, Pu, Th, Pa, Xe, Sm, B and D. Origin: ENDF/B-4; Weighting spectrum: 1/E + U 235 fission spectrum. Data library of thermal and fast neutron group Cross sections to generate input to the program LEOPARD. The data is based on ENDF/B-4 and consists of two parts: (1) 246 thermal groups in TEMPEST Format. (2) 54 fast groups in MUFT Format. From this library, the program SPOTS4 generates a 172-54 group library as input to the code LEOPARD (NESC0279)

XNWLUP, Graphical user interface to plot WIMS-D library multigroup cross sections

International Nuclear Information System (INIS)

Ganesan, S.; Jagannathan, V.; Thiyagarajan, T.K.

2005-01-01

1 - Description of program or function: XnWlup is a computer program with user-friendly graphical interface to help the users of WIMS-D library to enable quick visualisation of the plots of the energy dependence of the multigroup cross sections of any nuclide of interest. This software enables the user to generate and view the histogram of 69 multi-group cross sections as a function of neutron energy under Microsoft Windows environment. This software is designed using Microsoft Visual C++ and Microsoft Foundation Classes Library. IAEA1395/05: New features of version 3.0: - Plotting absorption and fission cross sections of resonant nuclide after applying the self-shielding cross section. - Plotting the data of Resonant Integral table, as a function of dilution cross section for a selected temperature and for a given energy group. - Plotting the data of Resonant Integral table, as a function of temperature for a selected background dilution cross section and for a given energy group. - Clearing all the graphs except one graph from the display screen is easily done by using a tool bar button. - Displaying the coordinate of the cursor point with appropriate units. 2 - Methods: XnWlup helps to obtain histogram plots of the values of cross section data of an element/isotope available as 69-group WIMS-D library as a function of energy bins. The software XnWlup is developed with this graphical user interface in order to help those users who frequently refer to the WIMS-D library cross section data of neutron-nuclear reactions. The software also helps to produce handbook of WIMS-D cross sections

TOPICS-B, Neutron and Gamma Cross-Sections Library Handling in FIDO Format

International Nuclear Information System (INIS)

Wasastjerna, Frej

2003-01-01

1 - Description of program or function: The program is intended to manipulate working format neutron and/or gamma cross section libraries, carrying out such operations as mixing materials, deleting unneeded groups, inserting response cross sections or whatever the user may require. It has been designed to make it easy to include new modules to cope with new requirements. The cross section libraries involved should preferably be in ANISN format, but if they are not, this too can be handled by adding new modules as needed. This program is intended to supersede TOPICS (NEA-1406). TOPICS was intended for interactive use, but experience has shown that using it is somewhat difficult. Therefore it was redesigned for batch use (the input is written to a file and the program is then run using that file, instead of reading input directly from the keyboard). 2 - Method of solution: Each required operation is performed by a separate module (a set of subprograms). 3 - Restrictions on the complexity of the problem: Essentially none, variable dimensioning is used. However, TOPICS-B is not intended to be applied to basic nuclear data libraries (such as the ENDF/B series) or to flexible format libraries (e.g., the VITAMIN series). It is intended only for working format libraries like the BUGLE series

Description of the ENDF-NJOY system for the generation of cross sections libraries

International Nuclear Information System (INIS)

Alonso V, G.

1991-01-01

The physics of nuclear reactors requires of a great number of data to be able to evaluate the different phenomena that happen in a nuclear reactor; these data are mainly the microscopic neutron cross sections, but it is also required of data of radioactive decay and of nuclear structure for a great number of materials as well as of the cross sections of the photons and the production of these for the neutron interaction. These data group in nuclear databases, being the main ones: ENDF Nuclear Evaluated File, ENDL Dates Nuclear Evaluated Library it Dates (of the Laboratory Lawrence Livermore). JENDL Japanese Nuclear Evaluated Library Dates. Soviet SOKRATOR Nuclear Evaluated KEDAF Nuclear Karlsruhe File Dates. JEF Join Evaluated File (coordinated by NEA Data Bank). The existent codes that execute neutron and photon calculations require libraries of data that are very different some of other and of the databases. Of here that it is required of a series of processing codes that use the database like enter and its generate a secondary library of cross sections, which is read as enter for a code of spectra generation. Generally average cross sections by group are obtained; this library is that it is used in the codes that execute neutron calculations. (Author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1982-02-01

This document lists more than 50 nuclear data libraries together with references that give more detailed information about these libraries. All data and documentation references are available, free of charge, from the IAEA Nuclear Data Section. (author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1984-12-01

This document lists more than 50 nuclear data libraries together with references that give more detailed information about these libraries. All data and documentation references are available, free of charge, from the IAEA Nuclear Data Section. (author)

Index of Nuclear Data Libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1993-01-01

This document lists more than 80 nuclear data libraries together with references that give more detailed information about these libraries. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge. (author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1992-01-01

This document lists more than 80 nuclear data libraries together with references that give more detailed information about these libraries. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge. (author)

Improvements on burnup chain model and group cross section library in the SRAC system

International Nuclear Information System (INIS)

Akie, Hiroshi; Okumura, Keisuke; Takano, Hideki; Ishiguro, Yukio; Kaneko, Kunio.

1992-01-01

Data and functions of the cell burnup calculation of the SRAC system were revised to improve mainly the accuracy of the burnup calculation of high conversion light water reactors (HCLWRs). New burnup chain models were developed in order to treat fission products (FPs) and actinide nuclides in detail. Group cross section library, SRACLIB-JENDL2, was generated based on JENDL-2 nuclear data file. In generating this library, emphasis was placed on FPs and actinides. Also revised were the data such as the average energy release per fission for various actinides. These improved data were verified by performing the burnup analysis of PWR spent fuels. Some new functions were added to the SRAC system for the convenience to yield macroscopic cross sections used in the core burnup process. (author)

IFLA Section of Libraries for the Blind. Expert Meeting, 1984. Papers.

Science.gov (United States)

International Federation of Library Associations, The Hague (Netherlands).

Papers on library services and developments in reading materials for the blind, which were presented at the 1984 Expert Meeting of the IFLA Section of Libraries for the Blind include: (1) "Teaching Map Concepts to the Blind" (R. B. Horsfall and B. Cox, Canada); (2) "Optical Character Recognition 'Reading' for Computerized Braille Production"…

Index of nuclear data libraries available from the IAEA nuclear data section

International Nuclear Information System (INIS)

Lemmel, H.D.

1996-11-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, or online through www or INTERNET: either menu driven within the Nuclear Data Information System (NDIS), or through FTP file transfer. (author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1996-01-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, or online through the INTERNET computer network: either menu driven within the Nuclear Data Information System (NDIS), or through FTP file transfer. (author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.; Schwerer, O.

1997-01-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, CD-ROM or online through WWW, Telnet (menu driven within the Nuclear Data Information System NDIS), or through FTP file transfer. (author)

Index of nuclear data libraries available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1994-01-01

This document lists more than 100 nuclear data libraries together with references that give more detailed information about these libraries. The data libraries include neutron cross-sections, resonance parameters, fission-product yields, nuclear structure and decay data, gamma-rays from radionuclides, data of nuclear reactions induced by charged particles or heavy ions, photonuclear data, photoatomic interaction data, and many others, partly with related data processing computer codes. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge on magnetic tape, PC diskettes, or online through the INTERNET computer network: either menu driven within the Nuclear Data Information System (NDIS), or through FTP file transfer. (author)

Differences between cross-section libraries for neutron dosimetry; Diferencas entre bibliotecas de secoes de choque para dosimetria de neutrons

Energy Technology Data Exchange (ETDEWEB)

Tardelli, T.C.; Stecher, L.C.; Coelho, T.S.; Castro, V.A. De; Cavalieri, T.A.; Menzel, F.; Giarola, R.S.; Domingos, D.B.; Yoriyaz, H., E-mail: tiago.tardelli@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Centro de Engenharia Nuclear

2013-08-15

Absorbed dose calculations depend on a consistent set of nuclear data used in simulations in computer codes. Nuclear data are stored in libraries, however, the information available about the differences in dose caused by different libraries are rare. The libraries are processed by a computer system to be able to be used by a radiation transport code. One of the systems capable of processing nuclear data is the NJOY system. The objective of this study is to evaluate the nuclear data libraries for neutrons available in the literature, and to quantify the differences in absorbed dose obtained using the libraries JENDL 4.0, JEFF 3.3.1 and ENDF/B.VII. The absorbed dose calculation was performed on a simple geometric model, as spheres, and in anthropomorphic model of the human body based on the ICRP-110 for neutron transport simulation using the MCNP5 code. The results were compared with literature data. The results obtained with cross sections from the libraries JEFF and ENDF/B.VII have shown to be identical in most cases, except for one case where the difference has exceeded 10%. The results obtained with JENDL library has shown to be considerably different in most cases comparing to other two libraries. Some differences were over 200%. The dose calculations showed differences between the libraries, which is justified by differences in the cross sections. It has been observed that the cross sections values of certain nuclides assume quite different values in different libraries. These differences in turn cause considerable differences in dose calculations. (author)

Library of neutron reaction cross-sections in the ABBN-93 constant system

International Nuclear Information System (INIS)

Zabrodskaya, S.V.; Korchagina, Zh.A.; Koshcheev, V.N.; Nikolaev, M.N.; Tsibulya, A.M.

2001-01-01

The library of neutron reaction group cross-sections in the ABBN-93 constant set is described. The format used for data representation, the content and purpose of the sub-libraries and their practical application in the SCALE criticality safety estimation system are discussed. (author)

Generation and validation of the WIMS-D5 library based on JENDL-3.2

International Nuclear Information System (INIS)

Gil, Choong-Sup; Kim, Jung-Do

2002-01-01

A WIMS-D5 library based on JENDL-3.2 has been prepared and is being tested against benchmark problems. Several sensitivity calculations for stability confirmation of the library were carried out, such as fission spectrum dependency and the self-shielding effects of the elastic scattering cross sections and the self-shielding effects 240 Pu and 242 Pu capture cross sections below 4.0 eV. The results of benchmark calculations with the libraries based on JENDL-3.2, ENDF/B-VI.5, JEF-2.2, and the 1986 WIMS-D library were intercompared. The multiplication factors for the thermal lattices are slightly underpredicted by all libraries (up to 1% with ENDF/B-VI.5). The k eff values with the library based on JENDL-3.2 are slightly higher than those of ENDF/B-VI.5 and JEF-2.2. The spectral indices for the lattices with JENDL-3.2 agree with the measured quantities within the uncertainties of the experiments. The calculated amounts of some isotopes such as 149 Sm, 237 Np, 238 Pu, 242 Cm and 243 Cm show large differences from the measured or reference values. (author)

A Validated MCNP(X) Cross Section Library based on JEFF 3.1

International Nuclear Information System (INIS)

Haeck, W.; Verboomen, B.

2006-01-01

ALEPH-LIB is a multi-temperature neutron transport library for standard use by MCNP(X) and ALEPH generated with ALEPH-DLG. This is an auxiliary computer code to ALEPH, the Monte Carlo burn-up code under development at SCK-CEN in collaboration with Ghent university. ALEPH-DLG automates the entire process of generating library files with NJOY and takes care of the first requirement of a validated application library: verify the processing. It produces tailor made NJOY input files using data from the original ENDF file (initial temperature, the fact if the nuclide is fissile or if it has unresolved resonances, etc.) When the library files have been generated, ALEPH-DLG will also process the output from NJOY by extracting all messages and warnings. If ALEPH-DLG finds anything out of the ordinary, it will either warn the user or perform corrective actions. The temperatures included in the ALEPH-LIB library are 300, 600, 900, 1200, 1500 and 1800 K. Library files were produced for the JEF 2.2, JEFF 3.0, JEFF 3.1, JENDL 3.3 and ENDF/B-VI.8 nuclear data libraries. This will be extended with ENDF/B-VII when it becomes available. This report deals with the JEFF 3.1 files included in ALEPH-LIB that are now released by the NEA-OECD.

A Validated MCNP(X) Cross Section Library based on JEFF 3.1

Energy Technology Data Exchange (ETDEWEB)

Haeck, W; Verboomen, B

2006-10-15

ALEPH-LIB is a multi-temperature neutron transport library for standard use by MCNP(X) and ALEPH generated with ALEPH-DLG. This is an auxiliary computer code to ALEPH, the Monte Carlo burn-up code under development at SCK-CEN in collaboration with Ghent university. ALEPH-DLG automates the entire process of generating library files with NJOY and takes care of the first requirement of a validated application library: verify the processing. It produces tailor made NJOY input files using data from the original ENDF file (initial temperature, the fact if the nuclide is fissile or if it has unresolved resonances, etc.) When the library files have been generated, ALEPH-DLG will also process the output from NJOY by extracting all messages and warnings. If ALEPH-DLG finds anything out of the ordinary, it will either warn the user or perform corrective actions. The temperatures included in the ALEPH-LIB library are 300, 600, 900, 1200, 1500 and 1800 K. Library files were produced for the JEF 2.2, JEFF 3.0, JEFF 3.1, JENDL 3.3 and ENDF/B-VI.8 nuclear data libraries. This will be extended with ENDF/B-VII when it becomes available. This report deals with the JEFF 3.1 files included in ALEPH-LIB that are now released by the NEA-OECD.

Design and producing of fine-group cross section library HENDL3.0/FG for subcritical system

International Nuclear Information System (INIS)

Zou, J.; Zeng, Q.; Xu, D.; Hu, L.; Long, P.

2012-01-01

To improve the accuracy of the neutron analyses for subcritical system with thermal fission blanket, a coupled neutron and photon (315 n + 42γ) fine-group cross section library HENDL3.0/FG based on ENDF/B-VII, JEFF3.1 and JENDL3.3 was produced by FDS team. In order to test the availability and reliability of the HENDL3.0/FG data library, shielding and critical safety benchmarks were performed with VisualBUS code. The testing results indicated that the discrepancy between calculation and experimental values of nuclear parameters fell in a reasonable range. It showed that the nuclear data library had accuracy and availability. (authors)

Index of data libraries available on magnetic tape from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1990-01-01

This document lists more than 80 nuclear data libraries and some atomic data libraries together with references that give more detailed information about these libraries. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge. (author)

Index of data libraries available on magnetic tape from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1991-05-01

This document lists more than 80 nuclear data libraries and some atomic data libraries together with references that give more detailed information about these libraries. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge. (author)

Index of data libraries available on magnetic tape from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Lemmel, H.D.

1986-07-01

This document lists more than 80 nuclear data libraries and some atomic data libraries together with references that give more detailed information about these libraries. All data and documentation references are available upon request from the IAEA Nuclear Data Section, free of charge. (author)

Point 2004 A Temperature Dependent ENDF/B-VI, Release 8 Cross Section Library

International Nuclear Information System (INIS)

Cullen, D E

2004-01-01

The ENDF/B data library has recently been updated and is now freely available through the National Nuclear Data Center (NNDC), Brookhaven National Laboratory. This most recent library is identified as ENDF/B-VI, Release 8. Release 8 completely supersedes all preceding releases. Release 8 will be the last release of ENDF/B-VI; the next release of ENDF/B data will be for the new ENDF/B-VII library. As distributed the ENDF/B-VI, Release 8 data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature. For use in applications this library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 and 2100 Kelvin, in steps of 300 Kelvin. It has also been processed to five astrophysics like temperatures, 1, 10, 100 eV, 1 and 10 keV. For reference purposes, 300 Kelvin is approximately 1/40 eV, so that 1 eV is approximately 12,000 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy. All results are in the computer independent ENDF/B-VI character format [1], which allows the data to be easily transported between computers. In its processed form this library is approximately 4.3 gigabyte in size and is distributed on a single DVD

Social Science Libraries Section. Special Libraries Division. Papers.

Science.gov (United States)

International Federation of Library Associations, The Hague (Netherlands).

Three papers on the nonconventional literature and social science libraries were presented at the 1983 International Federation of Library Associations (IFLA) conference. In "Grey Material: A Scandinavian View," Birgitta Bergdahl (Sweden) outlines the etymology and meaning of the concept of "grey literature" (which can include…

Evaluated cross-section libraries and kerma factors for neutrons up to 100 MeV on 12C

International Nuclear Information System (INIS)

Chadwick, M.B.; Blann, M.; Cox, L.; Young, P.G.; Meigooni, A.

1995-01-01

A program is being carried out at Lawrence Livermore National Laboratory to develop high-energy evaluated nuclear data libraries for use in Monte Carlo simulations of cancer radiation therapy. In this report we describe evaluated cross sections and kerma factors for neutrons with incident energies up to 100 MeV on 12 C. The aim of this effort is to incorporate advanced nuclear physics modeling methods, with new experimental measurements, to generate cross section libraries needed for an accurate simulation of dose deposition in fast neutron therapy. The evaluated libraries are based mainly on nuclear model calculations, benchmarked to experimental measurements where they exist. We use the GNASH code system, which includes Hauser-Feshbach, preequilibrium, and direct reaction mechanisms. The libraries tabulate elastic and nonelastic cross sections, angle-energy correlated production spectra for light ejectiles with A≤and kinetic energies given to light ejectiles and heavy recoil fragments. The major steps involved in this effort are: (1) development and validation of nuclear models for incident energies up to 100 MeV; (2) collation of experimental measurements, including new results from Louvain-la-Nueve and Los Alamos; (3) extension of the Livermore ENDL formats for representing high-energy data; (4) calculation and evaluation of nuclear data; and (5) validation of the libraries. We describe the evaluations in detail, with particular emphasis on our new high-energy modeling developments. Our evaluations agree well with experimental measurements of integrated and differential cross sections. We compare our results with the recent ENDF/B-VI evaluation which extends up to 32 MeV

ZZ DOSCROS, Neutron Cross-Section Library for Spectra Unfolding and Integral Parameter Evaluation

International Nuclear Information System (INIS)

Zijp, Willem L.; Nolthenius, Henk J.; Rieffe, Henk Ch.

1987-01-01

1 - Description of problem or function: Format: SAND-II; Number of groups: 640 fine group cross section values; Nuclides: Li, B, F, Na, Mg, Al, S, Sc, Ti, Cr, Mn, Fe, Co, Ni, Cu, Zn, As, Br, Nb, Mo, Rh, Pd, Ag, In, Sb, I, Cs, La, Eu, Sm, Dy, Lu, Ta, W, Re, Au, Th, U, Np, Pu. Origin: ENDF/B-V mainly, ENDF/B-IV, INDL/V. This library forms in combination with the DAMSIG81 library a convenient source of evaluated energy dependent cross section sets which may be used in the determination of neutron spectra by means of adjustment (or unfolding) procedures or which can be used for the determination of integral parameters (such as damage-to-activation ratio) useful in characterising the neutron spectra. The energy dependent fine group cross section data are presented in a 640 group structure of the SAND-II type. This group structure has 45 energy groups per energy decade below 1 MeV and a group width of 100 KeV above 1 MeV. The total energy span of this group structure is from 10 -10 MeV to 20 MeV. The library has the SAND-II format, which implies that a special part of the library has to contain cover cross section data sets. These cross section data sets are required in the SAND-II program for taking into account the influence of special detector surroundings which may be used during an irradiation. 2 - Method of solution: The selection of the reactions from the evaluated nuclear data libraries was determined by various properties of the reactions for neutron metrology. For this reason all the well- known reactions of the ENDF/B-V dosimetry file are included but these data are supplemented with cross section sets for less well known metrology reactions which may become of interest

FENDL/A-2.0. Neutron activation cross section data library for fusion applications

International Nuclear Information System (INIS)

Pashchenko, A.B.; Wienke, H.; Kopecky, J.; Sublet, J.C. Sublet; Forrest, R.A.

1997-01-01

This document describes the contents of a comprehensive neutron cross section data library for 13,006 neutron activation reactions with 739 target nuclides from H (A=1,Z=1) to Cm (A=248,Z=96), in the incident energy range up to 20 MeV. FENDL/A-2 is a sublibrary of FENDL-2, the second revision of the evaluated nuclear data library for fusion applications. It is supplemented by a decay data library FENDL/D-2 in ENDF-6 format for 1867 nuclides. The data are available from the IAEA Nuclear Data Section online via INTERNET by FTP command, or on magnetic tape upon request. (author)

Generation, Testing, and Validation of a WIMS-D/4 Multigroup Cross-Section Library Based on the JENDL-3.2 Nuclear Data

International Nuclear Information System (INIS)

Rahman, Mafizur; Takano, Hideki

2001-01-01

A new 69-group library of multigroup constants for the lattice code WIMS-D/4 has been generated with an improved resonance treatment, processing nuclear data from JENDL-3.2 by NJOY91.108. A parallel ENDF/B-VI based library has also been constructed for intercomparison of results. Benchmark calculations for a number of thermal reactor critical assemblies of both uranium and plutonium fuels have been performed with the code WIMS-D/4.1 with its three different libraries: the original WIMS library (NEA-0329/10) and the new ENDF/B-VI and JENDL-3.2 based libraries. The results calculated with both ENDF and JENDL based libraries show a similar tendency and are found in better agreement with the experimental values. Benchmark parameters are further calculated with the comprehensive lattice code SRAC95. The results from SRAC95 and WIMS-D/4.1 (both using JENDL-3.2 based libraries) agree well with each other. The new library is also verified for its applicability to mixed-oxide cores of varying plutonium contents

Analysis of fusion neutronics calculations and appraisal of UW cross-section library

International Nuclear Information System (INIS)

Xie Jianping; Li Xingzhong; Ying Chuntong

1989-01-01

A series of calculations for different cases (especially for the values of tritium breeding ratio T, and the fuel breeding ratio F in the blanket of a hybrid reactor) were carried out by using ANISN program and UW cross-section library. The comparison with other results in China and abroad kalso was done. It was shownwn that the installation and execution of ANISN program on ELXSI machine at Tsinghua University are successful, and the UW cross-section library is reliable. It may be used for fusion neutronics calculation in the future. The paper also points out that the difference between the calculations and by the authors are due to jthe different in cross-section data used

Extension and Verification of the Cross-Section Library for the VVER-1000 Surveillance Specimen Region

International Nuclear Information System (INIS)

Kirilova, D.; Belousov, S.; Ilieva, K.

2011-01-01

The objective of this work is a generation of new version of the BGL multigroup cross-section to extend the region of its applicability. The existing library version is problem oriented for VVER-1000 type of reactors and was generated by collapsing of the VITAMIN-B6 problem independent cross-section fine-group library applying the VVER-1000 reactor middle plane spectrum in cylindrical geometry. The new version BGLex additionally contains cross-sections averaged on the corresponding spectra of the surveillance specimen's (SS) region for VVER-1000 type of reactors. Comparative analysis of the neutron spectra for different one-dimensional geometry models that could be applied for the cross-section collapsing using the software package SCALE, showed a high sensitivity of the results to the geometry model. That is why a neutron importance assessment was done for the SS region using the adjoint solution calculated by the two-dimensional code DORT and problem-independent library VITAMIN-B6. The one-dimensional geometry model applied to the cross-section collapsing were determined by the material limits above the reactor core in axial direction z as for every material a homogenization in radial direction was done. The material homogenization in radial direction was done by material weighing taking into account the adjoint solution as well as the neutron source. The one-dimensional geometry model comprising the homogenized weighed materials was applied for the cross-section generation of the fine-group library VITAMIN-B6 to the broad-group structure of BGL library. The new version BGLex was extended with cross-sections for the SS region. Verification and validation of the new version BGLex is forthcoming. It includes comparison between the calculated results with the new version BGLex and the libraries BGL and VITAMIN-B6 and comparison with experimental results. (author)

Extension and Verification of the Cross-Section Library for the VVER- 1000 Surveillance Specimen Region

International Nuclear Information System (INIS)

Kirilova, D.; Belousov, S.; Ilieva, K.

2011-01-01

The objective of this work is a generation of new version of the BGL multigroup cross-section to extend the region of its applicability. The existing library version is problem oriented for VVER-1000 type of reactors and was generated by collapsing of the VITAMIN-B6 problem independent cross-section fine-group library applying the VVER-1000 reactor middle plane spectrum in cylindrical geometry. The new version BGLex additionally contains cross-sections averaged on the corresponding spectra of the surveillance specimen's (SS) region for VVER-1000 type of reactors. Comparative analysis of the neutron spectra for different one-dimensional geometry models that could be applied for the cross-section collapsing using the software package SCALE, showed a high sensitivity of the results to the geometry model. That is why a neutron importance assessment was done for the SS region using the adjoint solution calculated by the two-dimensional code DORT and problem-independent library VITAMIN-B6. The one-dimensional geometry model applied to the cross-section collapsing were determined by the material limits above the reactor core in axial direction z as for every material a homogenization in radial direction was done. The material homogenization in radial direction was done by material weighing taking into account the adjoint solution as well as the neutron source. The one-dimensional geometry model comprising the homogenized weighed materials was applied for the cross-section generation of the fine-group library VITAMIN-B6 to the broad-group structure of BGL library. The new version BGLex was extended with cross-sections for the SS region. Verification and validation of the new version BGLex is forthcoming. It includes comparison between the calculated results with the new version BGLex and the libraries BGL and VITAMIN-B6 and comparison with experimental results. (author)

CSRL-V: processed ENDF/B-V 227-neutron-group and pointwise cross-section libraries for criticality safety, reactor, and shielding studies

International Nuclear Information System (INIS)

Ford, W.E. III; Diggs, B.R.; Petrie, L.M.; Webster, C.C.; Westfall, R.M.

1982-01-01

A P 3 227-neutron-group cross-section library has been processed for the subsequent generation of problem-dependent fine- or broad-group cross sections for a broad range of applications, including shipping cask calculations, general criticality safety analyses, and reactor core and shielding analyses. The energy group structure covers the range 10 -5 eV - 20 MeV, including 79 thermal groups below 3 eV. The 129-material library includes processed data for all materials in the ENDF/B-V General Purpose File, several data sets prepared from LENDL data, hydrogen with water- and polyethyelene-bound thermal kernels, deuterium with C 2 O-bound thermal kernels, carbon with a graphite thermal kernel, a special 1/V data set, and a dose factor data set. The library, which is in AMPX master format, is designated CSRL-V (Criticality Safety Reference Library based on ENDF/B-V data). Also included in CSRL-V is a pointwise total, fission, elastic scattering, and (n,γ) cross-section library containing data sets for all ENDF/B-V resonance materials. Data in the pointwise library were processed with the infinite dilute approximation at a temperature of 296 0 K

Graphs of the cross sections in the recommended Monte Carlo cross-section library at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Soran, P.D.; Seamon, R.E.

1980-05-01

Graphs of all neutron cross sections and photon production cross sections on the Recommended Monte Carlo Cross Section (RMCCS) library have been plotted along with local neutron heating numbers. Values for anti ν, the average number of neutrons per fission, are also given

Performance assessment of new neutron cross section libraries using MCNP code and some critical benchmarks

International Nuclear Information System (INIS)

Bakkari, B El; Bardouni, T El.; Erradi, L.; Chakir, E.; Meroun, O.; Azahra, M.; Boukhal, H.; Khoukhi, T El.; Htet, A.

2007-01-01

Full text: New releases of nuclear data files made available during the few recent years. The reference MCNP5 code (1) for Monte Carlo calculations is usually distributed with only one standard nuclear data library for neutron interactions based on ENDF/B-VI. The main goal of this work is to process new neutron cross sections libraries in ACE continuous format for MCNP code based on the most recent data files recently made available for the scientific community : ENDF/B-VII.b2, ENDF/B-VI (release 8), JEFF3.0, JEFF-3.1, JENDL-3.3 and JEF2.2. In our data treatment, we used the modular NJOY system (release 99.9) (2) in conjunction with its most recent upadates. Assessment of the processed point wise cross sections libraries performances was made by means of some criticality prediction and analysis of other integral parameters for a set of reactor benchmarks. Almost all the analyzed benchmarks were taken from the international handbook of Evaluated criticality safety benchmarks experiments from OECD (3). Some revised benchmarks were taken from references (4,5). These benchmarks use Pu-239 or U-235 as the main fissionable materiel in different forms, different enrichments and cover various geometries. Monte Carlo calculations were performed in 3D with maximum details of benchmark description and the S(α,β) cross section treatment was adopted in all thermal cases. The resulting one standard deviation confidence interval for the eigenvalue is typically +/-13% to +/-20 pcm [fr

Preliminary assessment of Geant4 HP models and cross section libraries by reactor criticality benchmark calculations

DEFF Research Database (Denmark)

Cai, Xiao-Xiao; Llamas-Jansa, Isabel; Mullet, Steven

2013-01-01

Geant4 is an open source general purpose simulation toolkit for particle transportation in matter. Since the extension of the thermal scattering model in Geant4.9.5 and the availability of the IAEA HP model cross section libraries, it is now possible to extend the application area of Geant4......, U and O in uranium dioxide, Al metal, Be metal, and Fe metal. The native HP cross section library G4NDL does not include data for elements with atomic number larger than 92. Therefore, transuranic elements, which have impacts for a realistic reactor, can not be simulated by the combination of the HP...... models and the G4NDL library. However, cross sections of those missing isotopes were made available recently through the IAEA project “new evaluated neutron cross section libraries for Geant4”....

Cross sections of the lumped fission products for the AMZ library

International Nuclear Information System (INIS)

Ono, S.; Corcueca, R.P.; Nascimento, J.A.

1985-01-01

The preparation of the lumped fission product cross section for the AMZ library is described. For this purpose 100 nuclides were selected. The cross sections for each nuclide were generated by the NJOY code with evaluated nuclear data from ENDF/B-V, complemented with ENDF/B-IV data. A comparison is performed between the data obtained and the lumped fission product cross section of JFS-II [pt

Neutron cross-section libraries in the AMPX master interface format for thermal and fast reactors

International Nuclear Information System (INIS)

Bjerke, M.A.; Webster, C.C.

1981-12-01

Neutron cross-section libraries in the AMPX master interface format have been created for three reactor types. Included are an 84-group library for use with light-water reactors, a 27-group library for use with heavy-water CANDU reactors and a 126-group library for use with liquid metal fast breeder reactors. In general, ENDF/B data were used in the creation of these libraries, and the nuclides included in each library should be sufficient for most neutronic analyses of reactors of that type. Each library has been used successfully in fuel depletion calculations

CSRL-V ENDF/B-V 227-group neutron cross-section library and its application to thermal-reactor and criticality safety benchmarks

International Nuclear Information System (INIS)

Ford, W.E. III; Diggs, B.R.; Knight, J.R.; Greene, N.M.; Petrie, L.M.; Webster, C.C.; Westfall, R.M.; Wright, R.Q.; Williams, M.L.

1982-01-01

Characteristics and contents of the CSRL-V (Criticality Safety Reference Library based on ENDF/B-V data) 227-neutron-group AMPX master and pointwise cross-section libraries are described. Results obtained in using CSRL-V to calculate performance parameters of selected thermal reactor and criticality safety benchmarks are discussed

VITAMIN-J/COVA/EFF-3 cross-section covariance matrix library and its use to analyse benchmark experiments in sinbad database

International Nuclear Information System (INIS)

Kodeli, Ivan-Alexander

2005-01-01

The new cross-section covariance matrix library ZZ-VITAMIN-J/COVA/EFF3 intended to simplify and encourage sensitivity and uncertainty analysis was prepared and is available from the NEA Data Bank. The library is organised in a ready-to-use form including both the covariance matrix data as well as processing tools:-Cross-section covariance matrices from the EFF-3 evaluation for five materials: 9 Be, 28 Si, 56 Fe, 58 Ni and 60 Ni. Other data will be included when available. -FORTRAN program ANGELO-2 to extrapolate/interpolate the covariance matrices to a users' defined energy group structure. -FORTRAN program LAMBDA to verify the mathematical properties of the covariance matrices, like symmetry, positive definiteness, etc. The preparation, testing and use of the covariance matrix library are presented. The uncertainties based on the cross-section covariance data were compared with those based on other evaluations, like ENDF/B-VI. The collapsing procedure used in the ANGELO-2 code was compared and validated with the one used in the NJOY system

Graphs of the cross sections in the Alternate Monte Carlo Cross Section library at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Seamon, R.E.; Soran, P.D.

1980-06-01

Graphs of all neutron cross sections and photon production cross sections on the Alternate Monte Carlo Cross Section (AMCCS) library have been plotted along with local neutron heating numbers. The values of ν-bar, the average number of neutrons per fission, are also plotted for appropriate isotopes

Development of a common nuclear group constants library system: JSSTDL-295n-104γ based on JENDL-3 nuclear data library

International Nuclear Information System (INIS)

Hasegawa, A.

1992-01-01

JSSTDL 295n-104γ: A common group cross-section library system has been developed in JAERI to be used in fairly wide range of applications in nuclear industry. This system is composed of a common 295n-104γ group cross-section library based on JENDL-3 nuclear data file and its utility codes. Target of this system is focused to the criticality or shielding calculations in fast and fusion reactors using ANISN, DOT, or MORSE code. Specifications of the common group constants were decided responding to the request from various nuclear data users, particularly from nuclear design group in Japan. Group structure is decided so as to cover almost all group structures currently used in our country. This library includes self-shielding factor tables for primary reactions. A routine for generating macro-scopic cross-section using the self-shielding factor table is also provided. Neutron cross-sections and photon production cross-sections are processed by Prof. GROUCH-G/B code system and γ ray transport cross-sections are generated by GAMLEG-JR. In this paper, outline and present status of the JSSTDL library system is described along with two examples adopted in JENDL-3 benchmark test. One is for shielding calculation, where effects of self-shielding factor (f-table) is shown in conjunction with the analysis of the ASPIS natural iron deep penetration experiment. Without considering resonance self-shielding effect in resonance energy region for resonant nuclides like iron, the results is completely missled in the attenuation profile calculation in the shields. The other example is fast rector criticality calculations of very small critical assemblies with very high enrichment fuel materials where some basic characteristics of this library is presented. (orig.)

Creation of the equilibrium core PBMR ORIGEN-S cross section library

International Nuclear Information System (INIS)

Stoker, C.C.; Reitsma, F.; Karriem, Z.

2002-01-01

As part of the design calculations for the Pebble Bed Modular Reactor (PBMR), fuel inventories, neutron and gamma sources and decay heat needs to be determined for the fuel spheres. Using the SCALE4.4 code system, a PBMR specific cross section library was created for the ORIGEN-S depletion calculations, assuming a 10-pass refueling system for the PBMR. In this paper the rationale for the creation of the PBMR library is evaluated in terms of the spectrum dependence due to burn-up. The ORIGEN-S PBMR library was further evaluated comparing the results for different parameters calculated with the reactor analysis diffusion code VSOP and the Monte Carlo code MCNP4C. (author)

Comparative evaluation of photon cross section libraries for materials of interest in PET Monte Carlo simulations

CERN Document Server

Zaidi, H

1999-01-01

the many applications of Monte Carlo modelling in nuclear medicine imaging make it desirable to increase the accuracy and computational speed of Monte Carlo codes. The accuracy of Monte Carlo simulations strongly depends on the accuracy in the probability functions and thus on the cross section libraries used for photon transport calculations. A comparison between different photon cross section libraries and parametrizations implemented in Monte Carlo simulation packages developed for positron emission tomography and the most recent Evaluated Photon Data Library (EPDL97) developed by the Lawrence Livermore National Laboratory was performed for several human tissues and common detector materials for energies from 1 keV to 1 MeV. Different photon cross section libraries and parametrizations show quite large variations as compared to the EPDL97 coefficients. This latter library is more accurate and was carefully designed in the form of look-up tables providing efficient data storage, access, and management. Toge...

ZZ BOREHOLE-EB6.8-MG, multi group cross-section library for deterministic and Monte Carlo codes

International Nuclear Information System (INIS)

Kodeli, Ivo; Aldama, Daniel L.; Leege, Piet F.A. de; Legrady, David; Hoogenboom, J. Eduard

2007-01-01

1 - Description: Format: MATXS and ACE; Number of groups: 175 neutron, 45 gamma-ray; Nuclides: H-1, C-12, O-16, Na-23, Mg-nat, Al-27, Si-28, -29, -30, S-nat, Cl-35, -37, K-nat, Ca-nat, Mn-55, Fe-54, -56, -57, -58, I-127, W-nat. Origin: ENDF/B-VI.8; Weighting spectrum: Fission and fusion peak at high energies and a 1/E + thermal Maxwellian extension at low energies. The following materials/nuclides are included in the library: H-1, C-12, O-16, Na-23, Mg-nat, Al-27, Si-28, -29, -30, S-nat, Cl-35, -37, K-nat, Ca-nat, Fe-54, -56, -57, -58, Mn-55, I-127, W-nat. ZZ-BOREHOLE-EB6.8-MG is a multigroup cross section library for deterministic (DOORS, DANTSYS) and Monte Carlo (MCNP) transport codes developed for the oil well logging applications. The library is based on the ENDF/B-VI.8 evaluation and was processed by the NJOY-99 code. The cross sections are given in the 175 neutron and 45 gamma ray group structure. The MATXS format library can be directly used in TRANSX code to prepare the multigroup self-shielded cross sections for deterministic discrete ordinates codes like DOORS and DANTSYS. The data provided in the GROUPR and GAMINR format were converted to the MCNP ACE format by the NSLINK, SCALE and CRSRD codes. IAEA1398/03: Multigroup cross section data for Mn-55 were added in TRANSX format

Production of neutron cross section library based on JENDL-4.0 to continuous-energy Monte Carlo code MVP and its application to criticality analysis of benchmark problems in the ICSBEP handbook

International Nuclear Information System (INIS)

Okumura, Keisuke; Nagaya, Yasunobu

2011-09-01

In May 2010, JENDL-4.0 was released from Japan Atomic Energy Agency as the updated Japanese Nuclear Data Library. It was processed by the nuclear data processing system LICEM and an arbitrary-temperature neutron cross section library MVPlib - nJ40 was produced for the neutron and photon transport calculation code MVP based on the continuous-energy Monte Carlo method. The library contains neutron cross sections for 406 nuclides on the free gas model, thermal scattering cross sections, and cross sections of pseudo fission products for burn-up calculations with MVP. Criticality benchmark calculations were carried out with MVP and MVPlib - nJ40 for about 1,000 cases of critical experiments stored in the hand book of International Criticality Safety Benchmark Evaluation Project (ICSBEP), which covers a wide variety of fuel materials, fuel forms, and neutron spectra. We report all comparison results (C/E values) of effective neutron multiplication factors between calculations and experiments to give a validation data for the prediction accuracy of JENDL-4.0 for criticalities. (author)

Continuous energy cross section library for MCNP/MCNPX based on JENDL high energy file 2007. FXJH7

International Nuclear Information System (INIS)

Sasa, Toshinobu; Sugawara, Takanori; Fukahori, Tokio; Kosako, Kazuaki

2008-11-01

The latest JENDL High Energy File (JENDL/HE) was released in 2007 to respond the requirements of reaction data in high energy range up to several GeV to design accelerator facilities such as accelerator-driven systems and research complex like J-PARC. To apply the JENDL/HE-2007 file to the design study, the cross section library of FXJH7 series was constructed from the JENDL/HE file for the calculation using MCNP and MCNPX codes which are widely used in the field of nuclear reactors, fusion reactors, accelerator facilities, medical applications, and so on. In this report, the outline of the JENDL/HE-2007 file, modification of nuclear data processing code NJOY99, construction of FXJH7 library and test calculations for shielding and eigenvalue analyses are summarized. (author)

Generation of neutron cross sections library for the Thermos code of the Fuel management System (FMS)

International Nuclear Information System (INIS)

Alonso V, G.; Viais J, J.

1990-10-01

There is developed a method to generate the library of neutron cross sections for the Thermos code by means of the database ENDF-B/IV and the NJOY code. The obtained results are compared with the version previous of the library of neutron cross sections which was processed using the version ENDF-B/III. (Author)

COVFILS: 30-group covariance library based on ENDF/B-V

International Nuclear Information System (INIS)

Muir, D.W.; LaBauve, R.J.

1981-03-01

A library of 30-group cross sections and covariances called COVFILS has been prepared from ENDF/B-V data using the NJOY code system. COVFILS includes data on the total cross section, scattering cross sections, and the most important absorption cross sections for 1 H, 10 B, C, 16 O, Cr, Fe, Ni, Cu, and Pb. This report contains detailed descriptions of various features of the library, a listing of a FORTRAN retrieval program, and 143 plots of the multigroup cross-section uncertainties and their correlations

Cross-section libraries and kerma factors

International Nuclear Information System (INIS)

Little, R.C.; MacFarlane, R.E.; Seamon, R.E.

1991-01-01

A large amount of data is required in order to accurately simulate various aspects of Cold Neutron Sources using radiation transport codes such as MCNP and TWODANT. In particular, the following types of data are needed: couple neutron/photon transport libraries, neutron thermal S(α,β) data, response function data (including energy deposition), and proton interaction data. This paper concentrates on the coupled neutron/photon transport libraries and energy deposition. Data libraries available to radiation transport codes are obtained as a result of efforts in many areas, including differential and integral measurements, theoretical model codes, data evaluations, data processing, and data testing. A wide variety of data libraries are available to users of radiation transport codes, including pointwise and multigroup libraries. At Los Alamos, the authors generally recommend the use of data libraries derived from ENDF/B-V. It is often important to know how much energy is deposited in various regions of a device. This problem is typically modeled in radiation transport codes by folding the calculated fluences with an energy-dependent 'heating number'. The heating number represents the average energy deposited locally per collision. Calculation of these heating numbers from evaluated data libraries is fraught with difficulty. Many past difficulties related to energy deposition should be resolved by the release of ENDF/B-VI

Comparison of measurements and calculations of fuel for different structures in the libraries of effective sections (44 groups/238 groups)

International Nuclear Information System (INIS)

Rodriguez Rivada, A.; Tore, C.

2013-01-01

The study was conducted for the use of the sections effective in 44 groups, based on the libraries of effective sections ENDF/B-V, for the calculation of the isotopy of the spent fuel. These effective sections have been developed to be used in the system codes SCALE for the analysis the fresh nuclear fuel as the spent and their radioactive waste.

Problem Oriented Neutron-Gamma Cross Sections Libraries for WWER-440 and WWER-1000 Shielding and Reactor Vessel Dosimetry Application

International Nuclear Information System (INIS)

Belousov, S.; Antonov, S.; Ilieva, K.

1997-01-01

The 47 neutron and 20 gamma group libraries BGL-440 and BGL-1000 for the shielding and reactor vessel dosimetry application have been generated for WWER-440 and WWER-1000 by collapsing the VITAMIN-B6 library (199 neutron and 42 gamma groups on the base of ENDF/B-6). The first parts of the libraries for neutron-gamma transport calculation, BGL-440-1 (150 nuclides) and BGL-1000-1 (140 nuclides), have been generated by a modified version of SAS1X control module of the SCALE system. The appropriate zone-average neutron flux had been used for these sub-libraries collapsing. The BGL-440-2 and BGL-1000-2 sub-libraries consist of cross sections for all 120 nuclides of VITAMIN-B6, for calculation of the transport through non-reactor materials of dosimeters, capsules, specimens which may be placed in the cavity behind the reactor vessel. The neutron spectrum just beyond the RPV had been used for this collapsing. As the first test the comparative calculations of the neutron flux on/behind the WWER-1000 reactor vessel have been realised using the libraries BGL-1000 and BUGLE, intended for the American PWR reactors. The integral neutron flux values by BGL-1000 and BUGLE differ by 3% onto the vessel, and 5% behind the vessel. This result shows that the calculations of the neutron flux responses for the WWER vessel surveillance, especially in locations behind the WWER vessel have to be done by the appropriate BGL library. Key words: neutron transport, multigroup neutron cross section libraries

ZZ ORIGEN2.2-UPJ, A complete package of ORIGEN2 libraries based on JENDL-3.2 and JENDL-3.3

International Nuclear Information System (INIS)

Ishikawa, Makoto; Kataoka, Masaharu; Ohkawachi, Yasushi; Ohki, Shigeo; JIN, Tomoyuki; Katakura, Jun-ich; Suyama, Kenya; Yanagisawa, Hiroshi; Matsumoto, Hideki; ONOUE, Akira; Sasahara, Akihiro

2006-01-01

1 - Description: ORLIBJ32 is a package of the libraries for ORIGEN2 code based on JENDL-3.2(NEA-1642). The one grouped cross section data for PWR and BWR were compiled using the burnup calculation results by SWAT code. The FBR libraries were compiled by the analysis system used at JNC for FBR core calculation. The fission yield and decay constants data were also updated using the second version of the JNDC FP library. In ORLIBJ32, not only one-grouped cross section data but also variable actinide cross section data are prepared, using a code written in FORTRAN77. The routines should be linked to the Original ORIGEN2.1 program. The LWR Libraries are prepared based on the current PWR fuel assembly specification, and the FBR libraries are based on the request by the Japanese FBR researchers. Before compiling the libraries, the specification of fuel assembly was completely reviewed and evaluated by the members of Working Group in the Japanese Nuclear Data Committee, 'working group on the evaluation of the amount of isotope generation'. ORLIBJ33 is a new libraries based on JENDL-3.3 following the release of JENDL-3.3. The parameters used to prepare the library are the same as those of ORLIBJ32. The Original version or ORLIBJ33 is coupled with ORIGEN2.1. But after the release of ORIGEN2.2 from ORNL as CCC-0371 through RSICC, several requests for a combination with ORLIBJ33 and ORIGEN2.2 were received. During the development of ORLIBJ33, released as NEA-1642, authors found a problem in the library maker for FBR libraries, and consequently it was revised and tested in JNC-Oarai. This package 'ORIGEN2.2-UPJ' contains: - updated source code of ORIGEN2.2 of CCC-0371 to use ORLIBJ32 and ORLIBJ33, - all Original libraries in CCC-0371, - ORLIBJ32 in NEA-164/03 (but libraries for FBR are revised), - and ORLIBJ33. In this package, decay data based on the second version of the JNDC FP library and, photon and decay data libraries based on JENDL-3.3 are also included. NLB and NLIB

AXMIX, ANISN Cross-Sections Mixing, Transport Corrections, Data Library Management

International Nuclear Information System (INIS)

2002-01-01

1 - Nature of physical problem solved: Mixing, changing table length, adjoining, making scattering order adjustments (PN delta function subtraction), and transport corrections of ANISN-type cross sections, and management of cross section data sets and libraries. 2 - Method of solution: The number of energy groups which will fit into the core allocated is determined first. If all groups will fit, the solution is straightforward. If not, then the maximum number of groups which will fit is processed repeatedly using direct access I/O and storage disks. 3 - Restrictions on the complexity of the problem: Some flexibility in applying AXMIX is lost when cross sections to be processed contain up-scatter. A special section on up-scatter is therefore included in the report

The Cost of Library Services: Activity-Based Costing in an Australian Academic Library.

Science.gov (United States)

Robinson, Peter; Ellis-Newman, Jennifer

1998-01-01

Explains activity-based costing (ABC), discusses the benefits of ABC to library managers, and describes the steps involved in implementing ABC in an Australian academic library. Discusses the budgeting process in universities, and considers benefits to the library. (Author/LRW)

Comparison of CASMO and NESSEL few group cross section libraries and their usage in DYN3D

International Nuclear Information System (INIS)

Kuchin, A.; Ovdiyenko, Y.; Loetsch, T.

2007-01-01

This work presents comparative analysis of two group diffusion cross section libraries which were generated by NESSEL-4 and CASMO-4 lattice codes. Diffusion parameters were calculated for VVER-1000 fuel assemblies with stainless steel spacing grids and guiding tubes. These cross section sets were introduced into reactor core code DYN3D and tested on the base of real reactor core states. In this case operation data of the first three fuel cycles of 6-th unit of Zaporizhzhya NPP were used

Experience in developing and using the VITAMIN-C 171-neutron, 36-gamma-ray group cross-section library

International Nuclear Information System (INIS)

Roussin, R.W.; Weisbin, C.R.; White, J.E.; Wright, R.Q.; Greene, N.M.; Ford, W.E. III; Wright, J.B.; Diggs, B.R.

1978-01-01

The Department of Energy (DOE) Division of Magnetic Fusion Energy (DMFE) and Reactor Research and Technology (DRRT) jointly sponsored the development of a coupled, fine-group cross-section library. The 171-neutron, 36-gamma-ray group library is intended to be applicable to fusion reactor neutronics and LMFBR core and shield analysis. Versions of the library are available from the Radiation Shielding Information Center (RSIC) at Oak Ridge National Laboratory in both AMPX and CCCC formats. Computer codes for energy group collapsing, interpolation on Bondarenko factors for resonance self-shielding and temperature corrections, and various other useful data manipulations are available. The experience gained in the utilization of this library is discussed. Indications are that this venture, which is designed to allow users to derive problem-dependent cross sections from a fine-group master library, has been a success

Evaluated cross section libraries

International Nuclear Information System (INIS)

Maqurno, B.A.

1976-01-01

The dosimetry tape (ENDF/B-IV tape 412) was issued in a general CSEWG distribution, August 1974. The pointwise cross section data file was tested with specified reference spectra. A group averaged cross section data file (620 groups based on tape 412) was tested with the above spectra and the results are presented in this report

Compilation of MCNP data library based on JENDL-3T and test through analysis of benchmark experiment

International Nuclear Information System (INIS)

Sakurai, K.; Sasamoto, N.; Kosako, K.; Ishikawa, T.; Sato, O.; Oyama, Y.; Narita, H.; Maekawa, H.; Ueki, K.

1989-01-01

Based on an evaluated nuclear data library JENDL-3T, a temporary version of JENDL-3, a pointwise neutron cross section library for MCNP code is compiled which involves 39 nuclides from H-1 to Am-241 which are important for shielding calculations. Compilation is performed with the code system which consists of the nuclear data processing code NJOY-83 and library compilation code MACROS. Validity of the code system and reliability of the library are certified by analysing benchmark experiments. (author)

FENDL/E-2.0. Evaluated nuclear data library of neutron-nucleus interaction cross sections and photon production cross sections and photon-atom interaction cross sections for fusion applications. Version 1, March 1997. Summary documentation

International Nuclear Information System (INIS)

Pashchenko, A.B.; Wienke, H.

1998-01-01

This document presents the description of a physical tape containing the basic evaluated nuclear data library of neutron-nucleus interaction cross sections, photon production cross sections and photon-atom interaction cross sections for fusion applications. It is part of the evaluated nuclear data library for fusion applications FENDL-2. The data are available cost-free from the Nuclear Data Section upon request. The data can also be retrieved by the user via online access through international computer networks. (author)

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Boiling Water Reactor Benchmark Problem

Directory of Open Access Journals (Sweden)

Kulesza Joel A.

2016-01-01

Full Text Available This paper describes a comparison of contemporary and historical light water reactor shielding and pressure vessel dosimetry cross-section libraries for a boiling water reactor calculational benchmark problem. The calculational benchmark problem was developed at Brookhaven National Laboratory by the request of the U. S. Nuclear Regulatory Commission. The benchmark problem was originally evaluated by Brookhaven National Laboratory using the Oak Ridge National Laboratory discrete ordinates code DORT and the BUGLE-93 cross-section library. In this paper, the Westinghouse RAPTOR-M3G three-dimensional discrete ordinates code was used. A variety of cross-section libraries were used with RAPTOR-M3G including the BUGLE93, BUGLE-96, and BUGLE-B7 cross-section libraries developed at Oak Ridge National Laboratory and ALPAN-VII.0 developed at Westinghouse. In comparing the calculated fast reaction rates using the four aforementioned cross-section libraries in the pressure vessel capsule, for six dosimetry reaction rates, a maximum relative difference of 8% was observed. As such, it is concluded that the results calculated by RAPTOR-M3G are consistent with the benchmark and further that the different vintage BUGLE cross-section libraries investigated are largely self-consistent.

POINT 2011: ENDF/B-VII.1 Beta2 Temperature Dependent Cross Section Library

Energy Technology Data Exchange (ETDEWEB)

Cullen, D E

2011-04-07

This report is one in the series of 'POINT' reports that over the years have presented temperature dependent cross sections for the then current version of ENDF/B. In each case I have used my personal computer at home and publicly available data and codes. I have used these in combination to produce the temperature dependent cross sections used in applications and presented in this report. I should mention that today anyone with a personal computer can produce these results. The latest ENDF/B-VII.1 beta2 data library was recently and is now freely available through the National Nuclear Data Center (NNDC), Brookhaven National Laboratory. This release completely supersedes all preceding releases of ENDF/B. As distributed the ENDF/B-VII.1 data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature. For use in our applications the ENDF/B-VII.1 library has been processed into cross sections at eight neutron reactor like temperatures, between 0 and 2100 Kelvin, in steps of 300 Kelvin (the exception being 293.6 Kelvin, for exact room temperature at 20 Celsius). It has also been processed to five astrophysics like temperatures, 1, 10, 100 eV, 1 and 10 keV. For reference purposes, 300 Kelvin is approximately 1/40 eV, so that 1 eV is approximately 12,000 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy. All results are in the computer independent ENDF-6 character format [R2], which allows the data to be easily transported between computers. In its processed form the POINT 2011 library is approximately 16 gigabyte in size and is distributed on one compressed DVDs (see, below for the details of the contents of each DVD).

FENDL/E. Evaluated nuclear data library of neutron nuclear interaction cross-sections and photon production cross-sections and photon-atom interaction cross sections for fusion applications. Version 1.1 of November 1994

International Nuclear Information System (INIS)

Pashchenko, A.B.; Wienke, H.; Ganesan, S.; McLaughlin, P.K.

1996-01-01

This document presents the description of a physical tape containing the basic evaluated nuclear data library of neutron nuclear interaction cross-sections and photon production cross-sections and photon-atom interaction cross-sections for fusion applications. It is part of FENDL, the evaluated nuclear data library for fusion applications. The nuclear data are available cost-free for distribution to interested scientists upon request. The data can also be retrieved by the user via online access through international computer networks. (author). 11 refs, 1 tab

ENEA-Bologna production and testing of Jeff-3.1 multi-group cross section libraries for nuclear fission applications

International Nuclear Information System (INIS)

Pescarini, M.; Orsi, R.; Sinitsa, V.

2008-01-01

The ENEA-Bologna Nuclear Data Group produced the JEFF-3.1 VITJEFF31.BOLIB and MATJEFF31. BOLIB fine-group coupled neutron and photon (199 n + 42 γ) cross section libraries for nuclear fission applications, respectively in AMPX and MATXS format, with the same specifications and energy group structure of the Endf/B-VI-3 VITAMIN-B6 American library. Each library, containing 181 nuclide cross section files, was generated from the same set of cross section data files in GENDF format, obtained through the Bondarenko (f-factor) method, with an ENEA-Bologna revised version of the GROUPR module of the NJOY-99.160 system. Collapsed working libraries of self-shielded cross sections in FIDO-ANISN format, used by the deterministic transport codes of the DANTSYS and DOORS systems, can be generated from VITJEFF31.BOLIB and MATJEFF31.BOLIB through, respectively, further data processing with an ENEA-Bologna revised version of the SCAMPI system and with the TRANSX code. This paper describes the methodology and specifications of the data processing performed and presents some results of the VITJEFF31.BOLIB validation. (authors)

Library-Based Learning in an Information Society.

Science.gov (United States)

Breivik, Patricia Senn

1986-01-01

The average academic library has great potential for quality nonclassroom learning benefiting students, faculty, alumni, and the local business community. The major detriments are the limited perceptions about libraries and librarians among campus administrators and faculty. Library-based learning should be planned to be assimilated into overall…

Generation of the library of neutron cross sections for the Record code of the Fuel Management System (FMS)

International Nuclear Information System (INIS)

Alonso V, G.; Hernandez L, H.

1991-11-01

On the basis of the library structure of the RECORD code a method to generate the neutron cross sections by means of the ENDF-B/IV database and the NJOY code has been developed. The obtained cross sections are compared with those of the current library which was processed using the ENDF-B/III version. (Author)

Experimental OAI-Based Digital Library Systems

Science.gov (United States)

Nelson, Michael L. (Editor); Maly, Kurt (Editor); Zubair, Mohammad (Editor); Rusch-Feja, Diann (Editor)

2002-01-01

The objective of Open Archives Initiative (OAI) is to develop a simple, lightweight framework to facilitate the discovery of content in distributed archives (http://www.openarchives.org). The focus of the workshop held at the 5th European Conference on Research and Advanced Technology for Digital Libraries (ECDL 2001) was to bring researchers in the area of digital libraries who are building OAI based systems so as to share their experiences, problems they are facing, and approaches they are taking to address them. The workshop consisted of invited talks from well-established researchers working in building OAI based digital library system along with short paper presentations.

Production of application libraries for WIMS

International Nuclear Information System (INIS)

Dean, C.J.

1996-01-01

The WIMS codes have been developed over a period of 30 years to include sophisticated modelling of many thermal reactor lattices. WIMS6 is currently being developed to include the flexibility of WIMSE together with the case of use seen in LWRWIMS. A new cross-section library is to be released with WIMS6. For the first time since the original WIMSD was written, the library is being generated from completely new differential data based mainly on JEF2.2. Quality Assurance into the XMAS library is achieved in three levels; through general procedures during assembly, by validation studies and by verification. The main general procedure involves forming overall physics quantities (Thermal average cross section, resonance integrals and fission spectrum average values) from the point evaluations and comparing them with similar quantities from the XMAS library. Examples of validation are studies optimizing the background cross-sections at which resonance integrals are tabulated and comparing reaction rates from homogeneous calculations with those formed in Monte Carlo and deterministic codes which represent energy variation of cross-section on a hyperfine energy mesh. Verification involves performing benchmark calculations and comparing results with experiment and calculations with the Apollo code. The current XMAS library contains 140 nuclides based on JEF2.2 evaluations. (author)

Development and benchmark of high energy continuous-energy neutron cross Section library HENDL-ADS/MC

International Nuclear Information System (INIS)

Chen Chong; Wang Minghuang; Zou Jun; Xu Dezheng; Zeng Qin

2012-01-01

The ADS (accelerator driven sub-critical system) has great energy spans, complex energy spectrum structures and strong physical effects. Hence, the existing nuclear data libraries can't fully meet the needs of nuclear analysis in ADS. In order to do nuclear analysis for ADS system, a point-wise data library HENDL-ADS/MC (hybrid evaluated nuclear data library) was produced by FDS team. Meanwhile, to test the availability and reliability of the HENDL-ADS/MC data library, a series of shielding and critical safety benchmarks were performed. To validate and qualify the reliability of the high-energy cross section for HENDL-ADS/MC library further, a series of high neutronics integral experiments have been performed. The testing results confirm the accuracy and reliability of HENDL-ADS/MC. (authors)

The LAW library

International Nuclear Information System (INIS)

Green, N.M.; Parks, C.V.; Arwood, J.W.

1989-01-01

The 238 group LAW library is a new multigroup library based on ENDF/B-V data. It contains data for 302 materials and will be distributed by the Radiation Shielding Information Center, located at Oak Ridge National Laboratory. It was generated for use in neutronics calculations required in radioactive waste analyses, though it has equal utility in any study requiring multigroup neutron cross sections

Assessment and comparison of different multigroup neutron cross section libraries for dosimetry purposes

International Nuclear Information System (INIS)

Erradi, L.; Karouani, K.

1994-01-01

Many multigroup neutron cross section libraries have been processed from basic evaluated nuclear data for use in neutron dosimetry, reactor shielding calculation and in the development of fusion reactors. Most of these libraries have been tested only for fission spectra and were not validated for fusion spectra. Fifteen of these libraries such as DOSCROS84, IRDF85 and ENDFB5 have been used along with the neutron spectra unfolding code SAND II to evaluate about fifteen threshold detector saturated activities. The comparison between these computed activities and the measured ones of a set of foils placed in different places along the axis of a paraffin cylinder and irradiated by 14 MeV neutrons generated by a D-T source, hence giving rise to complex spectra, leads to different types of discrepancies. The analysis of these discrepancies allows to select from these libraries the ones that can be recommended. 1 fig., 4 refs. (author)

Curriculum-based neurosurgery digital library.

Science.gov (United States)

Langevin, Jean-Philippe; Dang, Thai; Kon, David; Sapo, Monica; Batzdorf, Ulrich; Martin, Neil

2010-11-01

Recent work-hour restrictions and the constantly evolving body of knowledge are challenging the current ways of teaching neurosurgery residents. To develop a curriculum-based digital library of multimedia content to face the challenges in neurosurgery education. We used the residency program curriculum developed by the Congress of Neurological Surgeons to structure the library and Microsoft Sharepoint as the user interface. This project led to the creation of a user-friendly and searchable digital library that could be accessed remotely and throughout the hospital, including the operating rooms. The electronic format allows standardization of the content and transformation of the operating room into a classroom. This in turn facilitates the implementation of a curriculum within the training program and improves teaching efficiency. Future work will focus on evaluating the efficacy of the library as a teaching tool for residents.

Development of fine-group (315n/42γ) cross section library ENDL3.0/FG for fusion-fission hybrid systems

International Nuclear Information System (INIS)

Zeng Qin; Zou Jun; Xu Dezhen; Jiang Jieqiong; Wang Minghuang; Wu Yican; Qiu Yuefeng; Chen Zhong; Chen Yan

2011-01-01

To improve the accuracy of the neutron analyses for subcritical systems with thermal fission blanket, a coupled neutron and photon (315 n + 42γ) fine-group cross section library HENDL3.0/FG based on ENDF/B-Ⅶ. 0 has been produced by FDS team. In order to test the availability and reliability of the HENDL3.0/FG data library, shielding and critical safety benchmarks were performed with VisualBUS code. The testing results indicated that the discrepancy between calculation and experimental values of nuclear parameters fell in a reasonable range. (authors)

ZZ FCXSEC, Coupled Cross-Section Library for Shielding from VITAMIN-C in AMPX, ANISN Format

International Nuclear Information System (INIS)

1985-01-01

1 - Description of problem or function: Format: (a) and (b) AMPX, (c) and (d) ANISN; Number of groups: (a) Fine-group 171 neutron and 36 gamma-ray; (b) Broad-group 22 neutron and 21 gamma-ray; (c) Broad-group microscopic (22n-21 gamma); (d) Broad-group macroscopic; Nuclides: Mixtures: H 2 O, Borated water, Concrete, D 2 O, Lithium hydride, Boral, Dry air, Nitric acid, Uranium dioxide, S 3 0 4 , UF 6 TBP in dodecane, Sm 2 O 3 , Eu 2 O 3 , Gd 2 O 3 , Gd(NO 3 ) 3 in water, WB2, Spen fuel oxide, Thorium oxide, Uranium metal, Silver zeolite. Individual materials: C, Na, Al, Fe, Zircaloy, Cd Nb, Mo, Pb, Be, Ti, V, Mn, Co, Cu, Sn, Ta. Origin: VITAMIN-C; Weighting spectrum: From 1.1109+5 eV to 1.7333+7 eV → 239 Pu thermal fission; From 4.1399-1 eV to 1.1109+5 eV → 1/E; From 1.0000-5 eV to 4.1399-1 eV → Maxwellian. FSXSEC is a collection of cross section libraries to be used for nuclear fuel cycle shielding calculations, generated from the pseudo-composition-independent VITAMIN-C cross section library: (a) A composition-dependent self-shielded fine-group library with 171 neutron groups and 36 gamma groups, and a broad-group library with 22 neutron and 21 gamma groups for AMPX. (b) A broad-group microscopic and a broad-group macroscopic library in ANISN format. 2 - Method of solution: To generate library (a), AMPX modules BONAMI, CHOX, and MALOCS were used. To generate library (b), AMPX modules NITAWL and AXMIX were used

BUGLE-93 (ENDF/B-VI) cross-section library data testing using shielding benchmarks

International Nuclear Information System (INIS)

Hunter, H.T.; Slater, C.O.; White, J.E.

1994-01-01

Several integral shielding benchmarks were selected to perform data testing for new multigroup cross-section libraries compiled from the ENDF/B-VI data for light water reactor (LWR) shielding and dosimetry. The new multigroup libraries, BUGLE-93 and VITAMIN-B6, were studied to establish their reliability and response to the benchmark measurements by use of radiation transport codes, ANISN and DORT. Also, direct comparisons of BUGLE-93 and VITAMIN-B6 to BUGLE-80 (ENDF/B-IV) and VITAMIN-E (ENDF/B-V) were performed. Some benchmarks involved the nuclides used in LWR shielding and dosimetry applications, and some were sensitive specific nuclear data, i.e. iron due to its dominant use in nuclear reactor systems and complex set of cross-section resonances. Five shielding benchmarks (four experimental and one calculational) are described and results are presented

Implementing of AMPX-II system for a univac computer neutron cross-section libraries

International Nuclear Information System (INIS)

Sancho, J.; Verdu, G.; Serradell, V.

1984-01-01

The AMPX-II system, developed at ORNL, is constituted by a modular set of computer programs, for generation and handling of several nuclear data libraries. The processing starts from ENDF/B library. Along this paper, we refer mainly to the modules related with neutron cross section libraries: master, working and weighted. These modules have been implemented recently for a UNIVAC 1100/60 computer in the Universidad Politecnica de Valencia (Spain). In order to run the programs in that machine it has been necessary to introduce a number of modifications into their programing structure. The main difficulties found in this work and the need of verification for the new versions are also pointed out. We also refer to the results obtained from the execution of a set of little sample problems. (author)

Generating and verification of ACE-multigroup library for MCNP

International Nuclear Information System (INIS)

Chen Chaobin; Hu Zehua; Chen Yixue; Wu Jun; Yang Shouhai

2012-01-01

The Monte Carlo code MCNP can handle multigroup calculations and a sample multigroup set based on ENDF/B-V, MGXSNP, is available for MCNP for coupled neutron-photon transport. However, this library is not suit- able for all problems, and there is a need for users to be able to generate multigroup libraries tailored to their specific applications. For these purposes CSPT (cross section processing tool) is created to generate multigroup library for MCNP from deterministic multigroup cross sections (GENDF or ANISN format at present). Several ACE-multigroup libraries based on ENDF/B-VII.0 converted and verified in this work, we drawn the conclusion that the CSPT code works correctly and the libraries produced are credible. (authors)

Recent validation experience with multigroup cross-section libraries and scale

International Nuclear Information System (INIS)

Bowman, S.M.; Wright, R.Q.; DeHart, M.D.; Parks, C.V.; Petrie, L.M.

1995-01-01

This paper will discuss the results obtained and lessons learned from an extensive validation of new ENDF/B-V and ENDF/B-VI multigroup cross-section libraries using analyses of critical experiments. The KENO V. a Monte Carlo code in version 4.3 of the SCALE computer code system was used to perform the critical benchmark calculations via the automated SCALE sequence CSAS25. The cross-section data were processed by the SCALE automated problem-dependent resonance-processing procedure included in this sequence. Prior to calling KENO V.a, CSAS25 accesses BONAMI to perform resonance self-shielding for nuclides with Bondarenko factors and NITAWL-II to process nuclides with resonance parameter data via the Nordheim Integral Treatment

Creation and validation of a neutron-gamma coupled multigroup cross section library

International Nuclear Information System (INIS)

Devan, K.; Gopalakrishnan, V.; Lee, S.M.

1995-01-01

The task of creating our own neutron-gamma coupled library was taken up. By using 1985 version of NJOY code system, a coupled set called IGC-DE4-S1 in ANISN format for 25 nuclides has been arrived at based on ENDF/B-IV neutron library and DLC-99 gamma library, with Legendre order of up to 5. The flow chart for the creation of coupled set is given. 5 refs, 1 fig., 3 tabs

Zero-base budgeting and the library.

Science.gov (United States)

Sargent, C W

1978-01-01

This paper describes the application of zero-base budgeting to libraries and the procedures involved in setting up this type of budget. It describes the "decision packages" necessary when this systmem is employed, as well as how to rank the packages and the problems which are related to the process. Zero-base budgeting involves the entire staff of a library, and the incentive engendered makes for a better and more realistic budget. The paper concludes with the problems which one might encounter in zero-base budgeting and the major benefits of the system. PMID:626795

AXMIX program for cross section mixing and library arrangement

International Nuclear Information System (INIS)

Haynes, G.C.

1976-03-01

AXMIX is a FORTRAN IV computer code written to provide the user a tool for creating cross-section data sets for ANISN and DOT from cross-section sets already available on cards, nuclide-organized libraries, and group-independent data sets. Numerous options, including adjointing, P/sub n/ adjustments, and changing table length, are available to give the user broad flexibility. The number of energy groups which will fit into the core allocated is determined first. If all groups will fit, the solution is straightforward; if not, then the maximum number of groups which will fit is processed repeatedly by using direct access I/O and storage disks. Some flexibility in applying AXMIX is lost when cross sections to be processed contain upscatter. A special section on upscatter is included in the report. AXMIX is written for IBM System 360 computers with at least 150K bytes of memory. Problems of a practical nature require from 2 to 20 seconds of CPU time on a 360/91 computer. Running time is inversely proportional to the number of groups of data which will fit into core memory. I/O time is 50 to 100 times CPU time

Mixture-based combinatorial libraries from small individual peptide libraries: a case study on α1-antitrypsin deficiency.

Science.gov (United States)

Chang, Yi-Pin; Chu, Yen-Ho

2014-05-16

The design, synthesis and screening of diversity-oriented peptide libraries using a "libraries from libraries" strategy for the development of inhibitors of α1-antitrypsin deficiency are described. The major buttress of the biochemical approach presented here is the use of well-established solid-phase split-and-mix method for the generation of mixture-based libraries. The combinatorial technique iterative deconvolution was employed for library screening. While molecular diversity is the general consideration of combinatorial libraries, exquisite design through systematic screening of small individual libraries is a prerequisite for effective library screening and can avoid potential problems in some cases. This review will also illustrate how large peptide libraries were designed, as well as how a conformation-sensitive assay was developed based on the mechanism of the conformational disease. Finally, the combinatorially selected peptide inhibitor capable of blocking abnormal protein aggregation will be characterized by biophysical, cellular and computational methods.

Neutron Cross Section Libraries for Cryogenic Aromatic Moderator Materials

International Nuclear Information System (INIS)

Cantargi, Florencia; Granada, J.R.; Sbaffoni, Maria Monica

2008-01-01

The dynamics of a set of aromatic hydrocarbons, such as benzene, toluene, mesitylene and a 3:2 mixture (by volume) of mesitylene and toluene, all of them in solid phase, was studied as potential moderator materials for cold neutron sources. Cross section libraries were generated for hydrogen bounded in those materials, at several temperatures in ACE format, and they were used in MCNP calculations to analyze their neutron production compared with traditional materials like solid methane and liquid hydrogen. In particular, cross section libraries were generated at 20 K, which is the operating temperature of the majority of the existing cold neutron sources. Although solid methane is the best moderator in terms of cold neutron production, it has very poor radiation resistance, causing spontaneous burping even at fairly low doses. Such effect is considerably reduced in the aromatic hydrocarbons. On the other hand, all of them show a similar and significant neutron production, with the exception of benzene. Even though those aromatic materials are very easy to handle, the solid phases that produce an enhanced flux of cold neutrons correspond to amorphous structures rich in low-energy excitations, and they can be created through lengthy cooling processes requiring in many cases additional annealing stages. The 3:2 mesitylene-toluene mixture, that forms in a simple and direct manner the appropriate disordered structure, constitutes an excellent cryogenic moderator material, as it is able to produce an intense flux of cold neutrons while presenting high resistance to radiation, thus conforming a new and advantageous alternative to traditional moderator materials. (authors)

Information provision in medical libraries: An evidence based ...

African Journals Online (AJOL)

The paper examined information provision in special libraries such as medical libraries. It provides an overview of evidence based practice as a concept for information provision by librarians. It specifically proffers meaning to the term evidence as used in evidence based practice and to evidence based medicine from where ...

New ENDF/B-7.0 library

International Nuclear Information System (INIS)

Oblozinsky, P.

2008-01-01

We describe the new version of the Evaluated Nuclear Data File, Endf/B-7.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, produced by the US Cross Section Evaluation Working Group, was released in December 2006. The library contains data in 14 sub-libraries, primarily for reactions with incident neutrons, protons and photons, based on the experimental data and nuclear reaction theory predictions. The neutron reaction sub-library contains data for 393 materials. The new library was extensively tested and shows considerable improvements over the earlier Endf/B-6.8 library. (author)

Web-Based Instruction: A Guide for Libraries, Third Edition

Science.gov (United States)

Smith, Susan Sharpless

2010-01-01

Expanding on the popular, practical how-to guide for public, academic, school, and special libraries, technology expert Susan Sharpless Smith offers library instructors the confidence to take Web-based instruction into their own hands. Smith has thoroughly updated "Web-Based Instruction: A Guide for Libraries" to include new tools and trends,…

Evidence Based Management as a Tool for Special Libraries

Directory of Open Access Journals (Sweden)

Bill Fisher

2007-12-01

Full Text Available Objective ‐ To examine the evidence based management literature, as an example of evidence based practice, and determine how applicable evidence based management might be in the special library environment. Methods ‐ Recent general management literature and the subject‐focused literature of evidence based management were reviewed; likewise recent library/information science management literature and the subject‐focused literature of evidence based librarianshipwere reviewed to identify relevant examples of the introduction and use of evidence based practice in organizations. Searches were conducted in major business/management databases, major library/information science databases, and relevant Web sites, blogs and wikis. Citation searches on key articles and follow‐up searches on cited references were also conducted. Analysis of the retrieved literature was conducted to find similarities and/or differences between the management literature and the library/information scienceliterature, especially as it related to special libraries.Results ‐ The barriers to introducing evidence based management into most organizations were found to apply to many special libraries and are similar to issues involved with evidence based practice in librarianship in general. Despite these barriers, a set of resources to assist special librarians in accessing research‐based information to help them use principles of evidence based management is identified.Conclusion ‐ While most special librarians are faced with a number of barriers to using evidence based management, resources do exist to help overcome these obstacles.

Development of ANJOYMC Program for Automatic Generation of Monte Carlo Cross Section Libraries

International Nuclear Information System (INIS)

Kim, Kang Seog; Lee, Chung Chan

2007-03-01

The NJOY code developed at Los Alamos National Laboratory is to generate the cross section libraries in ACE format for the Monte Carlo codes such as MCNP and McCARD by processing the evaluated nuclear data in ENDF/B format. It takes long time to prepare all the NJOY input files for hundreds of nuclides with various temperatures, and there can be some errors in the input files. In order to solve these problems, ANJOYMC program has been developed. By using a simple user input deck, this program is not only to generate all the NJOY input files automatically, but also to generate a batch file to perform all the NJOY calculations. The ANJOYMC program is written in Fortran90 and can be executed under the WINDOWS and LINUX operating systems in Personal Computer. Cross section libraries in ACE format can be generated in a short time and without an error by using a simple user input deck

Production and testing of the ENEA-Bologna VITJEFF32.BOLIB (JEFF-3.2) multi-group (199 n + 42 γ) cross section library in AMPX format for nuclear fission applications

Science.gov (United States)

Pescarini, Massimo; Orsi, Roberto; Frisoni, Manuela

2017-09-01

The ENEA-Bologna Nuclear Data Group produced the VITJEFF32.BOLIB multi-group coupled neutron/photon (199 n + 42 γ) cross section library in AMPX format, based on the OECD-NEA Data Bank JEFF-3.2 evaluated nuclear data library. VITJEFF32.BOLIB was conceived for nuclear fission applications as European counterpart of the ORNL VITAMIN-B7 similar library (ENDF/B-VII.0 data). VITJEFF32.BOLIB has the same neutron and photon energy group structure as the former ORNL VITAMIN-B6 reference library (ENDF/B-VI.3 data) and was produced using similar data processing methodologies, based on the LANL NJOY-2012.53 nuclear data processing system for the generation of the nuclide cross section data files in GENDF format. Then the ENEA-Bologna 2007 Revision of the ORNL SCAMPI nuclear data processing system was used for the conversion into the AMPX format. VITJEFF32.BOLIB contains processed cross section data files for 190 nuclides, obtained through the Bondarenko (f-factor) method for the treatment of neutron resonance self-shielding and temperature effects. Collapsed working libraries of self-shielded cross sections in FIDO-ANISN format, used by the deterministic transport codes of the ORNL DOORS system, can be generated from VITJEFF32.BOLIB through the cited SCAMPI version. This paper describes the methodology and specifications of the data processing performed and presents some results of the VITJEFF32.BOLIB validation.

Production and testing of the ENEA-Bologna VITJEFF32.BOLIB (JEFF-3.2 multi-group (199 n + 42 γ cross section library in AMPX format for nuclear fission applications

Directory of Open Access Journals (Sweden)

Pescarini Massimo

2017-01-01

Full Text Available The ENEA-Bologna Nuclear Data Group produced the VITJEFF32.BOLIB multi-group coupled neutron/photon (199 n + 42 γ cross section library in AMPX format, based on the OECD-NEA Data Bank JEFF-3.2 evaluated nuclear data library. VITJEFF32.BOLIB was conceived for nuclear fission applications as European counterpart of the ORNL VITAMIN-B7 similar library (ENDF/B-VII.0 data. VITJEFF32.BOLIB has the same neutron and photon energy group structure as the former ORNL VITAMIN-B6 reference library (ENDF/B-VI.3 data and was produced using similar data processing methodologies, based on the LANL NJOY-2012.53 nuclear data processing system for the generation of the nuclide cross section data files in GENDF format. Then the ENEA-Bologna 2007 Revision of the ORNL SCAMPI nuclear data processing system was used for the conversion into the AMPX format. VITJEFF32.BOLIB contains processed cross section data files for 190 nuclides, obtained through the Bondarenko (f-factor method for the treatment of neutron resonance self-shielding and temperature effects. Collapsed working libraries of self-shielded cross sections in FIDO-ANISN format, used by the deterministic transport codes of the ORNL DOORS system, can be generated from VITJEFF32.BOLIB through the cited SCAMPI version. This paper describes the methodology and specifications of the data processing performed and presents some results of the VITJEFF32.BOLIB validation.

Development of the CANDU 66-group SN transport library

International Nuclear Information System (INIS)

Tsang, K.T.

2001-01-01

The design of the shield configuration around a nuclear reactor is strongly dependent on the neutron and photon spatial and energy distributions. The nuclear heat deposition and material damage in and surrounding the reactor core are also a function of the neutron and photon distributions. Therefore, to ensure a suitable configuration of materials for shielding or heat transfer, an accurate calculation of the particle fluxes in the reactor systems is essential. The CANDU 66-group library was developed to update the cross sections that are needed to assess the performance of CANDU bulk shields. Since about 1980, shielding analysts at Atomic Energy of Canada Limited (AECL) and Ontario Power Generation Inc. (OPGI) have been using a 38-group CANDU-specific library to perform S N transport calculations. In 1994, a new CANDU 67-group cross-section library was developed. The 67-group cross-section library was developed to provide radiation-physics analysts with up-to-date nuclear data to correct deficiencies with documentation of the old library. Although there were improvements over the 38-group library, initial use showed there were some deficiencies in the 67-group library. To correct these deficiencies, the CANDU 66-group S N transport cross-section library was developed. The 66-group library is based on the 241-group cross-section library VITAMIN-B6. Collapsing and weighting of the 241-group cross sections into 66 groups were performed using the modular code system SCALE 4.4. This paper describes how the modules in the SCALE system were applied to generate the 66-group library. The CANDU 66-group library includes both core-weighted and lattice-weighted cross sections of 235 U, 238 U, and 239 Pu with, and without, delayed fission-product photons. In addition, the 66-group library contains more response functions than did the 67-group library. Finally, the CANDU 66-group library has been validated against one-dimensional benchmark problems. The results generated with

Research of the application of multi-group libraries based on ENDF/B-VII library in the reactor design

International Nuclear Information System (INIS)

Mi Aijun; Li Junjie

2010-01-01

In this paper the multi-group libraries were constructed by processing ENDF/B-VII neutron incident files into multi-group structure, and the application of the multi-group libraries in the pressurized-water reactor(PWR) design was studied. The construction of the multi-group library is realized by using the NJOY nuclear data processing system. The code can process the neutron cross section files form ENDF format to MATXS format which was required in SN code. Two dimension transport theory code of discrete ordinates DORT was used to verify the multi-group libraries and the method of the construction by comparing calculations for some representative benchmarks. We made the PWR shielding calculation by using the multi-group libraries and studied the influence of the parameters involved during the construction of the libraries such as group structure, temperatures and weight functions on the shielding design of the PWR. This work is the preparation for the construction of the multi-group library which will be used in PWR shielding design in engineering. (authors)

FENDL multigroup libraries

International Nuclear Information System (INIS)

Ganesan, S.; Muir, D.W.

1992-01-01

Selected neutron reaction nuclear data libraries and photon-atomic interaction cross section libraries for elements of interest to the IAEA's program on Fusion Evaluated Nuclear Data Library (FENDL) have been processed into MATXSR format using the NJOY system on the VAX4000 computer of the IAEA. This document lists the resulting multigroup data libraries. All the multigroup data generated are available cost-free upon request from the IAEA Nuclear Data Section. (author). 9 refs

New data libraries for transmutation studies

Energy Technology Data Exchange (ETDEWEB)

Kloosterman, J.L. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Hoogenboom, J.E. [Interfaculty Reactor Inst., Delft (Netherlands)

1995-06-01

The fuel depletion code ORIGEN-S is often used for transmutation studies. It uses three different working libraries for actinides, fission products, and light elements, which contain decay data, cross-section data and fission product yields. These data have been renewed with data based on the JEF2.2 and the EAF3 evaluated files. Furthermore, data for 201 fission products have been added to the libraries. The new data libraries are particular suitable for parameter studies and other introductory calculations. For more accurate calculations, it is advised to regularly update the cross sections of the most important actinides and fission products during the burnup sequence. (orig.).

New data libraries for transmutation studies

Energy Technology Data Exchange (ETDEWEB)

Kloosterman, J.L. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Hoogenboom, J.E. [Interfaculty Reactor Inst., Delft (Netherlands)

1995-12-31

The fuel depletion code ORIGEN-S is often used for transmutations studies. It uses three different working libraries for actinides, fission products, and light elements, which contain decay data, cross-section data and fission product yields. These data have renewed with data based on the JEF2.2 and the EAF3 evaluated files. Furthermore, data for 201 fission products have been added to the libraries. The new data libraries are particular suitable for parameter studies and other introductory calculations. For more accurate calculations, it is advised to regularly update the cross sections of the most important actinides and fission products during the burnup sequence. (author) 9 refs.

Establishing a PWR burn-up library

International Nuclear Information System (INIS)

Lutz, D.C.

1981-01-01

Starting out from data file ENDF/B IV /1/, a cross-section library has been established for the calculation of operating conditions in pressurized water reactors of the type used in BIBLIS B. The library includes macroscopic, homogenized 2-group cross-sections for all types of fuel elements used in this reactor, including those equipped with boron glass rods. For their calculation the previous irradiation of the fuel has been taken into consideration by approximation. Information on fuel consumption from cell burn-up calculations has been stored in a separate data file. It was designed as a base for the determination of cross sections to be used in the calculation of the incident ''main-steam pipe fracture''. For this library the description of cross sections as a function of the moderator status chose the water densities at 300 0 C/155 bar, 190 0 C/140 bar and 100 0 C/100 bar as fixed values. The burn-up library has been tested by a three-dimensional calculation for the 1sup(st) cycle of the BIBLIS B-reactor using program QUABOX /2/. This showed variances with the anticipated course concerning critically, which can be explained almost quantitatively by known deficiencies of the ENDF/b-IV library. (orig.) [de

Modernization of Cross Section Library for VVER-1000 Type Reactors Internals and Pressure Vessel Dosimetry

Directory of Open Access Journals (Sweden)

Voloschenko Andrey

2016-01-01

Full Text Available The broad-group library BGL1000_B7 for neutron and gamma transport calculations in VVER-1000 internals, RPV and shielding was carried out on a base of fine-group library v7-200n47g from SCALE-6 system. The comparison of the library BGL1000_B7 with the library v7-200n47g and the library BGL1000 (the latter is using for VVER-1000 calculations is demonstrated on several calculation and experimental tests.

Generation of seven group cross section library for TRIGA LEU fuel in CITATION format and benchmarking some experimental and operational data

International Nuclear Information System (INIS)

Sarker, M.M.; Bhuiyan, S.I.; Akramuzzaman, M.

2007-01-01

The principal objective of this study is to validate the seven group cross section library in CITATION format for TRIGA LEU Fuel. This presentation deals with the 'generation of a cross section library for the CITATION and its validation. We used WIMSD-5B version for the generation of all group constants. The overall strategy is: (1) use WIMS package to generate few group neutron macroscopic cross section (cell constants) for all of the materials in the core and its immediate neighborhood (2) use 3-D code CITATION to perform the global analysis of the core to study: multiplication factor, neutron flux distribution and power peaking factors. Various options available in WIMS program were studied in depth to finalize the models to generate the most appropriate group constants. For the global analysis the code CITATION and a post processing program FCAP were chosen. Thus a seven group cross section library for the calculations of TRIGA Research Reactor was generated. To investigate the validity of the generated library a critical experiment of the TRIGA research reactor was benchmarked. (author)

IFLA General Conference, 1986. Special Libraries Division. Section: Science and Technology Libraries. Papers.

Science.gov (United States)

International Federation of Library Associations and Institutions, The Hague (Netherlands).

Papers on science and technology libraries which were presented at the 1986 International Federation of Library Associations (IFLA) conference include: (1) "Online Information Service of the Japan Information Center of Science and Technology" (Ryuko Igarashi, Japan); (2) "A View from the Chip--The Influence of Information…

Fee-based services in sci-tech libraries

CERN Document Server

Mount, Ellis

2013-01-01

This timely and important book explores how fee-based services have developed in various types of sci-tech libraries. The authoritative contributors focus on the current changing financial aspects of the sci-tech library operation and clarify for the reader how these changes have brought about conditions in which traditional methods of funding are no longer adequate. What new options are open and how they are best being applied in today's sci-tech libraries is fully and clearly explained and illustrated. Topics explored include cost allocation and cost recovery, fees for computer searching, an

[Progress in the spectral library based protein identification strategy].

Science.gov (United States)

Yu, Derui; Ma, Jie; Xie, Zengyan; Bai, Mingze; Zhu, Yunping; Shu, Kunxian

2018-04-25

Exponential growth of the mass spectrometry (MS) data is exhibited when the mass spectrometry-based proteomics has been developing rapidly. It is a great challenge to develop some quick, accurate and repeatable methods to identify peptides and proteins. Nowadays, the spectral library searching has become a mature strategy for tandem mass spectra based proteins identification in proteomics, which searches the experiment spectra against a collection of confidently identified MS/MS spectra that have been observed previously, and fully utilizes the abundance in the spectrum, peaks from non-canonical fragment ions, and other features. This review provides an overview of the implement of spectral library search strategy, and two key steps, spectral library construction and spectral library searching comprehensively, and discusses the progress and challenge of the library search strategy.

AUTOMATION BASED LIBRARY MANAGEMENT IN DEPOK PUBLIC LIBRARY IN THE CONTEXT OF RITUAL PERFORMANCE

Directory of Open Access Journals (Sweden)

Rafiqa Maulidia

2017-06-01

Full Text Available Library management using manual system is no longer adequate to handle the workload in the library routines, librarians must use application of library automation. To provide a good working performance, librarians use strategy, competences and certain habits, which are referred to as a ritual performance. The performance of the ritual is the demonstration of competence spontaneously by individuals in dealing with individuals, groups and organizations, which contains elements of personal ritual, the work ritual, social ritual, and organization ritual. The research focuses in the automation based library management in the context of the performance of the ritual. This study used a qualitative approach with case study method. The findings suggest that the personal ritual shows the personal habits of librarians to do their tasks, ritual librarian's work show responsibility towards their duties, social rituals strengthen the emotional connection between librarians and leaders, as well as ritual organizations suggest the involvement of librarians in giving their contribution in decision making. Conclusions of this study shows that the performance of rituals librarian at Depok Public Library gives librarians the skills to implement automation systems in the library management, and reflect the values of responsibility, mutual trust, and mutual respect.   Key words : Library Management, Library Automation, Ritual Performance, Ritual Performance Value

Establishment of the BOSPOR-80 machine library of evaluated threshold reaction cross-sections and its testing by means of integral experiments

International Nuclear Information System (INIS)

Bychkov, V.M.; Zolotarev, K.I.; Pashchenko, A.B.; Plyaskin, V.I.

1982-08-01

A paper was published in 1979 containing a compilation of experimental data on the cross-sections of (n,p), (n,α) and (n,2n) threshold reactions and recommended excitation functions. A further paper considered the development of evaluation methods based on the use of theoretical model calculations, an increase in the number of recommended excitation functions, correction of the recommended cross-sections on the basis of integral experiments and allowance for recent experimental data. To satisfy the wide circle of users, BOSPOR-80 - a machine library of evaluated threshold reaction cross-sections - was set up

Bonderenko self-shielded cross sections and multiband parameters derived from the LLL Evaluated-Nuclear-Data Library (ENDL)

International Nuclear Information System (INIS)

Cullen, D.E.

1978-01-01

Bonderenko self-shielded cross sections and multiband parameters from the Lawrence Livermore Laboratory Evaluated-Nuclear-Data Library (ENDL) as of July 4, 1978 are presented. These data include total, elastic, capture, and fission cross sections in the TART 175 group structure. Multiband parameters are listed. Bonderenko self-shielded cross section and the multiband parameters are presented on microfiche

MARS-ORNL, Processing Program Collection for AMPX, CCCC, ANISN, DOT, MORSE Format Library. LINX, MINX Library Utility, Data Merge. BINX, MINX Utility and SPHINX Utility, BCD to BIN Library Conversion. CINX, MINX Utility and SPHINX Utility, Library Data Collapsing

International Nuclear Information System (INIS)

2001-01-01

Description of problem or function: MARS-ORNL is a selection of computer codes for the generation of problem-dependent multigroup cross section libraries. They are selected modules from the AMPX-2 system for AMPX interface format libraries, LASL codes for CCCC interfaces, and processing codes for libraries to be used by ANISN, DOT, or MORSE codes. The codes in the collection are used in connection with the following DLC data libraries: ZZ-LIB-IV (DLC-0040), ZZ-VITAMIN-C (DLC-0041), VITAMIN-4C (DLC-0053), ZZ-CLEAR/42B (DLC-0042), ZZ-CSRL/43B (DLC-0043), and EPRMASTER (DLC-0052). The functions of these processing codes are briefly described: A. AMPX Modules: AIM: Converts AMPX Master Interface Files from EBCDIC to binary form and back. AJAX: Merges, collects, assembles, re-orders, joins, and copies selected nuclides from AMPX Master Interfaces. BONAMI: Accesses Bondarenko factors from an AMPX Master Library and performs resonance self-shielding calculations. CHOX: Produces a coupled interface library in AMPX format by combining neutron libraries (generated by module XLACS), gamma libraries (generated by module SMUG), and photon production libraries (generated by module LAPHNGAS). CHOXM: Combines self-shielding factors as generated by the code SPHINX (PSR-0129) and an infinite dilution neutron master interface (generated by XLACS) to generate a self-shielded neutron AMPX Interface File. The interface produced by CHOXM is an input to the NITAWL module of AMPX. CHOXM is a modified version of CHOX. COMAND: Collapses ANISN cross section libraries. DIAL: Produces edits from AMPX Master Interfaces. ICE-II: Accepts cross sections from an AMPX working library and produces mixed cross sections in four formats: (1) AMPX working library format; (2) ANISN format; (3) group-independent ANISN format; (4) Monte Carlo processed cross section library format. NITAWL: Produces self-shielded and working cross section libraries in the formats required by the ANISN, DOT, or MORSE codes

Activity-Based Costing in User Services of an Academic Library.

Science.gov (United States)

Ellis-Newman, Jennifer

2003-01-01

The rationale for using Activity-Based Costing (ABC) in a library is to allocate indirect costs to products and services based on the factors that most influence them. This paper discusses the benefits of ABC to library managers and explains the steps involved in implementing ABC in the user services area of an Australian academic library.…

Shaping the Electronic Library--The UW-Madison Approach.

Science.gov (United States)

Dean, Charles W., Ed.; Frazier, Ken; Pope, Nolan F.; Gorman, Peter C.; Dentinger, Sue; Boston, Jeanne; Phillips, Hugh; Daggett, Steven C.; Lundquist, Mitch; McClung, Mark; Riley, Curran; Allan, Craig; Waugh, David

1998-01-01

This special theme section describes the University of Wisconsin-Madison's experience building its Electronic Library. Highlights include integrating resources and services; the administrative framework; the public electronic library, including electronic publishing capability and access to World Wide Web-based and other electronic resources;…

IAEA nuclear data for applications: Cross section standards and the reference input parameter library (RIPL)

International Nuclear Information System (INIS)

Capote Noy, Roberto; Nichols, Alan L.; Pronyaev, Vladimir G.

2003-01-01

develop a library of validated nuclear-model input parameters, referred to as the Reference Input Parameter Library (RIPL). The first stage of this work was initiated in 1994 and the second step began in 1998, both as IAEA CRPs. A consistent library of recommended nuclear theoretical input parameters is now available (RIPL-2) that includes a large amount of theoretical information suitable for nuclear reaction calculations, along with a number of computer codes for parameter retrieval and related calculations. A third further phase of this project has been recently initiated in order to extend the applicability of the RIPL library to cross sections for reactions on nuclei far from the line of stability, incident energies up to 200 MeV, and reactions induced by charged particles. (authors)

NJOY processed multigroup library for fast reactor applications and point data library for MCNP - Experience and validation

International Nuclear Information System (INIS)

Kim Jung-Do; Gil Choong-Sup

1996-01-01

JEF-1-based 50-group cross section library for fast reactor applications and point data library for continuous-energy Monte Carlo code MCNP have been generated using NJOY91.38 system. They have been examined by analyzing measured integral quantities such as criticality and central reaction rate ratios for 8 small fast critical assemblies. (author). 9 refs, 2 figs, 10 tabs

Benchmarking of multigroup neutron cross sections libraries on neutron transmission through WWER-440 vessel

International Nuclear Information System (INIS)

Ilieva, K.; Belousov, S.; Apostolov, T.

1998-01-01

The verification of calculated neutron fluence onto the WWER-440/230 pressure vessel is very topical task in particular referring that some of this type of reactors have been operated the major part of its design lifetime. Since the induced activity from the neutron irradiation onto the elements is a simple response of neutron flux the neutron fluence verification usually is done using the measured activity of radionuclides produced during reactor operation. Calculational and experimental results of 54 Mn induced activity of scraps from inner wall of Unit 1 reactor pressure vessel after 18th cycle and detectors irradiated behind the vessel during the 18th cycle of Unit 1 at Kozloduy NPP as well as neutron flux attenuation through the WWER-440/230 pressure vessel are presented. Neutron cross sections libraries generated on the base of ENDF/B-IV and ENDF/B-VI have been used in the calculations. The comparative analysis of evaluated activities and attenuation coefficient demonstrates the better reliability of the neutron fluence calculations by the libraries based on ENDF/B-VI than by ones on ENDF/B-IV. The extreme rarity of data for the activity of scraps from the WWER-440 reactor vessel and its combination with the data for the detectors irradiated behind the vessel makes them especially attractive for verification of calculational methods of neutron fluence onto the WWER-440 vessel with dummy cassettes loading. (author)

Dendrimer-based dynamic combinatorial libraries

NARCIS (Netherlands)

Chang, T.; Meijer, E.W.

2005-01-01

The aim of this project is to create water-sol. dynamic combinatorial libraries based upon dendrimer-guest complexes. The guest mols. are designed to bind to dendrimers using multiple secondary interactions, such as electrostatics and hydrogen bonding. We have been able to incorporate various guest

Application of a new cross section library based on ENDF/B-IV to reactor core analysis

International Nuclear Information System (INIS)

Lima Bezerra, J. de.

1991-04-01

The use of the ENDF/B-IV library in the LEOPARD code for the Angra-1 reactor simulation is presented. The results are compared to those obtained using the ENDF/B-II library and show better values for the power distribution but an underestimated global reactivity as compared to experimental results. (F.E.). 1 ref, 55 figs, 1 tab

Achievement and qualification of multigroup cross-section library for light water reactor calculation

International Nuclear Information System (INIS)

Gastaldi, B.

1986-07-01

This study intends to improve then to check on integral experiments, the calculation of the main neutronic parameters in light water moderated lattices: Uranium 238 capture and consequently Plutonium 239 build-up, multiplication factor, temperature coefficient. The first part of this work concerns the resonant reaction rate calculation method implemented in the APOLLO code, the so-called LIVOLANT and JEANPIERRE formalism. The errors introduced by the corresponding assumptions are quantified and we propose substitution methods which avoid large biases and supply satisfactory results. The second part is dedicated to the cross-section evaluation of uranium major isotopes and to the achievement of APOLLO multigroup cross-sections. This cross-section set takes into considerations on the one hand the recent differential information and the other hand the various integral information obtained in the French Atomic Energy Commission facilities. The nuclear data file (JEF abd ENDF/B5) processing, for multigroup and self-shielded cross-sections achieving enable us to check the new THEMIS computer code. In the last part, the experimental validation of the proposed procedure (accurate formalism mutuel shielding and new multigroup library) is presented. This qualification is based on the reinterpretation of critical experiments performed in the EOLE reactor at Cadarache and spent fuel analysis. The corresponding results demonstrate that our propositions provide improvements on the computation of the PWR neutronic parameters; calculation-experiment discrepancies are now consistent with experimental uncertainty margins. 46 refs; 31 figs; 23 tabl [fr

Validation of KENO V.a. and two cross-section libraries for criticality calculations of low-enriched uranium systems

International Nuclear Information System (INIS)

Easter, M.E.

1985-07-01

The SCALE code system, utilizing the Monte Carlo computer code KENO V.a, was employed to calculate 37 critical experiments. The critical assemblies had 235 U enrichments of 5% or less and cover a variety of geometries and materials. Values of k/sub eff/ were calculated using two different results using either of the cross-section libraries. The 16-energy-group Hansen-Roach and the 27-energy-group ENDF/B-IV cross-section libraries, available in SCALE, were used in this validation study, and both give good results for the experiments considered. It is concluded that the code and cross sections are adequate for low-enriched uranium systems and that reliable criticality safety calculations can be made for such systems provided the limits of validated applicability are not exceeded

WIMS Library updating

International Nuclear Information System (INIS)

Ravnik, M.; Trkov, A.; Holubar, A.

1992-01-01

At the end of 1990 the WIMS Library Update Project (WLUP) has been initiated at the International Atomic Energy Agency. The project was organized as an international research project, coordinated at the J. Stefan Institute. Up to now, 22 laboratories from 19 countries joined the project. Phase 1 of the project, which included WIMS input optimization for five experimental benchmark lattices, has been completed. The work presented in this paper describes also the results of Phase 2 of the Project, in which the cross sections based on ENDF/B-IV evaluated nuclear data library have been processed. (author) [sl

Library of neutron cross sections of the Thermos code; Biblioteca de secciones eficaces de neutrones del codigo Thermos

Energy Technology Data Exchange (ETDEWEB)

Alonso V, G; Hernandez L, H [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1991-10-15

The present work is the complement of the IT.SN/DFR-017 report in which the structure and the generation of the library of the Thermos code is described. In this report the comparison among the values of the cross sections that has the current library of the Thermos code and those generated by means of the ENDF-B/NJOY it is shown. (Author)

Views From the Pacific--Military Base Hospital Libraries in Hawaii and Guam.

Science.gov (United States)

Stephenson, Priscilla L; Trafford, Mabel A; Hadley, Alice E

2016-01-01

Hospital libraries serving military bases offer a different perspective on library services. Two libraries located on islands in the Pacific Ocean provide services to active duty service men and women, including those deployed to other regions of the world. In addition, these hospital libraries serve service members' families living on the base, and often citizens from the surrounding communities.

Comparison of CASMO and NESSEL few group cross section libraries and their usage in DYN3D

International Nuclear Information System (INIS)

Kuchin, A.; Ovdiyenko, Y.; Loetsch, T.

2007-01-01

This work presents comparative analysis of two group diffusion cross sections libraries which were generated by NESSEL-4 and CASMO-4 lattice codes. Diffusion parameters were calculated for WWER-1000 fuel assemblies with stainless steel spacing grids and guiding tubes. These cross section sets were introduced into reactor core code DYN3D and tested on the base of real reactor core states. In this case operation data of the first three fuel cycles of sixth unit of Zaporizhzhya NPP were used. The work was performed in the framework of the order BMU SR 2511 - 862 500/09, UA-2575. The report describes the opinion and view of the contractor - TUV ENERGIE CONSULT - and does not necessarily represent the opinion of the ordering party - Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (Authors)

PROF-DD, Generator of Multigroup Cross-Sections Library DDX for MORSE-DD, ANISN-DD, DOT-DD

International Nuclear Information System (INIS)

Mori, Takamasa; Nakagawa, Masayuki; Ishiguro, Yukio

2002-01-01

1 - Description of program or function: The code system PROF-DD generates a multi-group double-differential cross section library DDX from evaluated data in ENDF/B-IV or ENDF/B-V format. The system consists of the following five modules: PROF-DDX is the main module of the system. It calculates the multigroup DDX and stores them on a master PDS file. MCFILEF generates a control file for PROF-DDX, which contains energy group and angle bin structures. SPINPTF prepares an input data file for PROF-DDX by combining the control file with other input data. DDXLIBMK edits a DDX library from the master PDS file for transport calculations. RESENDD performs resonance cross section and Doppler broadening calculations. 2 - Restrictions on the complexity of the problem: The numbers of energy groups and angle bins are less than 150 and 40, respectively

Validation of a new 39 neutron group self-shielded library based on the nucleonics analysis of the Lotus fusion-fission hybrid test facility performed with the Monte Carlo code

International Nuclear Information System (INIS)

Pelloni, S.; Cheng, E.T.

1985-02-01

The Swiss LOTUS fusion-fission hybrid test facility was used to investigate the influence of the self-shielding of resonance cross sections on the tritium breeding and on the thorium ratios. Nucleonic analyses were performed using the discrete-ordinates transport codes ANISN and ONEDANT, the surface-flux code SURCU, and the version 3 of the MCNP code for the Li 2 CO 3 and the Li 2 O blanket designs with lead, thorium and beryllium multipliers. Except for the MCNP calculation which bases on the ENDF/B-V files, all nuclear data are generated from the ENDF/B-IV basic library. For the deterministic methods three NJOY group libraries were considered. The first, a 39 neutron group self-shielded library, was generated at EIR. The second bases on the same group structure as the first does and consists of infinitely diluted cross sections. Finally the third library was processed at LANL and consists of coupled 30+12 neutron and gamma groups; these cross sections are not self-shielded. The Monte Carlo analysis bases on a continuous and on a discrete 262 group library from the ENDF/B-V evaluation. It is shown that the results agree well within 3% between the unshielded libraries and between the different transport codes and theories. The self-shielding of resonance cross sections results in a decrease of the thorium capture rate and in an increase of the tritium breeding of about 6%. The remaining computed ratios are not affected by the self-shielding of cross sections. (Auth.)

New ENDF/B-V nuclear data library for WIMS-D4M

International Nuclear Information System (INIS)

Deen, J.R.; Woodruff, W.L.; Costescu, C.I.

1994-01-01

A new 69-group 96-material library has been created for use in WIMS-D4M. The latest SUN version of NJOY (91.27) was used to generate the ENDF/B-V-based cross-section library. The library also includes ENDF/B-V based fission yields, energy fission and energy per capture data. The upper energy boundary has been extended from 10 to 20 MeV in order to model high energy neutron reactions. Additional fuel and moderator temperatures have been included to better predict temperature coefficients. More excess potential scattering points have been added to increase the accuracy of self-shielded resonance cross-sections. Several benchmark comparisons have been made to validate the new library. (author)

Automation Based Library Management in Depok Public Library In The Context of Ritual Performance

Directory of Open Access Journals (Sweden)

Rafiqa Maulidia

2018-01-01

Full Text Available Library management using manual system is no longer adequate to handle the workload in the library routines, librarians must use application of library automation. To provide a good working performance, librarians use strategy, competences and certain habits, which are referred to as a ritual performance. The performance of the ritual is the demonstration of competence spontaneously by individuals in dealing with individuals, groups and organizations, which contains elements of personal ritual, the work ritual, social ritual, and organization ritual. The research focuses in the automation based library management in the context of the performance of the ritual. This study used a qualitative approach with case study method. The findings suggest that the personal ritual shows the personal habits of librarians to do their tasks, ritual librarian's work show responsibility towards their duties, social rituals strengthen the emotional connection between librarians and leaders, as well as ritual organizations suggest the involvement of librarians in giving their contribution in decision making. Conclusions of this study shows that the performance of rituals librarian at Depok Public Library gives librarians the skills to implement automation systems in the library management, and reflect the values of responsibility, mutual trust, and mutual respect.

MENDF71x. Multigroup Neutron Cross Section Data Tables Based upon ENDF/B-VII.1

International Nuclear Information System (INIS)

Conlin, Jeremy Lloyd; Parsons, Donald Kent; Gardiner, Steven J.; Gray, Mark Girard; Lee, Mary Beth; White, Morgan Curtis

2015-01-01

A new multi-group neutron cross section library has been released along with the release of NDI version 2.0.20. The library is named MENDF71x and is based upon the evaluations released in ENDF/B-VII.1 which was made publicly available in December 2011. ENDF/B-VII.1 consists of 423 evaluations of which ten are excited states evaluations and 413 are ground state evaluations. MENDF71x was created by processing the 423 evaluations into 618-group, downscatter only NDI data tables. The ENDF/B evaluation files were processed using NJOY version 99.393 with the exception of 35 Cl and 233 U. Those two isotopes had unique properties that required that we process the evaluation using NJOY version 2012. The MENDF71x library was only processed to room temperature, i.e., 293.6 K. In the future, we plan on producing a multi-temperature library based on ENDF/B-VII.1 and compatible with MENDF71x.

Recommended activation detector cross sections (RNDL-82)

International Nuclear Information System (INIS)

Bondars, Kh.Ya.; Lapenas, A.A.

1984-01-01

The results of the comparison between measured and calculated average cross sections in 5 benchmark experiments are presented. Calculations have been based on the data from 10 libraries of evaluated cross sections. The recommended library (RNDL-82) of the activation detector cross sections has been created on the basis of the comparison. RNDL-82, including 26 reactions, and the basic characteristics of the detectors are presented. (author)

Assessing availability of scientific journals, databases, and health library services in Canadian health ministries: a cross-sectional study.

Science.gov (United States)

Léon, Grégory; Ouimet, Mathieu; Lavis, John N; Grimshaw, Jeremy; Gagnon, Marie-Pierre

2013-03-21

Evidence-informed health policymaking logically depends on timely access to research evidence. To our knowledge, despite the substantial political and societal pressure to enhance the use of the best available research evidence in public health policy and program decision making, there is no study addressing availability of peer-reviewed research in Canadian health ministries. To assess availability of (1) a purposive sample of high-ranking scientific journals, (2) bibliographic databases, and (3) health library services in the fourteen Canadian health ministries. From May to October 2011, we conducted a cross-sectional survey among librarians employed by Canadian health ministries to collect information relative to availability of scientific journals, bibliographic databases, and health library services. Availability of scientific journals in each ministry was determined using a sample of 48 journals selected from the 2009 Journal Citation Reports (Sciences and Social Sciences Editions). Selection criteria were: relevance for health policy based on scope note information about subject categories and journal popularity based on impact factors. We found that the majority of Canadian health ministries did not have subscription access to key journals and relied heavily on interlibrary loans. Overall, based on a sample of high-ranking scientific journals, availability of journals through interlibrary loans, online and print-only subscriptions was estimated at 63%, 28% and 3%, respectively. Health Canada had a 2.3-fold higher number of journal subscriptions than that of the provincial ministries' average. Most of the organisations provided access to numerous discipline-specific and multidisciplinary databases. Many organisations provided access to the library resources described through library partnerships or consortia. No professionally led health library environment was found in four out of fourteen Canadian health ministries (i.e. Manitoba Health, Northwest

Investigating User Interfaces of Non-Iranian Digital Libraries based on Social Bookmarking Capabilities and Characteristics to Use by Iranian Digital Libraries

Directory of Open Access Journals (Sweden)

Zahra Naseri

2016-08-01

Full Text Available Current study aims to investigate the status of user interfaces of non-Iranian digital libraries’ based on social bookmarking capabilities and characteristics to use by Iranian digital libraries. This research studies the characteristics and capabilities of top digital libraries’ user interfaces in the world based on social bookmarking used by library users. This capability facilitates producing, identifying, organizing, and sharing contents using tags. Survey method was used with descriptive-analytical approach in this study. Populations include non-Iranian digital libraries interfaces. Top ten digital libraries’ interfaces were selected as the sample. A researcher-made checklist prepared based on literature review and investigating four distinguished websites (Library Thing, Delicious, Amazon, and Google Book. Faced validity evaluated by 10 experts’ viewpoints, then reliability calculated 0.87.Findings of this study are important because of two reasons: first, it provides a comprehensive and an unambiguous vision for recognizing user interfaces’ basic capabilities and characteristics based on social bookmarking. Second, it can provide a base for designing digital libraries in Iran. The results showed that the majority of digital libraries around the world had not used web 2.0 characteristics such as producing, identifying, organizing, and sharing contents except two digital libraries (Google Books, and Ibiblio.

ORIGEN-S data libraries

International Nuclear Information System (INIS)

Ryman, J.C.

1984-01-01

There are five card-image nuclear data libraries: (1) a small light element library for 253 nuclides, (2) a large light element library for 687 nuclides, (3) an actinide library for 101 nuclides, (4) a small fission product library for 461 nuclides, and (5) a large fission product library for 821 nuclides. The data for each nuclide are contained on five card-image records. The first card image contains decay data (half-life, branching fractions, recoverable energy per decay and the fraction of recoverable energy from photons), percent natural abundance, and radioactivity concentration guides. The last four card images contain cross section and (for fission product nuclides) fission yield data for four reactor types (HTGR, LWR, LMFBR, and MSBR), with one card for each reactor type. The card-image nuclear data libraries are the basic libraries for ORIGEN-S. The code can be run using these libraries directly, or it can be run from a binary data library which (prior to any cross section or other nuclear data updating) was created by running the COUPLE code to convert one or more of these card-image libraries

ANITA-IEAF activation code package - updating of the decay and cross section data libraries and validation on the experimental data from the Karlsruhe Isochronous Cyclotron

Science.gov (United States)

Frisoni, Manuela

2017-09-01

ANITA-IEAF is an activation package (code and libraries) developed in the past in ENEA-Bologna in order to assess the activation of materials exposed to neutrons with energies greater than 20 MeV. An updated version of the ANITA-IEAF activation code package has been developed. It is suitable to be applied to the study of the irradiation effects on materials in facilities like the International Fusion Materials Irradiation Facility (IFMIF) and the DEMO Oriented Neutron Source (DONES), in which a considerable amount of neutrons with energies above 20 MeV is produced. The present paper summarizes the main characteristics of the updated version of ANITA-IEAF, able to use decay and cross section data based on more recent evaluated nuclear data libraries, i.e. the JEFF-3.1.1 Radioactive Decay Data Library and the EAF-2010 neutron activation cross section library. In this paper the validation effort related to the comparison between the code predictions and the activity measurements obtained from the Karlsruhe Isochronous Cyclotron is presented. In this integral experiment samples of two different steels, SS-316 and F82H, pure vanadium and a vanadium alloy, structural materials of interest in fusion technology, were activated in a neutron spectrum similar to the IFMIF neutron field.

New Standard Evaluated Neutron Cross Section Libraries for the GEANT4 Code and First Verification

CERN Document Server

Mendoza, Emilio; Koi, Tatsumi; Guerrero, Carlos

2014-01-01

The Monte Carlo simulation of the interaction of neutrons with matter relies on evaluated nuclear data libraries and models. The evaluated libraries are compilations of measured physical parameters (such as cross sections) combined with predictions of nuclear model calculations which have been adjusted to reproduce the experimental data. The results obtained from the simulations depend largely on the accuracy of the underlying nuclear data used, and thus it is important to have access to the nuclear data libraries available, either of general use or compiled for specific applications, and to perform exhaustive validations which cover the wide scope of application of the simulation code. In this paper we describe the work performed in order to extend the capabilities of the GEANT4 toolkit for the simulation of the interaction of neutrons with matter at neutron energies up to 20 MeV and a first verification of the results obtained. Such a work is of relevance for applications as diverse as the simulation of a n...

IFLA General Conference, 1985. Division on Special Libraries. Section on Science and Technology Libraries. Papers.

Science.gov (United States)

International Federation of Library Associations, The Hague (Netherlands).

Papers on science and technology libraries which were presented at the 1985 International Federation of Library Associations (IFLA) conference include: (1) "UAP (Universal Availability of Publications) and User Training for Categories of Grey Literature" (Dieter Schmidmaier, Mining Academy Freiberg, East Germany); (2) "Resource…

Development of the tool for generating ORIGEN2 library based on JENDL-3.2 for FBR

International Nuclear Information System (INIS)

Ohkawachi, Yasushi; Fukushima, Manabu

1999-05-01

ORIGEN2 is one of the most widely-used burnup analysis code in the world. This code has one-grouped cross section libraries compiled for various types of reactors. However, these libraries have some problems. One is that these libraries were developed from old nuclear data libraries (ENDF/B-IV,V) and the other is that core and fuel designs from which these libraries are generated do not match the current analysis. In order to solve the problems, analysis tool is developed for generating ORIGEN2 library from JENDL-3.2 considering multi-energy neutron spectrum. And eight new libraries are prepared using this tool for analysis of sodium-cooled FBR. These new libraries are prepared for eight kinds of cores in total. Seven of them are made by changing core size (small core - large core), fuel type (oxide, nitride, metal) and Pu vector as a parameter. The eighth one is a Pu burner core. Burnup calculation using both new and original libraries, shows large difference in buildup or depletion numbers of nuclides among the libraries. It is estimated that the analysis result is greatly influenced by the neutron spectrum which is used in collapse of cross section. By using this tool or new libraries, it seems to improve evaluation accuracy of buildup or depletion numbers of nuclides in transmutation research on FBR fuel cycle. (author)

ENDF/B-6 Photon Atomic Interaction Data Library

International Nuclear Information System (INIS)

Lemmel, H.D.

1990-09-01

The ENDF/B-6 version of the Photo-Atomic Interaction Data Library of the Livermore Evaluated Photon Data Library (EPDL) contains pair and triplet cross-sections, photoelectric cross-sections, atom form factors, coherent scattering cross-sections and some other data for all the elements from Z=1 to 100. The data library is available on magnetic tape costfree from the IAEA Nuclear Data Section. The library supersedes the earlier photo-atomic data library by the US Radiation Shielding Information Center RSIC that was included in the data libraries ENDF/B-5 and JEF-1. (author). Refs, figs and tabs

America's Star Libraries, 2010: Top-Rated Libraries

Science.gov (United States)

Lyons, Ray; Lance, Keith Curry

2010-01-01

The "LJ" Index of Public Library Service 2010, "Library Journal"'s national rating of public libraries, identifies 258 "star" libraries. Created by Ray Lyons and Keith Curry Lance, and based on 2008 data from the IMLS, it rates 7,407 public libraries. The top libraries in each group get five, four, or three stars. All included libraries, stars or…

Application of Data Mining in Library-Based Personalized Learning

Directory of Open Access Journals (Sweden)

Lin Luo

2017-12-01

Full Text Available this paper expounds to mine up data with the DBSCAN algorithm in order to help teachers and students find which books they expect in the sea of library. In the first place, the model that DBSCAN algorithm applies in library data miner is proposed, followed by the DBSCAN algorithm improved on demands. In the end, an experiment is cited herein to validate this algorithm. The results show that the book price and the inventory level in the library produce a less impact on the resultant aggregation than the classification of books and the frequency of book borrowings. Library procurers should therefore purchase and subscribe data based on the results from cluster analysis thereby to improve hierarchies and structure distribution of library resources, forging on the library resources to be more scientific and reasonable, while it is also conducive to arousing readers' borrowing interest.

Use of internet library based services by the students of Imo State ...

African Journals Online (AJOL)

Findings show that students utilizes internet based library services in their academic work, for their intellectual development as well as in communicating to their lecturers and other relations on their day to day information needs. It is recommended that University libraries should provide and offer internet based library ...

42 CFR 4.8 - Publication of the Library and information about the Library.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Publication of the Library and information about the Library. 4.8 Section 4.8 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL PROVISIONS NATIONAL LIBRARY OF MEDICINE § 4.8 Publication of the Library and information...

Generation and performance of a multigroup coupled neutron-gamma cross-section library for deterministic and Monte Carlo borehole logging analysis

International Nuclear Information System (INIS)

Kodeli, I.; Aldama, D. L.; De Leege, P. F. A.; Legrady, D.; Hoogenboom, J. E.; Cowan, P.

2004-01-01

As part of the IRTMBA (Improved Radiation Transport Modelling for Borehole Applications) project of the EU community's 5. framework program a special purpose multigroup cross-section library was prepared for use in deterministic and Monte Carlo oil well logging particle transport calculations. This library is expected to improve the prediction of the neutron and gamma spectra at the detector positions of the logging tool, and their use for the interpretation of the neutron logging measurements was studied. Preparation and testing of this library is described. (authors)

The WIMSLIB library - neutron data library for WIMS-D

International Nuclear Information System (INIS)

Liu Ping

1998-05-01

During a visit to the IAEA Nuclear Data Section from 13 June to 12 December 1997, the author processed the Chinese Evaluated Nuclear Data Library (CENDL), Version 2.1, using the NJOY Nuclear Data Processing System, Version 94.105, to generate the working library WIMSLIB for input to WIMS-D/4 and WIMS-D/5A. The WIMSLIB library was then used to perform benchmark testing of CENDL-2.1. (author)

Testing of the IRDF-90 cross-section library in benchmark neutron spectra

International Nuclear Information System (INIS)

Nolthenius, H.J.; Zsolnay, E.M.; Szondi, E.J.

1993-09-01

The new version of the International Reactor Dosimetry File IRDF-90 (called ''Version April 1993'') has been tested by calculation of average cross-sections and their uncertainties in a coarse three energy group structure and by neutron spectrum adjustments in reference neutron spectra. This paper presents the results obtained and compares them with the corresponding ones of the old IRDF-85 and with the data of the Nuclear Data Guide for Reactor Neutron Metrology. The applicability of the new library in the field of neutron metrology is discussed. (orig.)

Evaluation of computer-based library services at Kenneth Dike ...

African Journals Online (AJOL)

This study evaluated computer-based library services/routines at Kenneth Dike Library, University of Ibadan. Four research questions were developed and answered. A survey research design was adopted; using questionnaire as the instrument for data collection. A total of 200 respondents randomly selected from 10 ...

Production and testing of the VITAMIN-B6 fine-group and the BUGLE-93 broad-group neutron/photon cross-section libraries derived from ENDF/B-VI nuclear data

International Nuclear Information System (INIS)

Ingersoll, D.T.; White, J.E.; Wright, R.Q.; Hunter, H.T.; Slater, C.O.; Greene, N.M.; MacFarlane, R.E.

1993-01-01

A new multigroup cross-section library based on ENDF/B-VI data has been produced and tested for light water reactor shielding and reactor pressure vessel dosimetry applications. The broad-group library is designated BUGLE-93. The processing methodology is consistent with ANSI/ANS 6.1.2, since the ENDF data were first processed into a fine-group, ''pseudo problem-independent'' format and then collapsed into the final broad-group format. The fine-group library is designated VITAMIN-B6. An extensive integral data testing effort was also performed. In general, results using the new data show significant improvements relative to earlier ENDF data

Generation of SCALE 6 Input Data File for Cross Section Library of PWR Spent Fuel

International Nuclear Information System (INIS)

Jeong, Chang Joon; Cho, Dong Keun

2010-11-01

In order to obtain the cross section libraries of the Korean Pressurized water reactor (PWR) spent fuel (SF), SCALE 6 code input files have been generated. The PWR fuel data were obtained from the nuclear design report (NDR) of the current operating PWRs. The input file were prepared for 16 fuel types such as 4 types of Westinghouse 14x14, 3 types of OPR-1000 16x16, 4 types of Westinghouse 16x16, and 6 types of Westinghouse 17x17. For each fuel type, 5 kinds of fuel enrichments have been considered such as 1.5, 2.0 ,3.0, 4.0 and 5.0 wt%. In the SCALE 6 calculation, a ENDF-V 44 group was used. The 25 burnup step until 72000 MWD/T was used. A 1/4 symmetry model was used for 16x16 and 17x17 fuel assembly, and 1/2 symmetry model was used for 14x14 fuel assembly The generated cross section libraries will be used for the source-term analysis of the PWR SF

Documentation for WIMSD-formatted libraries based on ENDF/B-VII.1 evaluated nuclear data files with extended actinide burn-up chains and cross section data up to 2000 K for fuel materials

International Nuclear Information System (INIS)

López Aldama, Daniel

2014-11-01

In the frame of WIMS Library Update Project the WIMSD-IAEA-69 and WIMSD-IAEA-172 libraries were prepared and made available at the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). The main libraries were prepared from different sources of evaluated nuclear data that were available before December 2003. Also others WIMSD libraries were prepared from the major evaluated nuclear data libraries and made available at http://www-nds.iaea.org/wimsd. During the last ten years new libraries have been prepared every time that a major version of an evaluated nuclear data library has been released, namely JEFF-3.1 and ENDF/B-VII.0. Recently, end-users have requested to extend the temperature ranges of fuel materials included in the libraries and also to extend the burn-up chains to higher actinides up to Cf-254. The inclusion of new structural materials, like bismuth, has been also considered. Therefore, new WIMSD-formatted libraries in the 69- and 172-energy structure have been prepared with more materials, extended actinides burn-up chains and higher temperatures in thermal and resonance range

ENDL type formats for the LLNL Evaluated Atomic Data Library, EADL, for the Evaluated Electron Data Library, EEDL, and for the Evaluated Photon Data Library, EPDL

International Nuclear Information System (INIS)

Perkins, S.T.; Cullen, D.E.

1994-07-01

Over the past five years, Lawrence Livermore National Laboratory has published extensive compilations derived from three of its main atomic data libraries. These are specifically the evaluated atomic relaxation data library, EADL, the evaluated electron interaction data library, EEDL, and the evaluated photon interaction data library, EPDL. All of these libraries span atomic numbers, Z, from 1 to 100. Additionally the particle interaction libraries cover the incident particle energy range from 10 eV to 100 GeV. The purpose of these libraries is to furnish data for particle transport calculations. Thus the files have been released for external distribution in a machine independent characterize format. In a complete coupled electron-photon transport analysis, results from all three of the data files are required. Therefore it is reasonable to discuss the format for all three libraries in the same work; that is the approach taken here. This report is composed of three sections, each section describing one of the libraries. For ease of reading, each section is separate and unique unto itself, including its own table numbers and references. This report will accompany any request for copies of these evaluated data libraries. This report and these three data libraries are available from the data centers at Brookhaven National Laboratory, RSIC (Oak Ridge National Laboratory), OECD/NEA Data Bank (France), and IAEA (Vienna)

Structure-Based Virtual Screening of Commercially Available Compound Libraries.

Science.gov (United States)

Kireev, Dmitri

2016-01-01

Virtual screening (VS) is an efficient hit-finding tool. Its distinctive strength is that it allows one to screen compound libraries that are not available in the lab. Moreover, structure-based (SB) VS also enables an understanding of how the hit compounds bind the protein target, thus laying ground work for the rational hit-to-lead progression. SBVS requires a very limited experimental effort and is particularly well suited for academic labs and small biotech companies that, unlike pharmaceutical companies, do not have physical access to quality small-molecule libraries. Here, we describe SBVS of commercial compound libraries for Mer kinase inhibitors. The screening protocol relies on the docking algorithm Glide complemented by a post-docking filter based on structural protein-ligand interaction fingerprints (SPLIF).

Two-level MOC calculation scheme in APOLLO2 for cross-section library generation for LWR hexagonal assemblies

International Nuclear Information System (INIS)

Petrov, Nikolay; Todorova, Galina; Kolev, Nikola; Damian, Frederic

2011-01-01

The accurate and efficient MOC calculation scheme in APOLLO2, developed by CEA for generating multi-parameterized cross-section libraries for PWR assemblies, has been adapted to hexagonal assemblies. The neutronic part of this scheme is based on a two-level calculation methodology. At the first level, a multi-cell method is used in 281 energy groups for cross-section definition and self-shielding. At the second level, precise MOC calculations are performed in a collapsed energy mesh (30-40 groups). In this paper, the application and validation of the two-level scheme for hexagonal assemblies is described. Solutions for a VVER assembly are compared with TRIPOLI4® calculations and direct 281g MOC solutions. The results show that the accuracy is close to that of the 281g MOC calculation while the CPU time is substantially reduced. Compared to the multi-cell method, the accuracy is markedly improved. (author)

FENDL/MG. Library of multigroup cross sections in GENDF and MATXS format for neutron-photon transport calculations. Version 1.1 of March 1995. Summary documentation

International Nuclear Information System (INIS)

Pashchenko, A.B.; Wienke, H.; Ganesan, S.

1996-01-01

Selected neutron reaction nuclear data evaluations and photon-atomic interaction cross section libraries for elements of interest to the IAEA's program on Fusion Evaluated Nuclear Data Library (FENDL) have been processed into GENDF and MATXS format using the NJOY system by R.E. MacFarlane, in VITAMIN-J group structure with VITAMIN-E weighting spectrum. This document summarizes the resulting multigroup data library FENDL/MG version 1.1. The data are available costfree, upon request from the IAEA Nuclear Data Section, online or on magnetic tape. (author). 7 refs, 1 tab

Development of automatic editing system for MCNP library 'autonj'

International Nuclear Information System (INIS)

Maekawa, Fujio; Sakurai, Kiyoshi; Kume, Etsuo; Nomura, Yasushi; Kosako, Kazuaki; Kawasaki, Nobuo; Naito, Yoshitaka

1999-12-01

As an activity of the MCNP High-Temperature Library Production Working Group under the Nuclear Code Evaluation Special Committee of Nuclear Code Committee, the automatic editing system for MCNP library 'autonj' was developed. The autonj includes the NJOY-97 code as its main body, and is a system that enables us to easily produce cross section libraries for MCNP from evaluated nuclear data files such as JENDL-3.2. A temperature dependent library at six temperature points based on JENDL-3.2 was produced by using autonj. The autonj system and the temperature dependent library were installed on the JAERI AP3000 computer. (author)

Nuclear Data Libraries for Hydrogen in Light Water Ice

International Nuclear Information System (INIS)

Torres, L; Gillette, V.H

2000-01-01

Nuclear data libraries were produced for hydrogen (H) in light water ice at different temperatures, 20, 30, 50, 77, 112, 180, 230 K.These libraries were produced using the NJOY nuclear data processing system.With this code we produce pointwise cross sections and related quantities, in the ENDF format, and in the ACE format for MCNP.Experimental neutron spectra at such temperatures were compared with MCNP4B simulations, based on the locally produced libraries, leading to satisfactory results

Academic Library Department Experience Fosters the Development of Leadership Skills Relevant to Academic Library Directorship

Directory of Open Access Journals (Sweden)

Joanne M. Muellenbach

2017-03-01

Full Text Available A Review of: Harris-Keith, Colleen S. (2015. The Relationship Between Academic Library Department Experience and Perceptions of Leadership Skill Development Relevant to Academic Library Directorship. The Journal of Academic Librarianship, 41(3, 246-263. doi:10.1016/j.acalib.2015.03.017 Objective – This study sought to identify if the perception of library leadership skill and quality development is equal across departmental experience, and what are the leadership skills and qualities most commonly perceived to be used in each department. Design – Quantitative online survey instrument. Setting – Master’s colleges and universities from 728 institutions in the United States of America, as classified by the Carnegie Foundation. Subjects – 666 academic library directors. Methods – Selected participants, representing academic library administrative leadership, were contacted by email a maximum of four times and were invited to complete an online survey instrument composed of six sections. The first three sections contained the purpose and confidentiality statements, demographic information, and data on the past five positions held by respondents prior to their current directorship. The next two sections each had 25 statements on a 5-point Likert scale, to collect data on perceived leadership skills and qualities exercised by respondents in their most recent three positions. The final section had four open-ended questions to help explain the academic library directors’ responses and provide context for the ratings in previous sections of the instrument. Main results – A total of 296 responses were received, for a 40.66% response rate, which was representative of the institution type demographics, including private non-profit, public, and private for-profit. The first research question asked: is the perception of library leadership skill and quality development equal across departmental experience? The data used for this question

Nuclear data, cross section libraries and their application in nuclear technology

International Nuclear Information System (INIS)

1985-01-01

These proceedings contain the articles presented at the named seminar. The articles deal with evaluated nuclear data libraries, computer codes for neutron transport and reactor calculations using nuclear data libraries, and the application of nuclear data libraries for the calculation of the interaction of neutron beams with materials. (HSI)

Libraries from the Inside Out.

Science.gov (United States)

Cohen, Elaine; And Others

1989-01-01

This annual report on library facilities and furnishings includes articles on: (1) designing libraries that are both handsome and functional; (2) functional use of color and light in library interior design; (3) creating user-friendly libraries; and (4) the seven deadly sins of architects. An eight-page section of photographs is included. (MES)

JSD1000: multi-group cross section sets for shielding materials

International Nuclear Information System (INIS)

Yamano, Naoki

1984-03-01

A multi-group cross section library for shielding safety analysis has been produced by using ENDF/B-IV. The library consists of ultra-fine group cross sections, fine-group cross sections, secondary gamma-ray production cross sections and effective macroscopic cross sections for typical shielding materials. Temperature dependent data at 300, 560 and 900 K have been also provided. Angular distributions of the group to group transfer cross section are defined by a new method of ''Direct Angular Representation'' (DAR) instead of the method of finite Legendre expansion. The library designated JSD1000 are stored in a direct access data base named DATA-POOL and data manipulations are available by using the DATA-POOL access package. The 3824 neutron group data of the ultra-fine group cross sections and the 100 neutron, 20 photon group cross sections are applicable to shielding safety analyses of nuclear facilities. This report provides detailed specifications and the access method for the JSD1000 library. (author)

BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) - Generation Methodology and Preliminary Testing of two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry

Science.gov (United States)

Pescarini, Massimo; Sinitsa, Valentin; Orsi, Roberto; Frisoni, Manuela

2016-02-01

Two broad-group coupled neutron/photon working cross section libraries in FIDO-ANISN format, dedicated to LWR shielding and pressure vessel dosimetry applications, were generated following the methodology recommended by the US ANSI/ANS-6.1.2-1999 (R2009) standard. These libraries, named BUGJEFF311.BOLIB and BUGENDF70.BOLIB, are respectively based on JEFF-3.1.1 and ENDF/B-VII.0 nuclear data and adopt the same broad-group energy structure (47 n + 20 γ) of the ORNL BUGLE-96 similar library. They were respectively obtained from the ENEA-Bologna VITJEFF311.BOLIB and VITENDF70.BOLIB libraries in AMPX format for nuclear fission applications through problem-dependent cross section collapsing with the ENEA-Bologna 2007 revision of the ORNL SCAMPI nuclear data processing system. Both previous libraries are based on the Bondarenko self-shielding factor method and have the same AMPX format and fine-group energy structure (199 n + 42 γ) as the ORNL VITAMIN-B6 similar library from which BUGLE-96 was obtained at ORNL. A synthesis of a preliminary validation of the cited BUGLE-type libraries, performed through 3D fixed source transport calculations with the ORNL TORT-3.2 SN code, is included. The calculations were dedicated to the PCA-Replica 12/13 and VENUS-3 engineering neutron shielding benchmark experiments, specifically conceived to test the accuracy of nuclear data and transport codes in LWR shielding and radiation damage analyses.

Recommended formulae and formats for a resonance parameter library

International Nuclear Information System (INIS)

James, M.F.

1968-08-01

It is proposed that a library of neutron resonance parameters be set up, on punched cards and magnetic tape, which will complement the cross section data in the present U.K. Nuclear Data Library. This report gives parametric formulae for the resolved resonance region, based on:- (i) the Breit-Wigner approximation, (ii) other approximations of R-matrix theory and (iii) the formulae of Adler and Adler. In addition, the statistical distributions of the parameters are given. The final section of the report contains the recommended formats for the parameters of the various formulae. (author)

Identification of toxic cyclopeptides based on mass spectral library matching

Directory of Open Access Journals (Sweden)

Boris L. Milman

2014-08-01

Full Text Available To gain perspective on the use of tandem mass spectral libraries for identification of toxic cyclic peptides, the new library was built from 263 mass spectra (mainly MS2 spectra of 59 compounds of that group, such as microcystins, amatoxins, and some related compounds. Mass spectra were extracted from the literature or specially acquired on ESI-Q-ToF and MALDI-ToF/ToF tandem instruments. ESI-MS2 product-ion mass spectra appeared to be rather close to MALDI-ToF/ToF fragment spectra which are uncommon for mass spectral libraries. Testing of the library was based on searches where reference spectra were in turn cross-compared. The percentage of 1st rank correct identifications (true positives was 70% in a general case and 88–91% without including knowingly defective (‘one-dimension’ spectra as test ones. The percentage of 88–91% is the principal estimate for the overall performance of this library that can be used in a method of choice for identification of individual cyclopeptides and also for group recognition of individual classes of such peptides. The approach to identification of cyclopeptides based on mass spectral library matching proved to be the most effective for abundant toxins. That was confirmed by analysis of extracts from two cyanobacterial strains.

Development of libraries for ORIGEN2 code based on JENDL-3.2

Energy Technology Data Exchange (ETDEWEB)

Suyama, Kenya; Katakura, Jun-ichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Ishikawa, Makoto; Ohkawachi, Yasushi

1998-03-01

The working Group of JNDC `Nuclide Generation Evaluation` has launched a project to make libraries for ORIGEN2 code based on the latest nuclear data library `JENDL-3.2` for current design of LWR and FBR fuels. Many of these libraries are under validation. (author)

Security of Heterogeneous Content in Cloud Based Library Information Systems Using an Ontology Based Approach

Directory of Open Access Journals (Sweden)

Mihai DOINEA

2014-01-01

Full Text Available As in any domain that involves the use of software, the library information systems take advantages of cloud computing. The paper highlights the main aspect of cloud based systems, describing some public solutions provided by the most important players on the market. Topics related to content security in cloud based services are tackled in order to emphasize the requirements that must be met by these types of systems. A cloud based implementation of an Information Library System is presented and some adjacent tools that are used together with it to provide digital content and metadata links are described. In a cloud based Information Library System security is approached by means of ontologies. Aspects such as content security in terms of digital rights are presented and a methodology for security optimization is proposed.

Update of WIMS-D libraries using JENDL-3.2, ENDF/B-VI.5 and JEF-2.2

International Nuclear Information System (INIS)

Gil, Choong Sup; Kim, Jung Do; Chang, Jong Wha

2001-01-01

The WIMS-D5 Libraries based on JENDL-3.2, ENDF/B-VI.5, and JEF-2.2 have been prepared and are being tested against the benchmark problems. Several sensitivity calculations for stabililty confirmation of the libraries were carried out such as the fission spectrum dependency, the self shielding effects of the elastic scattering cross sections, the self shielding effects of Pu -240 and Pu -242 capture cross sections below 4.0 eV, etc. The results of benchmark calculations with the libraries based on JENDL-3.2, ENDF/B-VI.5, JEF-2.2, and the '1986 library were intercompared. The predictions of criticalities and isotopic compositions with the updated libraries show good agreements with the measurements or the reference results. The multiplication factors with the library based on JENDL-3.2 are slightly higher than those of ENDF/B-VI.5 and JEF-2.2

37 CFR 202.19 - Deposit of published copies or phonorecords for the Library of Congress.

Science.gov (United States)

2010-07-01

... appropriate officials of the Library of Congress, and shall be based upon the acquisition policies of the... or phonorecords for the Library of Congress. 202.19 Section 202.19 Patents, Trademarks, and Copyrights COPYRIGHT OFFICE, LIBRARY OF CONGRESS COPYRIGHT OFFICE AND PROCEDURES PREREGISTRATION AND...

Evidence-based medicine and the development of medical libraries in China.

Science.gov (United States)

Huang, Michael Bailou; Cheng, Aijun; Ma, Lu

2009-07-01

This article elaborates on the opportunities and challenges that evidence-based medicine (EBM) has posed to the development of medical libraries and summarizes the research in the field of evidence-based medicine and achievements of EBM practice in Chinese medical libraries. Issues such as building collections of information resources, transformation of information services models, human resources management, and training of medical librarians, clinicians, and EBM users are addressed. In view of problems encountered in EBM research and practice, several suggestions are made about important roles medical libraries can play in the future development of EBM in China.

Calculation and analysis of the source term of the reactor core based on different data libraries

International Nuclear Information System (INIS)

Chen Haiying; Zhang Chunming; Wang Shaowei; Lan Bing; Liu Qiaofeng; Han Jingru

2014-01-01

The nuclear fuel in reactor core produces large amount of radioactive nuclides in the fission process. ORIGEN-S can calculate the accumulation and decay of radioactive nuclides in the core by using various forms of data libraries, including card-image library, binary library and ORIGEN-S cross section library generated by ARP through interpolation method. In this paper, the information of each data library was described, and the reactor core inventory was calculated by using Card-image library and ARP library. The radioactivity concentration of typical nuclides with the change of fuel burnup was analyzed. The results showed that the influence of data libraries on the calculation of nuclide radioactivity was various. Compared to Card-image library, the radioactivity of a small part of nuclides calculated by ARP library were larger and the radioactivity of "1"3"4Cs, "1"3"6Cs were calculated smaller by about 15%. For some typical nuclides, with the deepening of fuel burnup, the difference of nuclide radioactivity calculated by the two libraries increased. However, the changes of the ratio of nuclide radioactivity were different. (authors)

Nuclear data libraries for Tripoli-3.5 code

International Nuclear Information System (INIS)

Vergnaud, Th.

2001-01-01

The TRIPOLI-3 code uses multigroup nuclear data libraries generated using the NJOY-THEMIS suite of modules: for neutrons, they are produced from the ENDF/B-VI evaluations and cover the range between 20 MeV and 10 -5 eV, either in 315 groups and for one temperature, or in 3209 groups and for five temperatures; for gamma-rays, they are from JEF2 and are processed in groups between 14 MeV and keV. The probability tables used for the neutron transport calculations have been derived from the ENDF/B-VI evaluations using the CALENDF code. Cross sections for gamma production by neutron interaction (fission, capture or inelastic scattering) have been derived from ENDF/B-VI in 315 neutron groups and 75 gamma groups. The code also uses two response function libraries: for neutrons; based on several sources, in particular the dosimetry libraries IRDF/85 and IRDF/90; for gamma-rays it is based on the JEF2 evaluation and contains the kerma factors for all the elements and cross sections for all interactions. (author)

Library usage patterns in the electronic information environment. Electronic journals, Use studies, Libraries, Medical libraries

Directory of Open Access Journals (Sweden)

B. Franklin

2004-01-01

Full Text Available This paper examines the methodology and results from Web-based surveys of more than 15,000 networked electronic services users in the United States between July 1998 and June 2003 at four academic health sciences libraries and two large main campus libraries serving a variety of disciplines. A statistically valid methodology for administering simultaneous Web-based and print-based surveys using the random moments sampling technique is discussed and implemented. Results from the Web-based surveys showed that at the four academic health sciences libraries, there were approximately four remote networked electronic services users for each in-house user. This ratio was even higher for faculty, staff, and research fellows at the academic health sciences libraries, where more than five remote users for each in-house user were recorded. At the two main libraries, there were approximately 1.3 remote users for each in-house user of electronic information. Sponsored research (grant funded research accounted for approximately 32% of the networked electronic services activity at the health sciences libraries and 16% at the main campus libraries. Sponsored researchers at the health sciences libraries appeared to use networked electronic services most intensively from on-campus, but not from in the library. The purpose of use for networked electronic resources by patrons within the library is different from the purpose of use of those resources by patrons using the resources remotely. The implications of these results on how librarians reach decisions about networked electronic resources and services are discussed.

KAERI photonuclear library

Energy Technology Data Exchange (ETDEWEB)

Chang, Jong Hwa; Lee, Young Ouk; Han, Yin Iu

2000-03-01

This report contains summary information and figures depicting the KAERI photonuclear data library that extends up to 140 MeV of incident photon. The library consists of 143 isotopes from C-12 to Bi-209, providing the photoabsorption cross section and the emission spectra for neutron, proton, deuteron, triton, alpha particles, and all residual nuclides in ENDF6 format. The contents of this report and ENDF-6 format data library are available at http://atom.kaeri.re.kr/.

Towards Knowledge-Based Digital Libraries

NARCIS (Netherlands)

Feng, L.; Jeusfeld, M.A.; Hoppenbrouwers, J.

From the standpoint of satisfying human's information needs, the current digital library (DL) systems suffer from the following two shortcomings: (i) inadequate high-level cognition support; (ii) inadequate knowledge sharing facilities. In this article, we introduce a two-layered digital library

Calculating the Fee-Based Services of Library Institutions: Theoretical Foundations and Practical Challenges

Directory of Open Access Journals (Sweden)

Sysіuk Svitlana V.

2017-05-01

Full Text Available The article is aimed at highlighting features of the provision of the fee-based services by library institutions, identifying problems related to the legal and regulatory framework for their calculation, and the methods to implement this. The objective of the study is to develop recommendations to improve the calculation of the fee-based library services. The theoretical foundations have been systematized, the need to develop a Provision for the procedure of the fee-based services by library institutions has been substantiated. Such a Provision would protect library institution from errors in fixing the fee for a paid service and would be an informational source of its explicability. The appropriateness of applying the market pricing law based on demand and supply has been substantiated. The development and improvement of accounting and calculation, taking into consideration both industry-specific and market-based conditions, would optimize the costs and revenues generated by the provision of the fee-based services. In addition, the complex combination of calculation leverages with development of the system of internal accounting together with use of its methodology – provides another equally efficient way of improving the efficiency of library institutions’ activity.

WIMS Library updating

Energy Technology Data Exchange (ETDEWEB)

Ravnik, M; Trkov, A [Inst. Jozef Stefan, Ljubljana (Slovenia); Holubar, A [Ustav Jaderneho Vyzkumu CSKAE, Rez (Serbia and Montenegro)

1992-07-01

At the end of 1990 the WIMS Library Update Project (WLUP) has been initiated at the International Atomic Energy Agency. The project was organized as an international research project, coordinated at the J. Stefan Institute. Up to now, 22 laboratories from 19 countries joined the project. Phase 1 of the project, which included WIMS input optimization for five experimental benchmark lattices, has been completed. The work presented in this paper describes also the results of Phase 2 of the Project, in which the cross sections based on ENDF/B-IV evaluated nuclear data library have been processed. (author) [Slovenian] Konec 1990 se je na Mednarodni agenciji za atomsko energijo zacel projekt obnove knjiznice presekov programa WIMS (WIMS Library Updating Project, WLUP). V projektu sodeluje 22 laboratorijev iz 19 drzav, koordiniramo pa ga na Institutu Jozef Stefan. Doslej je koncana faza 1 tega projekta, ki obsega optimizacijo vhodnega modela programa WIMS za pet eksperimentalnih testnih problemov. Podani so tudi rezultati faze 2, v kateri so se procesirali preseki na osnovi ENDF/B-IV datoteke. (author)

Development on hybrid evaluated nuclear data library HENDL1.0/MG/MC

International Nuclear Information System (INIS)

Xu Dezheng; Gao Chunjing; Zheng Shanliang; Liu Haibo; Zhu Xiaoxiang; Li Jingjing; Wu Yican

2004-01-01

A Hybrid Evaluated Nuclear Data Library (HENDL) named as HENDL1.0 has been developed by Fusion Design Study (FDS) team of Institute of Plasma Physics, Academia Sinica (ASIPP) to take into account the requirements in design and research relevant to fusion, fission and fusion-fission sub-critical hybrid reactor. HENDLI1.0 contains one basic evaluated sub-library naming HENDL1.0/E and to processed working sub-libraries naming HENDL1.0/MG and HENDL1.0/MC, respectively. Through carefully comparing, distinguishing and choosing, HENDL1.0/E integrated basic evaluated neutron data files of 213 nuclides from the several main data libraries for evaluated neutron reaction cross sections including ENDF/B-VI (USA), JEF-2.2 (OECD/NEA, Europe), JENDL-3.2 (Japan), CENDL-2 (China), BROND-2 (Russia) and FENDL-2 (IAEA/NDS, ITER program). Based on this, 175-group neutron and 42-group photon neutron-photon coupled multi-group working library HENDL1.0/MG used for discrete ordinate Sn method transport calculation (such as ANISN code) and a compact ENDF form (ACE), continuous energy structure (pointwise) neutron cross section library HENDL1.0/MC for Monte Carlo method transport simulation (as MCMP code) can be attainable with the current group constants processing system NJOY and transport cross section preparation code TRANSX referring to the Vitamin-J energy group structure. In addition, two special bases i.e. transmutation (burnup) library BURNUP. DAT and response function library RESPONSE.DAT, have been also made for fuel cycle calculation and reactivity analyses of nuclear reactor. The relevant sample testing, benchmark checking and primary confirmation are also carried out to assess the validity of multi-purpose data library HENDL1.0. (authors)

Development of the CPXSD Methodology for Generation of Fine-Group Libraries for Shielding Applications

International Nuclear Information System (INIS)

Alpan, F. Arzu; Haghighat, Alireza

2005-01-01

Multigroup cross sections are one of the major factors that cause uncertainties in the results of deterministic transport calculations. Thus, it is important to prepare effective cross-section libraries that include an appropriate group structure and are based on an appropriate spectrum. There are several multigroup cross-section libraries available for particular applications. For example, the 47-neutron, 20-gamma group BUGLE library that is derived from the 199-neutron, 42-gamma group VITAMIN-B6 library is widely used for light water reactor (LWR) shielding and pressure vessel dosimetry applications. However, there is no publicly available methodology that can construct problem-dependent libraries. Thus, the authors have developed the Contributon and Point-wise Cross Section Driven (CPXSD) methodology for constructing effective fine- and broad-group structures. In this paper, new fine-group structures were constructed using the CPXSD, and new fine-group cross-section libraries were generated. The 450-group LIB450 and 589-group LIB589 libraries were developed for neutrons sensitive to the fast and thermal energy ranges, respectively, for LWR shielding problems. As compared to a VITAMIN-B6-like library, the new fine-group library developed for fast neutron dosimetry calculations resulted in closer agreement to the continuous-energy predictions. For example, for the fast neutron cavity dosimetry, ∼4% improvement was observed for the 237 Np(n,f) reaction rate. For the thermal neutron 1 H(n, γ) reaction, a maximum improvement of ∼14% was observed in the reaction rate at the middowncomer position

Development of multi-group xs libraries for the gfr 2400 reactor

International Nuclear Information System (INIS)

Cerba, Š.; Vrban, B.; Lüley, J.; Necas, V.

2016-01-01

GFR 2400 is considered as a conceptual design of the large scale GEN IV Gas-Cooled Fast Reactor. In general, the GEN IV technologies are seen as reliable but also very challenging reactor concepts. Since GFR 2400 lacks any experimental data, the questions on its safety are even more complex and the assessment of its performance could be made only based on computational experience. The paper deals with the development process of multi-group XS libraries based on a hybrid deterministic-Stochastic methodology, using the NJOY99, TRANSX, DIF3D, PARTISN and MCNP5 codes. A new optimized 25 group SBJ E 71 2 5G cross section library was developed based on ENDF/B-VII.1 evaluated data, ZZ-KAFAX-E70 background cross sections and GFR 2400 neutron spectrum. The created library was validated through integral experiments evaluated on the HEX-Z deterministic models in DIF3D. The results were also compared with MCNP5 calculations. (authors)

ORIGEN2 libraries based on JENDL-3.2 for LWR-MOX fuels

Energy Technology Data Exchange (ETDEWEB)

Suyama, Kenya; Katakura, Jun-ichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Onoue, Masaaki; Matsumoto, Hideki [Mitsubishi Heavy Industries Ltd., Tokyo (Japan); Sasahara, Akihiro [Central Research Inst. of Electric Power Industry, Tokyo (Japan)

2000-11-01

A set of ORIGEN2 libraries for LWR MOX fuels was developed based on JENDL-3.2. The libraries were compiled with SWAT using the specification of MOX fuels that will be used in nuclear power reactors in Japan. The verification of the libraries were performed by the analyses of post irradiation examinations for the fuels from European PWR. By the analysis of PIE data from PWR in United States, the comparison was made between calculation and experimental results in the case of that parameters for making the libraries are different from irradiation conditions. These new libraries for LWR MOX fuels are packaged in ORLIBJ32, the libraries released in 1999. (author)

Collection evaluation in University libraries (II. Methods based on collection use

Directory of Open Access Journals (Sweden)

Àngels Massísimo i Sánchez de Boado

2004-01-01

Full Text Available This is our second paper devoted to the collection evaluation in the university libraries. Seven methods are described, based on collection use. Their advantages and disadvantages are discussed, as well as their usefulness for a range of library types

ZZ ENDL82, Evaluated Charged Particle, Neutron, Photon Cross-Section Library

International Nuclear Information System (INIS)

2001-01-01

Description of program or function: - Format: Described in the manual; - Number of groups: (energies between 100 eV and 100 MeV); - Nuclides: 94 (Z 1 to 99); - Origin: LLNL Evaluated Nuclear Data Library. ENDL82 is a collection of evaluated data for neutron-induced reactions, photon interactions with matter, and charged-particle-induced reactions. It is maintained in a computer-oriented system. All interpolable quantities for neutron-induced reactions are presented so that linear interpolation between successive entries yields values that are consistent with stated experimental errors, where experiments exist, or that adhere to an assumed law, such as 1/v energy dependence, within a small fraction (typically 1%). In the case of an assumed energy-dependence law for cross sections, this is accomplished by creating a large number of (energy, cross section) pairs by computer and subsequently thinning the points to a specified accuracy, using the subroutine THINER. All angular distributions are differential probabilities normalized to an integral of unity over the cosine of the scattering angle. All energy distributions of secondary particles are presented as normalized Legendre polynomial representations. The linear interpolation will construct an acceptable angular distribution at an intermediate energy

7 CFR 505.2 - Fees for loans of materials in library collections.

Science.gov (United States)

2010-01-01

....00 processing fee. (d) All services in this section will incur a billing surcharge per invoice... RESEARCH SERVICE, DEPARTMENT OF AGRICULTURE NATIONAL AGRICULTURAL LIBRARY FEES FOR LOANS AND COPYING § 505....00, is billed as a direct cost recovery based on charges to the library by the billing vendor...

Arrangement and processing of monographic publications in youth sections of public libraries

Directory of Open Access Journals (Sweden)

Mateja Ločniškar-Fidler

2006-01-01

Full Text Available A systematic and transparent layout of library material on book shelves of public libraries is one of the essential conditions for successful viewing and searching of materials. The research tried to determine the contemporary classification system of library material for the youth. The data needed for the research was gathered and analyzed by a questionnaire completed by five randomly selected central public libraries. Special collections, arrangement and classification of certain fiction and specialized monographic publications for infants, teenagers and adolescents were analyzed. It was of our interest to observe whether the libraries assign the elements of a call number - which are evident on the library material and in online catalogs – according to standards and current instructions. The article also focuses on the unity and differences of the technical processing, and on color and/or image of labels which additionally explain the classification and the contents of the monographic publications for the youth.

A comparison of the BUGLE-80, SAILOR, and ELXSIR neutron cross-section libraries for PWR pressure vessels surveillance dosimetry and shielding applications

International Nuclear Information System (INIS)

Basha, H.S.; Manahan, M.P.

1992-01-01

In this paper three multigroup neutron cross-section libraries are used in synthesized three-dimensional discrete ordinates transport analyses to investigate their similarities, differences, and results for pressurized water reactor (PWR) pressure vessel surveillance dosimetry and shielding applications. The calculated-to-experimental (C/E) rations and the calculated reaction rates of several fast reactions are compared for the BUGLE-80, SAILOR, and ELXSIR cross-section libraries at the 97-deg surveillance capsule of the San Onofre Nuclear Generation Station Unit 2 (SONGS-2) and at the 90- and 97-deg (C/E ratios only) cavity dosimetry locations for another PWR (referred to as Reactor X)

IAEA consultants' meeting on selection of evaluations for the FENDL/A-2 activation cross section library. Summary report

International Nuclear Information System (INIS)

Pashchenko, A.B.

1996-02-01

FENDL/A is a nuclear data library of neutron activation cross-sections prepared for use in nuclear fusion reactor development. The present report contains recommendations for the creation of a second improved version of FENDL/A, including a list of 400 neutron reactions to be considered with priority. (author)

The value of Web-based library services at Cedars-Sinai Health System.

Science.gov (United States)

Halub, L P

1999-07-01

Cedars-Sinai Medical Library/Information Center has maintained Web-based services since 1995 on the Cedars-Sinai Health System network. In that time, the librarians have found the provision of Web-based services to be a very worthwhile endeavor. Library users value the services that they access from their desktops because the services save time. They also appreciate being able to access services at their convenience, without restriction by the library's hours of operation. The library values its Web site because it brings increased visibility within the health system, and it enables library staff to expand services when budget restrictions have forced reduced hours of operation. In creating and maintaining the information center Web site, the librarians have learned the following lessons: consider the design carefully; offer what services you can, but weigh the advantages of providing the services against the time required to maintain them; make the content as accessible as possible; promote your Web site; and make friends in other departments, especially information services.

Development of ORIGEN libraries for mixed oxide (MOX) fuel assembly designs

International Nuclear Information System (INIS)

Mertyurek, Ugur; Gauld, Ian C.

2016-01-01

Highlights: • ORIGEN MOX library generation process is described. • SCALE burnup calculations are validated against measured MOX fuel samples from the MALIBU program. • ORIGEN MOX libraries are verified using the OECD Phase IV-B benchmark. • There is good agreement for calculated-to-measured isotopic distributions. - Abstract: ORIGEN cross section libraries for reactor-grade mixed oxide (MOX) fuel assembly designs have been developed to provide fast and accurate depletion calculations to predict nuclide inventories, radiation sources and thermal decay heat information needed in safety evaluations and safeguards verification measurements of spent nuclear fuel. These ORIGEN libraries are generated using two-dimensional lattice physics assembly models that include enrichment zoning and cross section data based on ENDF/B-VII.0 evaluations. Using the SCALE depletion sequence, burnup-dependent cross sections are created for selected commercial reactor assembly designs and a representative range of reactor operating conditions, fuel enrichments, and fuel burnup. The burnup dependent cross sections are then interpolated to provide problem-dependent cross sections for ORIGEN, avoiding the need for time-consuming lattice physics calculations. The ORIGEN libraries for MOX assembly designs are validated against destructive radiochemical assay measurements of MOX fuel from the MALIBU international experimental program. This program included measurements of MOX fuel from a 15 × 15 pressurized water reactor assembly and a 9 × 9 boiling water reactor assembly. The ORIGEN MOX libraries are also compared against detailed assembly calculations from the Phase IV-B numerical MOX fuel burnup credit benchmark coordinated by the Nuclear Energy Agency within the Organization for Economic Cooperation and Development. The nuclide compositions calculated by ORIGEN using the MOX libraries are shown to be in good agreement with other physics codes and with experimental data.

Utilization of KENO-IV computer code with HANSEN-ROACH library

International Nuclear Information System (INIS)

Lima Barros, M. de; Vellozo, S.O.

1982-01-01

Several analysis with KENO-IV computer code, which is based in the Monte Carlo method, and the cross section library HANSEN-ROACH, were done, aiming to present the more convenient form to execute criticality calculations with this computer code and this cross sections. (E.G.) [pt

Neutron and proton transmutation-activation cross section libraries to 150 MeV for application in accelerator-driven systems and radioactive ion beam target-design studies

International Nuclear Information System (INIS)

Koning, A.J.; Chadwick, M.B.; MacFarlane, R.E.; Mashnik, S.; Wilson, W.B.

1998-05-01

New transmutation-activation nuclear data libraries for neutrons and protons up to 150 MeV have been created. These data are important for simulation calculations of radioactivity, and transmutation, in accelerator-driven systems such as the production of tritium (APT) and the transmutation of waste (ATW). They can also be used to obtain cross section predictions for the production of proton-rich isotopes in (p,xn) reactions, for radioactive ion beam (RIB) target-design studies. The nuclear data in these libraries stem from two sources: for neutrons below 20 MeV, we use data from the European activation and transmutation file, EAF97; For neutrons above 20 MeV and for protons at all energies we have isotope production cross sections with the nuclear model code HMS-ALICE. This code applies the Monte Carlo Hybrid Simulation theory, and the Weisskopf-Ewing theory, to calculate cross sections. In a few cases, the HMS-ALICE results were replaced by those calculated using the GNASH code for the Los Alamos LA150 transport library. The resulting two libraries, AF150.N and AF150.P, consist of 766 nuclides each and are represented in the ENDF6-format. An outline is given of the new representation of the data. The libraries have been checked with ENDF6 preprocessing tools and have been processed with NJOY into libraries for the Los Alamos transmutation/radioactivity code CINDER. Numerous benchmark figures are presented for proton-induced excitation functions of various isotopes compared with measurements. Such comparisons are useful for validation purposes, and for assessing the accuracy of the evaluated data. These evaluated libraries are available on the WWW at: http://t2.lanl.gov/. 21 refs

Nuclear data library in design calculation

International Nuclear Information System (INIS)

Hirano, Go; Kosaka, Shinya

2006-01-01

In core design calculation, nuclear data takes part as multi group cross section library during the assembly calculation, which is the first stage of a core design calculation. This report summarizes the multi group cross section libraries used in assembly calculations and also presents the methods adopted for resonance and assembly calculation. (author)

Optimization of reference library used in content-based medical image retrieval scheme

International Nuclear Information System (INIS)

Park, Sang Cheol; Sukthankar, Rahul; Mummert, Lily; Satyanarayanan, Mahadev; Zheng Bin

2007-01-01

Building an optimal image reference library is a critical step in developing the interactive computer-aided detection and diagnosis (I-CAD) systems of medical images using content-based image retrieval (CBIR) schemes. In this study, the authors conducted two experiments to investigate (1) the relationship between I-CAD performance and size of reference library and (2) a new reference selection strategy to optimize the library and improve I-CAD performance. The authors assembled a reference library that includes 3153 regions of interest (ROI) depicting either malignant masses (1592) or CAD-cued false-positive regions (1561) and an independent testing data set including 200 masses and 200 false-positive regions. A CBIR scheme using a distance-weighted K-nearest neighbor algorithm is applied to retrieve references that are considered similar to the testing sample from the library. The area under receiver operating characteristic curve (A z ) is used as an index to evaluate the I-CAD performance. In the first experiment, the authors systematically increased reference library size and tested I-CAD performance. The result indicates that scheme performance improves initially from A z =0.715 to 0.874 and then plateaus when the library size reaches approximately half of its maximum capacity. In the second experiment, based on the hypothesis that a ROI should be removed if it performs poorly compared to a group of similar ROIs in a large and diverse reference library, the authors applied a new strategy to identify 'poorly effective' references. By removing 174 identified ROIs from the reference library, I-CAD performance significantly increases to A z =0.914 (p<0.01). The study demonstrates that increasing reference library size and removing poorly effective references can significantly improve I-CAD performance

JDATAVIEWER – JAVA-Based Charting Library

CERN Document Server

Kruk, G

2009-01-01

The JDataViewer is a Java-based charting library developed at CERN, with powerful, extensible and easy to use function editing capabilities. Function edition is heavily used in Control System applications, but poorly supported in products available on the market. The JDataViewer enables adding, removing and modifying function points graphically (using a mouse) or by editing a table of values. Custom edition strategies are supported: developer can specify an algorithm that reacts to the modification of a given point in the function by automatically adapting all other points. The library provides all typical 2D plotting types (scatter, polyline, area, bar, HiLo, contour), as well as data point annotations and data indicators. It also supports common interactors to zoom and move the visible view, or to select and highlight function segments. A clear API is provided to configure and customize all chart elements (colors, fonts, data ranges ...) programmatically, and to integrate non-standard rendering types, inter...

MT71x: Multi-Temperature Library Based on ENDF/B-VII.1

Energy Technology Data Exchange (ETDEWEB)

Conlin, Jeremy Lloyd [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Parsons, Donald Kent [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gray, Mark Girard [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Lee, Mary Beth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); White, Morgan Curtis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-12-16

The Nuclear Data Team has released a multitemperature transport library, MT71x, based upon ENDF/B-VII.1 with a few modifications as well as additional evaluations for a total of 427 isotope tables. The library was processed using NJOY2012.39 into 23 temperatures. MT71x consists of two sub-libraries; MT71xMG for multigroup energy representation data and MT71xCE for continuous energy representation data. These sub-libraries are suitable for deterministic transport and Monte Carlo transport applications, respectively. The SZAs used are the same for the two sub-libraries; that is, the same SZA can be used for both libraries. This makes comparisons between the two libraries and between deterministic and Monte Carlo codes straightforward. Both the multigroup energy and continuous energy libraries were verified and validated with our checking codes checkmg and checkace (multigroup and continuous energy, respectively) Then an expanded suite of tests was used for additional verification and, finally, verified using an extensive suite of critical benchmark models. We feel that this library is suitable for all calculations and is particularly useful for calculations sensitive to temperature effects.

The activation cross section library UKACT1 and the inventory code FISPACT

International Nuclear Information System (INIS)

Forrest, R.A.

1989-01-01

The UK activation library for fusion applications, UKACT1, supersedes the existing UKCTRIIIA library. It contains neutron induced reaction data for 8719 reactions on 625 target nuclides. The library is used by the inventory code FISPACT which is a modified version of the existing code FISPIN. A library of decay information for all the 1314 nuclides involved is also required for calculations and this is also briefly described. UKACT1 will be used for irradiation calculations and as the starting point for a new version which will contain improved data for the most important reactions. These will be identified using the sensitivity subroutine in FISPACT. 16 refs, 1 fig., 2 tabs

Current status of Russian Evaluated Neutron Data Libraries

International Nuclear Information System (INIS)

Blokhin, A.I.; Ignatyuk, A.V.; Manokhin, V.N.; Nikolaev, M.N.

1996-01-01

The status of Russian Evaluated Data Libraries is discussed. The last modifications of the BROND-2 files and their relations to the additional files of the FOND library and the ABBN-90 group constants are considered. The main characteristics of new libraries for the photoneutron data, dosimetry and activation reaction cross sections and transmutation cross sections for intermediate energies are described briefly. (author)

A problem-based learning curriculum in transition: the emerging role of the library.

Science.gov (United States)

Eldredge, J D

1993-07-01

This case study describes library education programs that serve the University of New Mexico School of Medicine, known for its innovative problem-based learning (PBL) curricular track. The paper outlines the specific library instruction techniques that are integrated into the curriculum. The adaptation of library instruction to a PBL mode of medical education, including the use of case studies, is discussed in detail. Also addressed are the planning processes for the new PBL curriculum scheduled for implementation in 1993, including the activities of library faculty and staff and the probable new role of the library in the new curriculum.

State Virtual Libraries

Science.gov (United States)

Pappas, Marjorie L.

2003-01-01

Virtual library? Electronic library? Digital library? Online information network? These all apply to the growing number of Web-based resource collections managed by consortiums of state library entities. Some, like "INFOhio" and "KYVL" ("Kentucky Virtual Library"), have been available for a few years, but others are just starting. Searching for…

The CASTOR shower library

International Nuclear Information System (INIS)

Mundim Filho, Luiz Martins; Carvalho, Wagner de Paula

2012-01-01

Full text: CASTOR (Centaur And Strange Object Research) is an electromagnetic (EM) and hadronic (HAD) calorimeter, based on tungsten and quartz plates, operating in the CMS Detector (Compact Muon Solenoid) at LHC. The calorimeter detects Cerenkov radiation and is positioned around the beam pipe in the very forward region of CMS (at 14.38 m from the interaction point), covering the pseudo-rapidity range between -6.6 ≤ η≤-5.1 . It is longitudinally segmented into 14 sections, 2 for the EM and 12 for the HAD parts and is 16-fold azimuthally symmetric around the beam pipe. A Shower Library is needed for CASTOR Monte Carlo simulation, as the full simulation of showers takes a long time and the high multiplicity of particles in the forward region makes this simulation very time consuming. The Shower Library is used as a look-up table in the form of a ROOT file, so that when a simulated particle enters the detector with a certain energy and direction, characterized by the azimuthal angle φ and the pseudo-rapidity η, instead of making the full simulation of the shower in CASTOR, it is substituted by one already stored in the Shower Library. Showers corresponding to two types of particles are included in the Shower Library: electrons (or photons) and charged pions. The software implemented to make the Shower Library is described, as well as the validation of this library and timing studies. This package has been developed in the context of the official software of the CMS Collaboration, CMSSW. (author)

Activity-Based Costing (ABC and Time-Driven Activity-Based Costing (TDABC: Applicable Methods for University Libraries?

Directory of Open Access Journals (Sweden)

Kate-Riin Kont

2011-01-01

Full Text Available Objective – This article provides an overview of how university libraries research and adapt new cost accounting models, such as “activity-based costing” (ABC and “time-driven activity-based costing” (TDABC, focusing on the strengths and weaknesses of both methods to determine which of these two is suitable for application in university libraries.Methods – This paper reviews and summarizes the literature on cost accounting and costing practices of university libraries. A brief overview of the history of cost accounting, costing, and time and motion studies in libraries is also provided. The ABC and the TDABC method, designed as a revised and easier version of the ABC by Kaplan and Anderson (Kaplan & Anderson 2004 at the beginning of the 21st century, as well as the adoption and adaptation of these methods by university libraries are described, and their strengths and weaknesses, as well as their suitability for university libraries, are analyzed. Results – Cost accounting and costing studies in libraries have a long history, the first of these dating back to 1877. The development of cost accounting and time and motion studies can be seen as a natural evolution of techniques which were created to solve management problems. The ABC method is the best-known management accounting innovation of the last 20 years, and is already widely used in university libraries around the world. However, setting up an ABC system can be very costly, and the system needs to be regularly updated, which further increases its costs. The TDABC system can not only be implemented more quickly (and thus more cheaply, but also can be updated more easily than the traditional ABC, which makes the TDABC the more suitable method for university libraries.Conclusion – Both methods are suitable for university libraries. However, the ABC method can only be implemented in collaboration with an accounting department. The TDABC method can be tested and implemented by

36 CFR 702.11 - Smoking in Library buildings.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Smoking in Library buildings. 702.11 Section 702.11 Parks, Forests, and Public Property LIBRARY OF CONGRESS CONDUCT ON LIBRARY PREMISES § 702.11 Smoking in Library buildings. Smoking in Library areas is prohibited except in those...

Evaluated cross section libraries and kerma factors for neutrons up to 100 MeV on {sup 16}O and {sup 14}N

Energy Technology Data Exchange (ETDEWEB)

Chadwick, M.B.; Young, P.G.

1995-07-01

We present evaluations of the interaction of 20 to 100 MeV neutrons with oxygen and nitrogen nuclei, which follows on from our previous work on carbon. Our aim is to accurately represent integrated cross sections, inclusive emission spectra, and kerma factors, in a data library which can be used in radiation transport calculations. We apply the FKK-GNASH nuclear model code, which includes Hauser-Feshbach, preequilibrium, and direct reaction mechanisms, and use experimental measurements to optimize the calculations. We determine total, elastic, and nonelastic cross sections, angle-energy correlated emission spectra, for light ejectiles with A{<=}4 and gamma-rays, and average energy depositions. Our results for charged-particle emission spectra agree well with the measurements of Subramanian et al.. We compare kerma factors derived from our evaluated cross sections with experimental data, providing an integral benchmarking of our work. The evaluated data libraries are available as electronic files.

ENDF/B-6 decay data library

International Nuclear Information System (INIS)

1992-01-01

This document summarizes the contents of the nuclear decay data library of ENDF/B-6, the U.S. Evaluated Nuclear Data Library. The data are in ENDF-6 format. A copy of the library is available on magnetic tape from the IAEA Nuclear Data Section, free of charge, upon request. (author)

JENDL-3. The Japanese evaluated nuclear data library

International Nuclear Information System (INIS)

Lemmel, H.D.

1992-01-01

This document summarizes the contents of JENDL-3.1, the Japanese evaluated data library for neutron nuclear data, released in 1989 and revised in Dec. 1990. It also summarizes the JENDL-3 fission-products cross-section data library released in 1990. The entire library or retrievals of selected materials are available on magnetic tape from the IAEA Nuclear Data Section free of charge. (author)

IFLA General Conference, 1989. Division of Libraries Serving the General Public. Section on Library Services to Multicultural Populations; Round Table--International Association of Metropolitan City Libraries; Round Table on Mobile Libraries. Booklet 31.

Science.gov (United States)

International Federation of Library Associations, The Hague (Netherlands).

The seven papers in this collection continue the presentations from the Division of Libraries Serving the General Public: (1) "Multicultural Activities for Children and Young People at the Munich International Youth Library" (German and English versions; Lioba Betten); (2) "Multicultural Literature and Library Services for Children:…

Collection-based analysis of selected medical libraries in the Philippines using Doody's Core Titles.

Science.gov (United States)

Torres, Efren

2017-01-01

This study assessed the book collection of five selected medical libraries in the Philippines, based on Doodys' Essential Purchase List for basic sciences and clinical medicine, to compare the match and non-match titles among libraries, to determine the strong and weak disciplines of each library, and to explore the factors that contributed to the percentage of match and non-match titles. List checking was employed as the method of research. Among the medical libraries, De La Salle Health Sciences Institute and University of Santo Tomas had the highest percentage of match titles, whereas Ateneo School of Medicine and Public Health had the lowest percentage of match titles. University of the Philippines Manila had the highest percentage of near-match titles. De La Salle Health Sciences Institute and University of Santo Tomas had sound medical collections based on Doody's Core Titles. Collectively, the medical libraries shared common collection development priorities, as evidenced by similarities in strong areas. Library budget and the role of the library director in book selection were among the factors that could contribute to a high percentage of match titles.

Generation of neutron scattering cross sections for silicon dioxide

International Nuclear Information System (INIS)

Ramos, R; Marquez Damian, J.I; Granada, J.R.; Cantargi, F

2009-01-01

A set of neutron scattering cross sections for silicon and oxygen bound in silicon dioxide were generated and validated. The cross sections were generated in the ACE format for MCNP using the nuclear data processing system NJOY, and the validation was done with published experimental data. This cross section library was applied to the calculation of five critical configurations published in the benchmark Critical Experiments with Heterogeneous Compositions of Highly Enriched Uranium, Silicon Dioxide and Polyethylene. The original calculations did not use the thermal scattering libraries generated in this work and presented significant differences with the experimental results. For this reason, the newly generated library was added to the input and the multiplication factor for each configuration was recomputed. The utilization of the thermal scattering libraries did not result in an improvement of the computational results. Based on this we conclude that integral experiments to validate this type of thermal cross sections need to be designed with a higher influence of thermal scattering in the measured result, and the experiments have to be performed under more controlled conditions. [es

Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data

Energy Technology Data Exchange (ETDEWEB)

Risner, J. M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wiarda, D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dunn, M. E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Miller, T. M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Peplow, D. E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Patton, B. W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2011-09-30

New coupled neutron-gamma cross-section libraries have been developed for use in light water reactor (LWR) shielding applications, including pressure vessel dosimetry calculations. The libraries, which were generated using Evaluated Nuclear Data File/B Version VII Release 0 (ENDF/B-VII.0), use the same fine-group and broad-group energy structures as the VITAMIN-B6 and BUGLE-96 libraries. The processing methodology used to generate both libraries is based on the methods used to develop VITAMIN-B6 and BUGLE-96 and is consistent with ANSI/ANS 6.1.2. The ENDF data were first processed into the fine-group pseudo-problem-independent VITAMIN-B7 library and then collapsed into the broad-group BUGLE-B7 library. The VITAMIN-B7 library contains data for 391 nuclides. This represents a significant increase compared to the VITAMIN-B6 library, which contained data for 120 nuclides. The BUGLE-B7 library contains data for the same nuclides as BUGLE-96, and maintains the same numeric IDs for those nuclides. The broad-group data includes nuclides which are infinitely dilute and group collapsed using a concrete weighting spectrum, as well as nuclides which are self-shielded and group collapsed using weighting spectra representative of important regions of LWRs. The verification and validation of the new libraries includes a set of critical benchmark experiments, a set of regression tests that are used to evaluate multigroup crosssection libraries in the SCALE code system, and three pressure vessel dosimetry benchmarks. Results of these tests confirm that the new libraries are appropriate for use in LWR shielding analyses and meet the requirements of Regulatory Guide 1.190.

ORIGEN-2 libraries based on JENDL-3.2 for PWR-MOX fuel

Energy Technology Data Exchange (ETDEWEB)

Matsumoto, Hideki; Onoue, Masaaki; Tahara, Yoshihisa [Mitsubishi Heavy Industries Ltd., Tokyo (Japan)

2001-08-01

A set of ORIGEN-2 libraries for PWR MOX fuel was developed based on JENDL-3.2 in the Working Group on Evaluation of Nuclide Production, Japanese Nuclear Data Committee. The calculational model generating ORIGEN-2 libraries of PWR MOX is explained here in detail. The ORIGEN-2 calculation with the new ORIGEN-2 MOX library can predict the nuclides contents within 10% for U and Pu isotopes and 20% for both minor actinides and main FPs. (author)

The needs for program and cross-section library improvement in calculation of neutron-induced activity inventories

International Nuclear Information System (INIS)

Yavshitz, S.G.; Rubchenya, V.A.; Rimski-Korsakov, A.A.

1993-01-01

The authors demonstrate the possibility of an approach to evaluate the radioactive inventory - induced activity of structural materials and surface contamination of reactor components, that will fit well into ORIGEN code structure and could be used on a modest PC directly on the decommissioning site. This approach would also require only one well tested set of pre-calculated and adjusted by experiment cross-section libraries (averaged by typical neutron spectra outside the reactor core). 15 refs, 1 fig

Evidence-based Practice in libraries - Principles and discussions

DEFF Research Database (Denmark)

Johannsen, Carl Gustav

2012-01-01

The article examines problems concerning the introduction and future implementation of evidence-based practice (EBP) in libraries. It includes important conceptual distinctions and definitions, and it reviews the more controversial aspects of EBP, primarely based on experiences from Denmark. The ....... The purpose of the article is both to qualify existing scepticism and reservations and - maybe - to clarify misunderstandings and objections through the presentation of arguments and data....

MIRANDA - a module based on multiregion resonance theory for generating cross sections within the AUS neutronics code system

International Nuclear Information System (INIS)

Robinson, G.S.

1985-12-01

MIRANDA is the cross-section generation module of the AUS neutronics code system used to prepare multigroup cross-section data which are pertinent to a particular study from a general purpose multigroup library of cross sections. Libraries have been prepared from ENDF/B which are suitable for thermal and fast fission reactors and for fusion blanket studies. The libraries include temperature dependent data, resonance cross sections represented by subgroup parameters and may contain photon as well as neutron data. The MIRANDA module includes a multiregion resonance calculation in slab, cylinder or cluster geometry, a homogeneous B L flux solution, and a group condensation facility. This report documents the modifications to an earlier version of MIRANDA and provides a complete user's manual

Curriculum-based library instruction from cultivating faculty relationships to assessment

CERN Document Server

Blevins, Amy

2014-01-01

Curriculum-Based Library Instruction: From Cultivating Faculty Relationships to Assessment highlights the movement beyond one-shot instruction sessions, specifically focusing on situations where academic librarians have developed curriculum based sessions and/or become involved in curriculum committees.

Status of multigroup cross-section data for shielding applications

International Nuclear Information System (INIS)

Roussin, R.W.; Maskewitz, B.F.; Trubey, D.K.

1983-01-01

Multigroup cross-section libraries for shielding applications in formats for direct use in discrete ordinates or Monte Carlo codes have long been a part of the Data Library Collection (DLC) of the Radiation Shielding Information Center (RSIC). In recent years libraries in more flexible and comprehensive formats, which allow the user to derive his own problem-dependent sets, have been added to the collection. The current status of both types is described, as well as projections for adding data libraries based on ENDF/B-V

Nuclear data libraries and online services. An introduction to the data types and services available from the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Oblozinsky, P.; Schwerer, O.

1998-09-01

The IAEA Nuclear Data Section provides convenient, cost-free access to the world's most comprehensive collection of numerical nuclear physics data. These nuclear data libraries result from a worldwide cooperation of nuclear data centres coordinated by the IAEA. An introduction is given to the various nuclear data types and libraries with particular emphasis to online services via the Internet. This paper summarizes a presentation for the IAEA Workshop on ''Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety'' held at ICTP Trieste, Italy, 23 February - 17 March 1998. (author)

Measurements of D-T neutron induced radioactivity in plasma-facing materials and their role in qualification of activation cross-section libraries and codes

International Nuclear Information System (INIS)

Kumar, A.; Abdou, M.A.; Kosako, K.; Oyama, Y.; Nakamura, T.; Maekawa, H.

1995-01-01

The D-T neutron-induced radioactivity constitutes one of the foremost issues in fusion reactor design. The validation of activation cross-sections and decay data libraries is one of the important requirements for validating ITER design from safety and waste disposal viewpoints. An elaborate, experimental program was initiated in 1988, under USDOE-JAERI collaborative program, to validate the radioactivity codes/libraries. The measurements of decay-γ spectra from irradiated, high purity samples of Al, Si, Ti, V, Cr, Mn-Cu alloy, Fe, Co, Ni, Cu, stainless steel 316 (AISI 316), Zn, Zr, Nb, Mo, In, Sn, Ta, W, and Pb, among others, were conducted under D-T neutron fluences varying from 1.6 x 10 10 ncm -2 to 6.1 x 10 13 ncm -2 . As many as 14 neutron energy spectra were covered for a number of materials. The analysis of isotopic activities of the irradiated materials using activation cross-section libraries of four leading radioactivity codes, i.e. ACT4/THIDA-2, REAC-3, DKR-ICF, and RACC, has shown large discrepancies among the calculations, on the one hand, and between the calculations and the measurements, on the other. A discussion is also presented on definition and obtention of safety cum quality factors for various activation libraries. (orig.)

Criticality and safety parameter studies for upgrading 3 MW TRIGA MARK II research reactor and validation of generated cross section library and computational method

International Nuclear Information System (INIS)

Bhuiyan, S.I.; Mondal, M.A.W.; Sarker, M.M.; Rahman, M.; Shahdatullah, M.S.; Huda, M.Q.; Chakrroborty, T.K.; Khan, M.J.H.

2000-01-01

This study deals with the neutronic and thermal hydraulic analysis of the 3MW TRIGA MARK II research reactor to upgrade it to a higher flux. The upgrading will need a major reshuffling and reconfiguration of the current core. To reshuffle the current core configuration, the chain of NJOY94.10 - WIMSD-5A - CITATION - PARET - MCNP4B2 codes has been used for the overall analysis. The computational methods, tools and techniques, customisation of cross section libraries, various models for cells and super cells, and a lot of associated utilities have been standardised and established/validated for the overall core analysis. Analyses using the 4-group and 7-group libraries of macroscopic cross sections generated from the 69-group WIMSD-5 library showed that a 7-group structure is more suitable for TRIGA calculations considering its LEU fuel composition. The MCNP calculations established that the CITATION calculations and the generated cross section library are reasonably good for neutronic analysis of TRIGA reactors. Results obtained from PARET demonstrated that the flux upgrade will not cause the temperature limit on the fuel to be exceeded. Also, the maximum power density remains, by a substantial margin below the level at which the departure from nucleate boiling could occur. A possible core with two additional irradiation channels around the CT is projected where almost identical thermal fluxes as in the CT are obtained. The reconfigured core also shows 7.25% thermal flux increase in the Lazy Susan. (author)

Evidence-Based Practice and School Libraries: Interconnections of Evidence, Advocacy, and Actions

Science.gov (United States)

Todd, Ross J.

2015-01-01

This author states that a professional focus on evidence based practice (EBP) for school libraries emerged from the International Association of School Librarianship conference when he presented the concept. He challenged the school library profession to actively engage in professional and reflective practices that chart, measure, document, and…

Cross sections in 25 groups obtained from ENDF/B-IV and ENDL/78 libraries, processed with GALAXY and NJOY computer codes

International Nuclear Information System (INIS)

Chalhoub, E.S.; Corcuera, R.P.

1982-01-01

The discrepancies existing between ENDF/B-IV and ENDL/78 libraries, in diferent energy regions are identified, and the order of the differences in multigroup sections are determined, when GALAXY or NJOY computer codes are used. (E.G.) [pt

A Web-Based Electronic Book (e-book) Library: The netLibrary Model.

Science.gov (United States)

Connaway, Lynn Silipigni

2001-01-01

Identifies elements that are important for academic libraries to use in evaluating electronic books, including content; acquisition and collection development; software and hardware standards and protocols; digital rights management; access; archiving; privacy; the market and pricing; and enhancements and ideal features. Describes netLibrary, a…

EURLIB-LWR-45/16 and - 15/5. Two board group libraries for LWR-shielding problems

Energy Technology Data Exchange (ETDEWEB)

Herrnberger, V

1982-04-01

Specifications of the broad group cross section libraries EURLIB-LWR-45/16 and -15/5 are given. They are based on EURLIB-III data and produced for LWR shielding problems. The elements considered are H, C{sub 12}, O, Na, Al, Si, Ca, Cr, Mn, Fe, Ni, Zr, U{sub 235}, U{sub 238}. The cross section libraries are available upon request from EIR, RSIC, NEA-CPL and IAEA-NDS. (author) Refs, figs, tabs

Status of neutron dosimetry cross sections

International Nuclear Information System (INIS)

Griffin, P.J.; Kelly, J.G.

1992-01-01

Several new cross section libraries, such as ENDF/B-VI(release 2), IRDF-90,JEF-2.2, and JENDL-3 Dosimetry, have recently been made available to the dosimetry community. the Sandia National Laboratories (SNL) Radiation Metrology Laboratory (RML) has worked with these libraries since pre-release versions were available. this paper summarizes the results of the intercomparison and testing of dosimetry cross sections. As a result of this analysis, a compendium of the best dosimetry cross sections was assembled from the available libraries for use within the SNL RML. this library, referred to as the SNLRML Library, contains 66 general dosimetry sensors and 3 special dosimeters unique to the RML sensor inventory. The SNLRML cross sections have been put into a format compatible with commonly used spectrum determination codes

FENDL/MG-2.0 and FENDL/MC-2.0. The processed cross-section libraries for neutron photon transport calculations. Version 1, March 1997. Summary documentation

International Nuclear Information System (INIS)

Wienke, H.; Herman, M.

1998-01-01

Evaluated neutron reaction data and photon-atom interaction cross sections for materials contained in the general purpose Fusion Evaluated Nuclear Data Library (FENDL/E2.0) have been processed with the NJOY code system into VITAMIN-J multigroup structure, for use in discrete-ordinates transport codes, and into continuous energy ACE format, for use in the Monte Carlo transport code MCNP. This document summarizes the resulting data libraries FENDL/MG-2.0 version 1 and FENDL/MC-2.0 version 1. The data are available costfree from the IAEA Nuclear Data Section online or on magnetic tape. (author)

Analysis of Environmental Friendly Library Based on the Satisfaction and Service Quality: study at Library “X”

Science.gov (United States)

Herdiansyah, Herdis; Satriya Utama, Andre; Safruddin; Hidayat, Heri; Gema Zuliana Irawan, Angga; Immanuel Tjandra Muliawan, R.; Mutia Pratiwi, Diana

2017-10-01

One of the factor that influenced the development of science is the existence of the library, which in this case is the college libraries. Library, which is located in the college environment, aims to supply collections of literatures to support research activities as well as educational for students of the college. Conceptually, every library now starts to practice environmental principles. For example, “X” library as a central library claims to be an environmental friendly library for practicing environmental friendly management, but the X library has not inserted the satisfaction and service aspect to the users, including whether it is true that environmental friendly process is perceived by library users. Satisfaction can be seen from the comparison between expectations and reality of library users. This paper analyzes the level of library user satisfaction with library services in the campus area and the gap between expectations and reality felt by the library users. The result of the research shows that there is a disparity between the hope of library management, which is sustainable and environmentally friendly with the reality in the management of the library, so that it has not given satisfaction to the users yet. The gap value of satisfaction that has the biggest difference is in the library collection with the value of 1.57; while for the smallest gap value is in the same service to all students with a value of 0.67.

Comparison between Nuclear Data Libraries of Different Density of Data for H in Light Water

International Nuclear Information System (INIS)

Torres, Lourdes; Gillette, Victor

2003-01-01

We introduce the results of comparison between nuclear data libraries at different density of data.Nuclear data libraries were produced for hydrogen (H) in light water at different density of data.These libraries were produced using the NJOY nuclear data processing system.With this code we produce pointwise cross sections and related quantities, in the ENDF format, and in the ACE format for MCNP.Experimental neutron spectrum was compared with MCNP4C simulations, based on the produced libraries and calculation time

The impact of computerisation of library operations on library ...

African Journals Online (AJOL)

The use of computer-based systems in libraries and information units is now a vogue. The era of manual system in library operations is on its way to extinction. Recent developments in information world tend towards a globalized information communication technology (ICT). The library as a dynamic institution cannot afford ...

To Reach Multicultural Users in Libraries--Some Reflections and Examples from Sweden.

Science.gov (United States)

Ekman, Maud

This paper describes library services to multicultural users in Sweden. The first section addresses library buildings and staff, stressing the importance of a welcoming environment. Library materials and technique are discussed in the second section, including media in other languages and access to the Internet. The third section considers…

A nuclear data library for activity determinations of selected nuclides

International Nuclear Information System (INIS)

Baard, J.H.

1991-11-01

This report describes the GAMLIB 1-5 library, which is used in the calculation of the activity of radionuclides present in the gamma-ray spectra of irradiated neutron fluence detectors. The library contains all constants needed to calculate the activity for reactions normally applied in neutron fluence determinations, performed in irradiation experiments in the HFR. It also contains the nuclide constants for the activity calculation of gamma-ray measurements of U and Pu samples. The library consists of two kinds of tables, the first containing gamma-ray energies and gamma-ray emission probabilities with their uncertainties and the nuclide code, the other the nuclide code, decay constant, gamma -ray energies and gamma-ray emission probabilities. No cross-section data are stored in this library. All the relevant dat of the Nuclear Data Guide (Dordrecht, Kluwer 1989) have been used as base for this library. Other data have been obtained from recent literature. This library comprises 155 nuclides and 1115 gamma-ray energies. (author). 9 refs

Optimal protein library design using recombination or point mutations based on sequence-based scoring functions.

Science.gov (United States)

Pantazes, Robert J; Saraf, Manish C; Maranas, Costas D

2007-08-01

In this paper, we introduce and test two new sequence-based protein scoring systems (i.e. S1, S2) for assessing the likelihood that a given protein hybrid will be functional. By binning together amino acids with similar properties (i.e. volume, hydrophobicity and charge) the scoring systems S1 and S2 allow for the quantification of the severity of mismatched interactions in the hybrids. The S2 scoring system is found to be able to significantly functionally enrich a cytochrome P450 library over other scoring methods. Given this scoring base, we subsequently constructed two separate optimization formulations (i.e. OPTCOMB and OPTOLIGO) for optimally designing protein combinatorial libraries involving recombination or mutations, respectively. Notably, two separate versions of OPTCOMB are generated (i.e. model M1, M2) with the latter allowing for position-dependent parental fragment skipping. Computational benchmarking results demonstrate the efficacy of models OPTCOMB and OPTOLIGO to generate high scoring libraries of a prespecified size.

FRDS.Broker Library

DEFF Research Database (Denmark)

2018-01-01

The FRDS.Broker library is a teaching oriented implementation of the Broker architectural pattern for distributed remote method invocation. It defines the central roles of the pattern and provides implementations of those roles that are not domain/use case specific. It provides a JSON based (GSon...... library) Requestor implementation, and implementations of the ClientRequestHandler and ServerRequestHandler roles in both a Java socket based and a Http/URI tunneling based variants. The latter us based upon the UniRest and Spark-Java libraries. The Broker pattern and the source code is explained...

A problem-based learning curriculum in transition: the emerging role of the library.

OpenAIRE

Eldredge, J D

1993-01-01

This case study describes library education programs that serve the University of New Mexico School of Medicine, known for its innovative problem-based learning (PBL) curricular track. The paper outlines the specific library instruction techniques that are integrated into the curriculum. The adaptation of library instruction to a PBL mode of medical education, including the use of case studies, is discussed in detail. Also addressed are the planning processes for the new PBL curriculum schedu...

42 CFR 4.3 - Purpose of the Library.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Purpose of the Library. 4.3 Section 4.3 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL PROVISIONS NATIONAL LIBRARY OF MEDICINE § 4.3 Purpose of the Library. The purpose of the Library is to assist the advancement of...

Multicultural Communities: Guidelines for Library Services. Third Edition

Science.gov (United States)

International Federation of Library Associations and Institutions (NJ1), 2009

2009-01-01

These Guidelines constitute the third edition of the International Federation of Library Associations (IFLA) "Multicultural Communities: "Guidelines for Library Services." This revision follows the IFLA Section of Library Services to Multicultural Populations' "2006-2010 Strategic Plans": to review and revise the…

Process Fragment Libraries for Easier and Faster Development of Process-based Applications

Directory of Open Access Journals (Sweden)

David Schumm

2011-01-01

Full Text Available The term “process fragment” is recently gaining momentum in business process management research. We understand a process fragment as a connected and reusable process structure, which has relaxed completeness and consistency criteria compared to executable processes. We claim that process fragments allow for an easier and faster development of process-based applications. As evidence to this claim we present a process fragment concept and show a sample collection of concrete, real-world process fragments. We present advanced application scenarios for using such fragments in development of process-based applications. Process fragments are typically managed in a repository, forming a process fragment library. On top of a process fragment library from previous work, we discuss the potential impact of using process fragment libraries in cross-enterprise collaboration and application integration.

MCNP4c JEFF-3.1 Based Libraries. Eccolib-Jeff-3.1 libraries

International Nuclear Information System (INIS)

Sublet, J.Ch.

2006-01-01

Continuous-energy and multi-temperatures MCNP Ace types libraries, derived from the Joint European Fusion-Fission JEFF-3.1 evaluations, have been generated using the NJOY-99.111 processing code system. They include the continuous-energy neutron JEFF-3.1/General Purpose, JEFF-3.1/Activation-Dosimetry and thermal S(α,β) JEFF-3.1/Thermal libraries and data tables. The processing steps and features are explained together with the Quality Assurance processes and records linked to the generation of such multipurpose libraries. (author)

Development and verification of a 281-group WIMS-D library based on ENDF/B-VII.1

International Nuclear Information System (INIS)

Dong, Zhengyun; Wu, Jun; Ma, Xubo; Yu, Hui; Chen, Yixue

2016-01-01

Highlights: • A new WIMS-D library based on SHEM 281 energy structures is developed. • The method for calculating the lambda factor is illustrated and parameters are discussed. • The results show the improvements of this library compared with other libraries. - Abstract: The WIMS-D library based on WIMS 69 or XMAS 172 energy group structures is widely used in thermal reactor research. Otherwise, the resonance overlap effect is not taken into account in the two energy group structure, which limits the accuracy of resonance treatment. The SHEM 281 group structure is designed by the French to avoid the resonance overlap effect. In this study, a new WIMS-D library with SHEM 281 mesh is developed by using the NJOY nuclear data processing system based on the latest Evaluated Nuclear Data Library ENDF/B-VII.1. The parameters such as the thermal cut-off energy and lambda factor that depend on group structure are discussed. The lambda factor is calculated by Neutron Resonance Spectrum Calculation System and the effect of this factor is analyzed. The new library is verified through the analysis of various criticality benchmarks by using DRAGON code. The values of multiplication factor are consistent with the experiment data and the results also are improved in comparison with other WIMS libraries.

Promotion: Study of the Library of the department of library and information science and book

Directory of Open Access Journals (Sweden)

Andreja Nagode

2003-01-01

Full Text Available The contribution presents basic information about academic libraries and their promotion. Librarians should have promotion knowledge since they have to promote and market their libraries. The paper presents the definition of academic libraries, their purpose, objectives and goals. Marketing and promotion in academic libraries are defined. The history of academic libraries and their promotion are described. The contribution presents results and the interpretation of the research, based on the study of users of the Library of the Department of Library and Information Science and Book studies. A new promotion plan for libraries based on the analysis of the academic library environment is introduced.

Development and testing of the VITAMIN-B7/BUGLE-B7 coupled neutron-gamma multigroup cross-section libraries

Energy Technology Data Exchange (ETDEWEB)

Risner, J.M.; Wiarda, D.; Miller, T.M.; Peplow, D.E.; Patton, B.W.; Dunn, M.E. [Oak Ridge National Laboratory, MS 6170, P.O. Box 2008, Oak Ridge, TN 37831-6170 (United States); Parks, B.T. [U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Mail Stop O10-B3, 11555 Rockville Pike, Rockville, MD 20852 (United States)

2011-07-01

The U.S. Nuclear Regulatory Commission's Regulatory Guide 1.190 states that calculational methods used to estimate reactor pressure vessel (RPV) fluence should use the latest version of the evaluated nuclear data file (ENDF). The VITAMIN-B6 fine-group library and BUGLE-96 broad-group library, which are widely used for RPV fluence calculations, were generated using ENDF/B-VI.3 data, which was the most current data when Regulatory Guide 1.190 was issued. We have developed new fine-group (VITAMIN-B7) and broad-group (BUGLE-B7) libraries based on ENDF/B-VII.0. These new libraries, which were processed using the AMPX code system, maintain the same group structures as the VITAMIN-B6 and BUGLE-96 libraries. Verification and validation of the new libraries were accomplished using diagnostic checks in AMPX, 'unit tests' for each element in VITAMIN-B7, and a diverse set of benchmark experiments including critical evaluations for fast and thermal systems, a set of experimental benchmarks that are used for SCALE regression tests, and three RPV fluence benchmarks. The benchmark evaluation results demonstrate that VITAMIN-B7 and BUGLE-B7 are appropriate for use in RPV fluence calculations and meet the calculational uncertainty criterion in Regulatory Guide 1.190. (authors)

Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries

International Nuclear Information System (INIS)

Risner, Joel M.; Wiarda, Dorothea; Miller, Thomas Martin; Peplow, Douglas E.; Patton, Bruce W.; Dunn, Michael E.; Parks, Benjamin T.

2011-01-01

The U.S. Nuclear Regulatory Commission's Regulatory Guide 1.190 states that calculational methods used to estimate reactor pressure vessel (RPV) fluence should use the latest version of the Evaluated Nuclear Data File (ENDF). The VITAMIN-B6 fine-group library and BUGLE-96 broad-group library, which are widely used for RPV fluence calculations, were generated using ENDF/B-VI data, which was the most current data when Regulatory Guide 1.190 was issued. We have developed new fine-group (VITAMIN-B7) and broad-group (BUGLE-B7) libraries based on ENDF/B-VII. These new libraries, which were processed using the AMPX code system, maintain the same group structures as the VITAMIN-B6 and BUGLE-96 libraries. Verification and validation of the new libraries was accomplished using diagnostic checks in AMPX, unit tests for each element in VITAMIN-B7, and a diverse set of benchmark experiments including critical evaluations for fast and thermal systems, a set of experimental benchmarks that are used for SCALE regression tests, and three RPV fluence benchmarks. The benchmark evaluation results demonstrate that VITAMIN-B7 and BUGLE-B7 are appropriate for use in LWR shielding applications, and meet the calculational uncertainty criterion in Regulatory Guide 1.190.

Speech-Based Information Retrieval for Digital Libraries

National Research Council Canada - National Science Library

Oard, Douglas W

1997-01-01

Libraries and archives collect recorded speech and multimedia objects that contain recorded speech, and such material may comprise a substantial portion of the collection in future digital libraries...

Library Standards: Evidence of Library Effectiveness and Accreditation.

Science.gov (United States)

Ebbinghouse, Carol

1999-01-01

Discusses accreditation standards for libraries based on experiences in an academic law library. Highlights include the accreditation process; the impact of distance education and remote technologies on accreditation; and a list of Internet sources of standards and information. (LRW)

Digital library usability studies

CERN Document Server

Eden, Bradford Lee

2005-01-01

Each summer, circulation staff in my library inventories a section of the stacks andbrings collection issues to the attention of appropriate bibliographers. Since I amresponsible for the economics collection, I see an array of government documents thathave managed to elude the cataloging process. Many of these titles are decades old,having squatted in the library undisturbed and uncirculated since our online catalogwas implemented in 1990.

Nuclear libraries for SCALE5.1 system

International Nuclear Information System (INIS)

Vertes, P.

2009-01-01

Codes for preparing master and working AMPX libraries and point-wise nuclear libraries for SCALE5.1 system have been created. Master and working libraries are constructed from multigroup library in matxs form which are produced by means of the NJOY code. The point-wise cross-section library is derived from pend files obtained also by NJOY. The AMPX libraries may contain neutron, gamma production and gamma transport data, as well. The produced master libraries can be used either with stand-alone functional modules or with control modules. An assistant package of programs also has been developed in order to facilitate the usage of NJOY. (Authors)

Nuclear libraries for SCALE5.1 system

International Nuclear Information System (INIS)

Vertes, P.

2009-01-01

Codes for preparing master and working AMPX libraries and point-wise (PW) nuclear libraries for SCALE5.1 system have been created. Master and working libraries are constructed from multigroup library in matxs form which are produced by means of the NJOY code. The PW cross-section library is derived from pend files obtained also by NJOY. The AMPX libraries may contain neutron, gamma production and gamma transport data, as well. The produced master libraries can be used either with stand-alone functional modules or with control modules. An assistant package of programs also has been developed in order to facilitate the usage of NJOY. (author)

Verification and validation of multi-group library MUSE1.0 created from ENDF/B-VII.0

International Nuclear Information System (INIS)

Chen Yixue; Wu Jun; Yang Shouhai; Zhang Bin; Lu Daogang; Chen Chaobin

2010-01-01

A multi-group library set named MUSE1.0 with 172-neutron group and 42-photon group is produced based on ENDF/B-VII.0 using NJOY code. Weight function of the multi-group library set is taken from the Vitanim-e library and the max legendre order of scattering matrix is six. All the nuclides have thermal scattering data created using free-gas scattering law and 10 Bondarenko background cross sections se lected to generate the self-shielded multi-group cross sections. The final libraries have GENDF-format, MATXS-format and ACE-multi-group sub-libraries and each sub-library generated under 4 temperatures(293 K,600 K,800 K and 900 K). This paper provides a summary of the procedure to produce the library set and a detail description of the validation of the multi-group library set by several critical benchmark devices and shielding benchmark devices using MCNP code. The ability to handle the thermal neutron transport and resonance self-shielding problems are investigated specially. In the end, we draw the conclusion that the multi-group libraries produced is credible and can be used in the R and D process of Supercritical Water Reactor Design. (authors)

Assessing high affinity binding to HLA-DQ2.5 by a novel peptide library based approach

DEFF Research Database (Denmark)

Jüse, Ulrike; Arntzen, Magnus; Højrup, Peter

2011-01-01

Here we report on a novel peptide library based method for HLA class II binding motif identification. The approach is based on water soluble HLA class II molecules and soluble dedicated peptide libraries. A high number of different synthetic peptides are competing to interact with a limited amount...... library. The eluted sequences fit very well with the previously described HLA-DQ2.5 peptide binding motif. This novel method, limited by library complexity and sensitivity of mass spectrometry, allows the analysis of several thousand synthetic sequences concomitantly in a simple water soluble format....

SCHOOL COMMUNITY PERCEPTION OF LIBRARY APPS AGAINTS LIBRARY EMPOWERMENT

Directory of Open Access Journals (Sweden)

Achmad Riyadi Alberto

2017-07-01

Full Text Available Abstract. This research is motivated by the development of information and communication technology (ICT in the library world so rapidly that allows libraries in the present to develop its services into digital-based services. This study aims to find out the school community’s perception of library apps developed by Riche Cynthia Johan, Hana Silvana, and Holin Sulistyo and its influence on library empowerment at the library of SD Laboratorium Percontohan UPI Bandung. Library apps in this research belong to the context of m-libraries, which is a library that meets the needs of its users by using mobile platforms such as smartphones,computers, and other mobile devices. Empowerment of library is the utilization of all aspects of the implementation of libraries to the best in order to achieve the expected goals. An analysis of the schoolcommunity’s perception of library apps using the Technology Acceptance Model (TAM includes: ease of use, usefulness, usability, usage trends, and real-use conditions. While the empowerment of the library includes aspects: information empowerment, empowerment of learning resources, empowerment of human resources, empowerment of library facilities, and library promotion. The research method used in this research is descriptive method with quantitative approach. Population and sample in this research is school community at SD Laboratorium Percontohan UPI Bandung. Determination of sample criteria by using disproportionate stratified random sampling with the number of samples of 83 respondents. Data analysis using simple linear regression to measure the influence of school community perception about library apps to library empowerment. The result of data analysis shows that there is influence between school community perception about library apps to library empowerment at library of SD Laboratorium Percontohan UPI Bandung which is proved by library acceptance level and library empowerment improvement.

A library for X-ray-matter interaction cross sections for X-ray fluorescence applications

Energy Technology Data Exchange (ETDEWEB)

Brunetti, A. [Istituto di Matematica e Fisica, Universita di Sassari, via Vienna 2, 07100 Sassari (Italy) and INFN, Sezione di Cagliari (Italy)]. E-mail: brunetti@uniss.it; Sanchez del Rio, M. [European Synchrotron Radiation Facility, 6 rue Jules Horowitz, 38043 Grenoble Cedex (France); Golosio, B. [INFN, Sezione di Cagliari (Italy); European Synchrotron Radiation Facility, 6 rue Jules Horowitz, 38043 Grenoble Cedex (France); Simionovici, A. [European Synchrotron Radiation Facility, 6 rue Jules Horowitz, 38043 Grenoble Cedex (France); Laboratoire de Sciences de la Terre, Ecole Normale Superieure, Lyon, F-69364 (France); Somogyi, A. [European Synchrotron Radiation Facility, 6 rue Jules Horowitz, 38043 Grenoble Cedex (France)

2004-10-08

Quantitative estimate of elemental composition by spectroscopic and imaging techniques using X-ray fluorescence requires the availability of accurate data of X-ray interaction with matter. Although a wide number of computer codes and data sets are reported in literature, none of them is presented in the form of freely available library functions which can be easily included in software applications for X-ray fluorescence. This work presents a compilation of data sets from different published works and an xraylib interface in the form of callable functions. Although the target applications are on X-ray fluorescence, cross sections of interactions like photoionization, coherent scattering and Compton scattering, as well as form factors and anomalous scattering functions, are also available.

The Experience of Evidence-Based Practice in an Australian Public Library: An Ethnography

Science.gov (United States)

Gillespie, Ann; Partridge, Helen; Bruce, Christine; Howlett, Alisa

2016-01-01

Introduction: This paper presents the findings from a project that investigated the lived experiences of library and information professionals in relation to evidence-based practice within an Australian public library. Method: The project employed ethnography, which allows holistic description of people's experiences within a particular community…

Affinity-based screening of combinatorial libraries using automated, serial-column chromatography

Energy Technology Data Exchange (ETDEWEB)

Evans, D.M.; Williams, K.P.; McGuinness, B. [PerSeptive Biosystems, Framingham, MA (United States)] [and others

1996-04-01

The authors have developed an automated serial chromatographic technique for screening a library of compounds based upon their relative affinity for a target molecule. A {open_quotes}target{close_quotes} column containing the immobilized target molecule is set in tandem with a reversed-phase column. A combinatorial peptide library is injected onto the target column. The target-bound peptides are eluted from the first column and transferred automatically to the reversed-phase column. The target-specific peptide peaks from the reversed-phase column are identified and sequenced. Using a monoclonal antibody (3E-7) against {beta}-endorphin as a target, we selected a single peptide with sequence YGGFL from approximately 5800 peptides present in a combinatorial library. We demonstrated the applicability of the technology towards selection of peptides with predetermined affinity for bacterial lipopolysaccharide (LPS, endotoxin). We expect that this technology will have broad applications for high throughput screening of chemical libraries or natural product extracts. 21 refs., 4 figs.

Validation of the 172 group ENDFB7GX library

International Nuclear Information System (INIS)

Khan, Suhail Ahmad; Raj, Devesh; Karthikeyan, R.; Jagannathan, V.

2007-01-01

Full text: Five 172 group libraries, viz., IAEAGX, ENDFB6GX, JENDL3GX, JEFF31GX, and LWRPSGX were obtained as a part of the IAEA WIMS Library Update Project (WLUP). The first four libraries have data available for 173 nuclides up to 244 Cm. The LWRPSGX library based on JEFF3.1 point dataset is an extended library up to 252 Cf. Data for 12 more actinides and the related burnup chain were added. The five libraries were validated against known experiments in an earlier work. In general the LWRPSGX was found to be giving better results. Recently another version of 172 group library 'ENDFB7GX' has been released. In the present work we provide the results of validation of the ENDFB7GX library against the same set of experimental data and a comparison with results of other libraries. The experimental configuration data include a variety of uniform lattices with enriched UO 2 , U- metal, mixed oxide (UO 2 -PuO 2 ) fuels with H 2 O and D 2 O moderators for a wide range of enrichment, fuel diameter and ratio of moderator to fuel volume (V m /V f ). The calculations have been done using the code LATTEST which solves the single pin lattice cell problem by 1-D multi-group transport theory after cylindricalising the square or hexagonal cell boundary. The LATTEST code is an improved version of the MURLI code and is capable of providing a ready testing of any new cross section library against a set of experimental benchmark lattices collected from various sources. The calculated k eff values and certain spectral indices, where available, have been compared for all the libraries for more than hundred critical lattices. There is a general under prediction of k eff values by all libraries. The maximum under prediction is for ENDFB6GX library and the least is for JENDL3GX library. The ENDFB7GX library, in general, is found to over predict in comparison to the k eff values obtained using LWRPSGX library. While scrutinizing the basic nuclear data it was noted that the slowing down cross

Analyses of criticality and reactivity for TRACY experiments based on JENDL-3.3 data library

International Nuclear Information System (INIS)

Sono, Hiroki; Miyoshi, Yoshinori; Nakajima, Ken

2003-01-01

The parameters on criticality and reactivity employed for computational simulations of the TRACY supercritical experiments were analyzed using a recently revised nuclear data library, JENDL-3.3. The parameters based on the JENDL-3.3 library were compared to those based on two former-used libraries, JENDL-3.2 and ENDF/B-VI. In the analyses computational codes, MVP, MCNP version 4C and TWOTRAN, were used. The following conclusions were obtained from the analyses: (1) The computational biases of the effective neutron multiplication factor attributable to the nuclear data libraries and to the computational codes do not depend the TRACY experimental conditions such as fuel conditions. (2) The fractional discrepancies in the kinetic parameters and coefficients of reactivity are within ∼5% between the three libraries. By comparison between calculations and measurements of the parameters, the JENDL-3.3 library is expected to give closer values to the measurements than the JENDL-3.2 and ENDF/B-VI libraries. (3) While the reactivity worth of transient rods expressed in the $ unit shows ∼5% discrepancy between the three libraries according to their respective β eff values, there is little discrepancy in that expressed in the Δk/k unit. (author)

Template-based combinatorial enumeration of virtual compound libraries for lipids.

Science.gov (United States)

Sud, Manish; Fahy, Eoin; Subramaniam, Shankar

2012-09-25

A variety of software packages are available for the combinatorial enumeration of virtual libraries for small molecules, starting from specifications of core scaffolds with attachments points and lists of R-groups as SMILES or SD files. Although SD files include atomic coordinates for core scaffolds and R-groups, it is not possible to control 2-dimensional (2D) layout of the enumerated structures generated for virtual compound libraries because different packages generate different 2D representations for the same structure. We have developed a software package called LipidMapsTools for the template-based combinatorial enumeration of virtual compound libraries for lipids. Virtual libraries are enumerated for the specified lipid abbreviations using matching lists of pre-defined templates and chain abbreviations, instead of core scaffolds and lists of R-groups provided by the user. 2D structures of the enumerated lipids are drawn in a specific and consistent fashion adhering to the framework for representing lipid structures proposed by the LIPID MAPS consortium. LipidMapsTools is lightweight, relatively fast and contains no external dependencies. It is an open source package and freely available under the terms of the modified BSD license.

Growing Competition for Libraries.

Science.gov (United States)

Gibbons, Susan

2001-01-01

Describes the Questia subscription-based online academic digital books library. Highlights include weaknesses of the collection; what college students want from a library; importance of marketing; competition for traditional academic libraries that may help improve library services; and the ability of Questia to overcome barriers and…

Libraries Today, Libraries Tomorrow: Contemporary Library Practices and the Role of Library Space in the L

Directory of Open Access Journals (Sweden)

Ana Vogrinčič Čepič

2013-09-01

Full Text Available ABSTRACTPurpose: The article uses sociological concepts in order to rethink the changes in library practices. Contemporary trends are discussed with regard to the changing nature of working habits, referring mostly to the new technology, and the (emergence of the third space phenomenon. The author does not regard libraries only as concrete public service institutions, but rather as complex cultural forms, taking in consideration wider social context with a stress on users’ practices in relation to space.Methodology/approach: The article is based on the (self- observation of the public library use, and on the (discourse analysis of internal library documents (i.e. annual reports and plans and secondary sociological literature. As such, the cultural form approach represents a classic method of sociology of culture.Results: The study of relevant material in combination with direct personal experiences reveals socio-structural causes for the change of users’ needs and habits, and points at the difficulty of spatial redefinition of libraries as well as at the power of the discourse.Research limitations: The article is limited to an observation of users’ practices in some of the public libraries in Ljubljana and examines only a small number of annual reports – the discoveries are then further debated from the sociological perspective.Originality/practical implications: The article offers sociological insight in the current issues of the library science and tries to suggest a wider explanation that could answer some of the challenges of the contemporary librarianship.

School Library Media Specialists Inform Technology Preparation of Library Science Students: An Evidence-Based Discussion

Science.gov (United States)

Snyder, Donna L.; Miller, Andrea L.

2009-01-01

What is the relative importance of current and emerging technologies in school library media programs? In order to answer this question, in Fall 2007 the authors administered a survey to 1,053 school library media specialists (SLMSs) throughout the state of Pennsylvania. As a part of the MSLS degree with Library Science K-12 certification, Clarion…

Libraries and Accessibility: Istanbul Public Libraries Case

Directory of Open Access Journals (Sweden)

Gül Yücel

2016-12-01

Full Text Available In the study; the assessment of accessibility has been conducted in Istanbul public libraries within the scope of public area. Public libraries commonly serve with its user of more than 20 million in total, spread to the general of Turkey, having more than one thousand branches in the centrums and having more than one million registered members. The building principles and standards covering the subjects such as the selection of place, historical and architectural specification of the region, distance to the centre of population and design in a way that the disabled people could benefit from the library services fully have been determined with regulations in the construction of new libraries. There are works for the existent libraries such as access for the disabled, fire safety precautions etc. within the scope of the related standards. Easy access by everyone is prioritized in the public libraries having a significant role in life-long learning. The purpose of the study is to develop solution suggestions for the accessibility problems in the public libraries. The study based on the eye inspection and assessments carried out within the scope of accessibility in the public libraries subsidiary to Istanbul Culture and Tourism Provincial Directorate Library and Publications Department within the provincial borders of Istanbul. The arrangements such as reading halls, study areas, book shelves etc. have been examined within the frame of accessible building standards. Building entrances, ramps and staircases, horizontal and vertical circulation of building etc. have been taken into consideration within the scope of accessible building standards. The subjects such as the reading and studying areas and book shelf arrangements for the library have been assessed within the scope of specific buildings. There are a total of 34 public libraries subsidiary to Istanbul Culture and Tourism Provincial Directorate on condition that 20 ea. of them are in the

Availability and accessibility of evidence-based information resources provided by medical libraries in Australia.

Science.gov (United States)

Ritchie, A; Sowter, B

2000-01-01

This article reports on the results of an exploratory survey of the availability and accessibility of evidence-based information resources provided by medical libraries in Australia. Although barriers impede access to evidence-based information for hospital clinicians, the survey revealed that Medline and Cinahl are available in over 90% of facilities. In most cases they are widely accessible via internal networks and the Internet. The Cochrane Library is available in 69% of cases. The Internet is widely accessible and most libraries provide access to some full-text, electronic journals. Strategies for overcoming restrictions and integrating information resources with clinical workflow are being pursued. State, regional and national public and private consortia are developing agreements utilising on-line technology. These could produce cost savings and more equitable access to a greater range of evidence-based resources.

Introduction of library administration system using an office computer in the smallscale library

International Nuclear Information System (INIS)

Itabashi, Keizo; Ishikawa, Masashi

1984-01-01

Research Information Center was established in Fusion Research Center at Naka site as a new section of Department of Technical Information of Japan Atomic Energy Research Institute. A library materials management system utilizing an office computer was introduced to provide good services. The system is a total-system centered on services at counter except purchase business and the serviced materials are books, reports, journals and pamphlets. The system has produced good effects on many aspects, e.g. a significantly easy inventory of library materials, and complete removal of user's handwriting for borrowing materials, by using an optical chracter recognition handscanner. Those improvements have resulted in better image of the library. (author)

MOSFET-like CNFET based logic gate library for low-power application: a comparative study

International Nuclear Information System (INIS)

Gowri Sankar, P. A.; Udhayakumar, K.

2014-01-01

The next generation of logic gate devices are expected to depend upon radically new technologies mainly due to the increasing difficulties and limitations of existing CMOS technology. MOSFET like CNFETs should ideally be the best devices to work with for high-performance VLSI. This paper presents results of a comprehensive comparative study of MOSFET-like carbon nanotube field effect transistors (CNFETs) technology based logic gate library for high-speed, low-power operation than conventional bulk CMOS libraries. It focuses on comparing four promising logic families namely: complementary-CMOS (C-CMOS), transmission gate (TG), complementary pass logic (CPL) and Domino logic (DL) styles are presented. Based on these logic styles, the proposed library of static and dynamic NAND-NOR logic gates, XOR, multiplexer and full adder functions are implemented efficiently and carefully analyzed with a test bench to measure propagation delay and power dissipation as a function of supply voltage. This analysis provides the right choice of logic style for low-power, high-speed applications. Proposed logic gates libraries are simulated using Synopsys HSPICE based on the standard 32 nm CNFET model. The simulation results demonstrate that, it is best to use C-CMOS logic style gates that are implemented in CNFET technology which are superior in performance compared to other logic styles, because of their low average power-delay-product (PDP). The analysis also demonstrates how the optimum supply voltage varies with logic styles in ultra-low power systems. The robustness of the proposed logic gate library is also compared with conventional and state-art of CMOS logic gate libraries. (semiconductor integrated circuits)

ADL-3. Nuclear data library for activation and transmutation calculations

International Nuclear Information System (INIS)

Grudzevich, O.T.; Zelenetskij, A.V.; Ignatyuk, A.V.; Pashchenko, A.B.

1995-07-01

It is shown that the use of simplified approaches to calculate threshold neutron reaction cross-sections is not acceptable for the generation of cross-section libraries. Although rigorous models are complex and involve laborious calculations, they provide the only reliable means for evaluating cross-sections when no experimental data are available. A brief description is given of the new version of the library ADL-3 generated by the authors. It contains 18,200 excitation functions of reactions induced by neutrons of up to 20 MeV. The threshold reaction cross-sections have been calculated in the Hauser-Feshbach-Moldauer formalism with allowance for the contribution of non-equilibrium processes. The cross-sections obtained have been tested by comparison with experimental data and evaluations from other libraries. (author)

Verification study of thorium cross section in MVP calculation of thorium based fuel core using experimental data

International Nuclear Information System (INIS)

Mai, V. T.; Fujii, T.; Wada, K.; Kitada, T.; Takaki, N.; Yamaguchi, A.; Watanabe, H.; Unesaki, H.

2012-01-01

Considering the importance of thorium data and concerning about the accuracy of Th-232 cross section library, a series of experiments of thorium critical core carried out at KUCA facility of Kyoto Univ. Research Reactor Inst. have been analyzed. The core was composed of pure thorium plates and 93% enriched uranium plates, solid polyethylene moderator with hydro to U-235 ratio of 140 and Th-232 to U-235 ratio of 15.2. Calculations of the effective multiplication factor, control rod worth, reactivity worth of Th plates have been conducted by MVP code using JENDL-4.0 library [1]. At the experiment site, after achieving the critical state with 51 fuel rods inserted inside the reactor, the measurements of the reactivity worth of control rod and thorium sample are carried out. By comparing with the experimental data, the calculation overestimates the effective multiplication factor about 0.90%. Reactivity worth of the control rods evaluation using MVP is acceptable with the maximum discrepancy about the statistical error of the measured data. The calculated results agree to the measurement ones within the difference range of 3.1% for the reactivity worth of one Th plate. From this investigation, further experiments and research on Th-232 cross section library need to be conducted to provide more reliable data for thorium based fuel core design and safety calculation. (authors)

SPOTS4. Group data library and computer code, preparing ENDF/B-4 data for input to LEOPARD

International Nuclear Information System (INIS)

Kim, J.D.; Lee, J.T.

1981-09-01

The magnetic tape SPOTS4 contains in file 1 a data library to be used as input to the SPOTS4 program which is contained in file 2. The data library is based on ENDF/B-4 and consists of two parts in TEMPEST format (246 groups) and MUFT format (54 groups) respectively. From this library the SPOTS4 program produces a 172 + 54 group library for LEOPARD input. A copy of the magnetic tape is available from the IAEA Nuclear Data Section. (author)

New Neutron, Proton, and S(α,β) MCNP Data Libraries Based on ENDF/B-VII

International Nuclear Information System (INIS)

Little, Robert C.; Trellue, Holly R.; MacFarlane, Robert E.; Kahler, A.C.; Lee, Mary Beth; White, Morgan C.

2008-01-01

The general-purpose Evaluated Nuclear Data File ENDF/B-VII.0 was released in December 2006. A number of sub-libraries were included in ENDF/B-VII.0 such that data were provided for incident neutrons, photons, and charged particles. This paper describes the creation of MCNP data libraries at Los Alamos National Laboratory based on three ENDF/B-VII.0 sub-libraries: neutrons, protons, and thermal scattering. An ACE-formatted continuous-energy neutron data library called ENDF70 for MCNP has been produced. This library provides data for 390 materials at five temperatures: 293.6, 600, 900, 1200, and 2500 K. The library was processed primarily with Version 248 of NJOY99. Extensive checking and quality-assurance tests were applied to the data. Improvements to the processing code were made and certain evaluations were modified as a result of these tests. ENDF/B-VII.0 included proton evaluations for 48 target materials. Forty-seven proton evaluations (all except for 13 C) were processed at room temperature and combined into the MCNP library ENDF70PROT. Neutron thermal S(α,β) scattering data exist for twenty different materials in ENDF/B-VII.0. All twenty of these evaluations were processed at all applicable temperatures (these vary for each evaluation), and combined into the MCNP library ENDF70SAB. All of these ENDF/B-VII.0 based MCNP libraries (ENDF70, ENDF70PROT, and ENDF70SAB) are available as part of the MCNP5 1.50 release. (authors)

Douglass Rationalization: An Evaluation of a Team Environment and a Computer-Based Task in Academic Libraries

Science.gov (United States)

Denda, Kayo; Smulewitz, Gracemary

2004-01-01

In the contemporary library environment, the presence of the Internet and the infrastructure of the integrated library system suggest an integrated internal organization. The article describes the example of Douglass Rationalization, a team-based collaborative project to refocus the collection of Rutgers' Douglass Library, taking advantage of the…

New evaluation of thermal neutron scattering libraries for light and heavy water

Directory of Open Access Journals (Sweden)

Marquez Damian Jose Ignacio

2017-01-01

Full Text Available In order to improve the design and safety of thermal nuclear reactors and for verification of criticality safety conditions on systems with significant amount of fissile materials and water, it is necessary to perform high-precision neutron transport calculations and estimate uncertainties of the results. These calculations are based on neutron interaction data distributed in evaluated nuclear data libraries. To improve the evaluations of thermal scattering sub-libraries, we developed a set of thermal neutron scattering cross sections (scattering kernels for hydrogen bound in light water, and deuterium and oxygen bound in heavy water, in the ENDF-6 format from room temperature up to the critical temperatures of molecular liquids. The new evaluations were generated and processable with NJOY99 and also with NJOY-2012 with minor modifications (updates, and with the new version of NJOY-2016. The new TSL libraries are based on molecular dynamics simulations with GROMACS and recent experimental data, and result in an improvement of the calculation of single neutron scattering quantities. In this work, we discuss the importance of taking into account self-diffusion in liquids to accurately describe the neutron scattering at low neutron energies (quasi-elastic peak problem. To improve modeling of heavy water, it is important to take into account temperature-dependent static structure factors and apply Sköld approximation to the coherent inelastic components of the scattering matrix. The usage of the new set of scattering matrices and cross-sections improves the calculation of thermal critical systems moderated and/or reflected with light/heavy water obtained from the International Criticality Safety Benchmark Evaluation Project (ICSBEP handbook. For example, the use of the new thermal scattering library for heavy water, combined with the ROSFOND-2010 evaluation of the cross sections for deuterium, results in an improvement of the C/E ratio in 48 out of

New evaluation of thermal neutron scattering libraries for light and heavy water

Science.gov (United States)

Marquez Damian, Jose Ignacio; Granada, Jose Rolando; Cantargi, Florencia; Roubtsov, Danila

2017-09-01

In order to improve the design and safety of thermal nuclear reactors and for verification of criticality safety conditions on systems with significant amount of fissile materials and water, it is necessary to perform high-precision neutron transport calculations and estimate uncertainties of the results. These calculations are based on neutron interaction data distributed in evaluated nuclear data libraries. To improve the evaluations of thermal scattering sub-libraries, we developed a set of thermal neutron scattering cross sections (scattering kernels) for hydrogen bound in light water, and deuterium and oxygen bound in heavy water, in the ENDF-6 format from room temperature up to the critical temperatures of molecular liquids. The new evaluations were generated and processable with NJOY99 and also with NJOY-2012 with minor modifications (updates), and with the new version of NJOY-2016. The new TSL libraries are based on molecular dynamics simulations with GROMACS and recent experimental data, and result in an improvement of the calculation of single neutron scattering quantities. In this work, we discuss the importance of taking into account self-diffusion in liquids to accurately describe the neutron scattering at low neutron energies (quasi-elastic peak problem). To improve modeling of heavy water, it is important to take into account temperature-dependent static structure factors and apply Sköld approximation to the coherent inelastic components of the scattering matrix. The usage of the new set of scattering matrices and cross-sections improves the calculation of thermal critical systems moderated and/or reflected with light/heavy water obtained from the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook. For example, the use of the new thermal scattering library for heavy water, combined with the ROSFOND-2010 evaluation of the cross sections for deuterium, results in an improvement of the C/E ratio in 48 out of 65

Developing Applications in the Era of Cloud-based SaaS Library Systems

Directory of Open Access Journals (Sweden)

Josh Weisman

2014-10-01

Full Text Available As the move to cloud-based SaaS library systems accelerates, we must consider what it means to develop applications when the core of the system isn't under the library's control. The entire application lifecycle is changing, from development to testing to production. Developing applications for cloud solutions raises new concerns, such as security, multi-tenancy, latency, and analytics. In this article, we review the landscape and suggest a view of how to be successful for the benefit of library staff and end-users in this new reality. We discuss what kinds of APIs and protocols vendors should be supporting, and suggest how best to take advantage of the innovations being introduced.

More than a House of Cards: Developing a Firm Foundation for Streaming Media and Consumer-Licensed Content in the Library

Directory of Open Access Journals (Sweden)

William Cross

2016-09-01

Full Text Available This article will introduce traditional library practice for licensing multimedia content and discuss the way that consumer-licensing and streaming services disrupt that practice. Sections II and III describe the statutory copyright regime designed by Congress to facilitate the socially-valuable work done by libraries and the impact of the move from ownership to licensed content. Collecting multimedia materials has always presented special legal challenges for libraries, particularly as licensed content has replaced the traditional practice of purchasing and circulation based on the first sale doctrine. These issues have grown even more complex as streaming services like Netflix and Amazon and video game downloads through services like Steam have come to dominate the landscape. Section IV will describe the way that consumer-licensed materials, which not only remove the ownership that undergirds library practice, but also the ability to negotiate for library use, imperil the congressionally-designed balance. Section V will present a path forward for libraries to develop robust, cutting-edge collections that reflect a sophisticated understanding of the contractual and copyright issues at play.

Effect of new cross-section evaluations on criticality and neutron energy spectrum of a typical material test research reactor

International Nuclear Information System (INIS)

Ahmad, Siraj-ul-Islam; Ahmad, Nasir; Aslam

2004-01-01

Several new WIMSD libraries based on recent cross-section evaluations such as IAEA, ENDFB-VI, JENDL, and JEF have been made available by IAEA. These libraries were used for the computation of multiplication factor and energy spectrum for Pakistan Research Reactor-1 (PARR-1). Methodology was validated for benchmark problems made available by IAEA and comparison with reference results. The value of effective multiplication factors for all newly released libraries are 1.8-3.2% less than that of 1981 WIMSD library. The effect of various cross-section libraries on neutron energy spectrum was also studied. Differences of about -10% to 12.5% were found in thermal flux using the newly released libraries as compared with that obtained using 1981 WIMSD library. From the analysis, it was found that the main source of the difference is the cross-sections of hydrogen bound in water. When these cross-sections of hydrogen (bound in water) from new libraries were used along with all other data in 1981 WIMSD library, the k eff obtained in this way has a difference of only 0.02-0.8% with that obtained from new libraries, while the flux spectrum agreed within 1% below 1 MeV with new libraries

BROND: USSR Evaluated Neutron Data Library

International Nuclear Information System (INIS)

Manokhin, V.N.; Lemmel, H.D.; McLaughlin, P.K.

1989-10-01

BROND, the USSR computerized data library for evaluated neutron reaction data was released in 1987/1989. Upon request it is available on magnetic tape, costfree, from the IAEA Nuclear Data Section. This document describes the contents of this library in the versions BROND-NDS1 and BROND-NDS2. (author). 16 refs

Collection-based analysis of selected medical libraries in the Philippines using Doody’s Core Titles

Directory of Open Access Journals (Sweden)

Efren Torres Jr., MLIS

2017-01-01

Conclusion: De La Salle Health Sciences Institute and University of Santo Tomas had sound medical collections based on Doody’s Core Titles. Collectively, the medical libraries shared common collection development priorities, as evidenced by similarities in strong areas. Library budget and the role of the library director in book selection were among the factors that could contributed to a high percentage of match titles.

Libraries and the USA PATRIOT Act

National Research Council Canada - National Science Library

Doyle, Charles

2005-01-01

.... It has several provisions, however, that might apply in a library context. The most frequently mentioned of these is Section 215 that amends the business record sections of the Foreign Surveillance Intelligence Act (FISA...

Afghanistan Digital Library Initiative: Revitalizing an Integrated Library System

Directory of Open Access Journals (Sweden)

Yan HAN

2007-12-01

Full Text Available This paper describes an Afghanistan digital library initiative of building an integrated library system (ILS for Afghanistan universities and colleges based on open-source software. As one of the goals of the Afghan eQuality Digital Libraries Alliance, the authors applied systems analysis approach, evaluated different open-source ILSs, and customized the selected software to accommodate users’ needs. Improvements include Arabic and Persian language support, user interface changes, call number label printing, and ISBN-13 support. To our knowledge, this ILS is the first at a large academic library running on open-source software.

Iowa DNR - NRGIS Library

Data.gov (United States)

Iowa State University GIS Support and Research Facility — The Natural Resources Geographic Information System (NRGIS) Library is a Geographic Information System (GIS) repository developed and maintained by the GIS Section...

The library assessment cookbook

CERN Document Server

Dobbs, Aaron W

2017-01-01

The Library Assessment Cookbook features 80 practical, easy-to-implement recipes divided into nine sections. This Cookbook will help librarians of all levels of experience measure and demonstrate their institutional value.

Preparation of next generation set of group cross sections. 3

International Nuclear Information System (INIS)

Kaneko, Kunio

2002-03-01

This fiscal year, based on the examination result about the evaluation energy range of heavy element unresolved resonance cross sections, the upper energy limit of the energy range, where ultra-fine group cross sections are produced, was raised to 50 keV, and an improvement of the group cross section processing system was promoted. At the same time, reflecting the result of studies carried out till now, a function producing delayed neutron data was added to the general-purpose group cross section processing system , thus the preparation of general purpose group cross section processing system has been completed. On the other hand, the energy structure, data constitution and data contents of next generation group cross section set were determined, and the specification of a 151 groups next generation group cross section set was defined. Based on the above specification, a concrete library format of the next generation cross section set has been determined. After having carried out the above-described work, using the general-purpose group cross section processing system , which was complete in this study, with use of the JENDL-3. 2 evaluated nuclear data, the 151 groups next generation group cross section of 92 nuclides and the ultra fine group resonance cross section library for 29 nuclides have been prepared. Utilizing the 151 groups next generation group cross section set and the ultra-fine group resonance cross-section library, a bench mark test calculation of fast reactors has been performed by using an advanced lattice calculation code. It was confirmed, by comparing the calculation result with a calculation result of continuous energy Monte Carlo code, that the 151 groups next generation cross section set has sufficient accuracy. (author)

Library based x-ray scatter correction for dedicated cone beam breast CT

International Nuclear Information System (INIS)

Shi, Linxi; Zhu, Lei; Vedantham, Srinivasan; Karellas, Andrew

2016-01-01

Purpose: The image quality of dedicated cone beam breast CT (CBBCT) is limited by substantial scatter contamination, resulting in cupping artifacts and contrast-loss in reconstructed images. Such effects obscure the visibility of soft-tissue lesions and calcifications, which hinders breast cancer detection and diagnosis. In this work, we propose a library-based software approach to suppress scatter on CBBCT images with high efficiency, accuracy, and reliability. Methods: The authors precompute a scatter library on simplified breast models with different sizes using the GEANT4-based Monte Carlo (MC) toolkit. The breast is approximated as a semiellipsoid with homogeneous glandular/adipose tissue mixture. For scatter correction on real clinical data, the authors estimate the breast size from a first-pass breast CT reconstruction and then select the corresponding scatter distribution from the library. The selected scatter distribution from simplified breast models is spatially translated to match the projection data from the clinical scan and is subtracted from the measured projection for effective scatter correction. The method performance was evaluated using 15 sets of patient data, with a wide range of breast sizes representing about 95% of general population. Spatial nonuniformity (SNU) and contrast to signal deviation ratio (CDR) were used as metrics for evaluation. Results: Since the time-consuming MC simulation for library generation is precomputed, the authors’ method efficiently corrects for scatter with minimal processing time. Furthermore, the authors find that a scatter library on a simple breast model with only one input parameter, i.e., the breast diameter, sufficiently guarantees improvements in SNU and CDR. For the 15 clinical datasets, the authors’ method reduces the average SNU from 7.14% to 2.47% in coronal views and from 10.14% to 3.02% in sagittal views. On average, the CDR is improved by a factor of 1.49 in coronal views and 2.12 in sagittal

Library based x-ray scatter correction for dedicated cone beam breast CT

Energy Technology Data Exchange (ETDEWEB)

Shi, Linxi; Zhu, Lei, E-mail: leizhu@gatech.edu [Nuclear and Radiological Engineering and Medical Physics Programs, The George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States); Vedantham, Srinivasan; Karellas, Andrew [Department of Radiology, University of Massachusetts Medical School, Worcester, Massachusetts 01655 (United States)

2016-08-15

Purpose: The image quality of dedicated cone beam breast CT (CBBCT) is limited by substantial scatter contamination, resulting in cupping artifacts and contrast-loss in reconstructed images. Such effects obscure the visibility of soft-tissue lesions and calcifications, which hinders breast cancer detection and diagnosis. In this work, we propose a library-based software approach to suppress scatter on CBBCT images with high efficiency, accuracy, and reliability. Methods: The authors precompute a scatter library on simplified breast models with different sizes using the GEANT4-based Monte Carlo (MC) toolkit. The breast is approximated as a semiellipsoid with homogeneous glandular/adipose tissue mixture. For scatter correction on real clinical data, the authors estimate the breast size from a first-pass breast CT reconstruction and then select the corresponding scatter distribution from the library. The selected scatter distribution from simplified breast models is spatially translated to match the projection data from the clinical scan and is subtracted from the measured projection for effective scatter correction. The method performance was evaluated using 15 sets of patient data, with a wide range of breast sizes representing about 95% of general population. Spatial nonuniformity (SNU) and contrast to signal deviation ratio (CDR) were used as metrics for evaluation. Results: Since the time-consuming MC simulation for library generation is precomputed, the authors’ method efficiently corrects for scatter with minimal processing time. Furthermore, the authors find that a scatter library on a simple breast model with only one input parameter, i.e., the breast diameter, sufficiently guarantees improvements in SNU and CDR. For the 15 clinical datasets, the authors’ method reduces the average SNU from 7.14% to 2.47% in coronal views and from 10.14% to 3.02% in sagittal views. On average, the CDR is improved by a factor of 1.49 in coronal views and 2.12 in sagittal

Introduction of library administration system using an office computer in the smallscale library

Energy Technology Data Exchange (ETDEWEB)

Itabashi, Keizo; Ishikawa, Masashi

1984-01-01

Research Information Center was established in Fusion Research Center at Naka site as a new section of Department of Technical Information of Japan Atomic Energy Research Institute. A library materials management system utilizing an office computer was introduced to provide good services. The system is a total-system centered on services at counter except purchase business and the serviced materials are books, reports, journals and pamphlets. The system has produced good effects on many aspects, e.g. a significantly easy inventory of library materials, and complete removal of user's handwriting for borrowing materials, by using an optical chracter recognition handscanner. Those improvements have resulted in better image of the library.

Modeling of frequency agile devices: development of PKI neuromodeling library based on hierarchical network structure

Science.gov (United States)

Sanchez, P.; Hinojosa, J.; Ruiz, R.

2005-06-01

Recently, neuromodeling methods of microwave devices have been developed. These methods are suitable for the model generation of novel devices. They allow fast and accurate simulations and optimizations. However, the development of libraries makes these methods to be a formidable task, since they require massive input-output data provided by an electromagnetic simulator or measurements and repeated artificial neural network (ANN) training. This paper presents a strategy reducing the cost of library development with the advantages of the neuromodeling methods: high accuracy, large range of geometrical and material parameters and reduced CPU time. The library models are developed from a set of base prior knowledge input (PKI) models, which take into account the characteristics common to all the models in the library, and high-level ANNs which give the library model outputs from base PKI models. This technique is illustrated for a microwave multiconductor tunable phase shifter using anisotropic substrates. Closed-form relationships have been developed and are presented in this paper. The results show good agreement with the expected ones.

ACTIV87 Fast neutron activation cross section file 1987

International Nuclear Information System (INIS)

Manokhin, V.N.; Pashchenko, A.B.; Plyaskin, V.I.; Bychkov, V.M.; Pronyaev, V.G.; Schwerer, O.

1989-10-01

This document summarizes the content of the Fast Neutron Activation Cross Section File based on data from different evaluated data libraries and individual evaluations in ENDF/B-5 format. The entire file or selective retrievals from it are available on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

BROND. USSR Evaluated Neutron Data Library

International Nuclear Information System (INIS)

Manokhin, V.N.

1990-09-01

BROND, the USSR computerized data library for evaluated neutron reaction data was released in 1987/1990. Upon request it is available on magnetic tape, costfree, from the IAEA Nuclear Data Section. This document describes the contents of this library in the versions BROND-NDS1 and BROND-NDS2, BROND-NDS3, BROND-NDS4. (author). 16 refs

BROND: USSR evaluated neutron data library

International Nuclear Information System (INIS)

Manokhin, V.N.

1991-03-01

BROND, the USSR computerized data library for evaluated neutron reaction data was released in 1987/1990. Upon request it is available on magnetic tape, costfree, from the IAEA Nuclear Data Section. This document describes the contents of this library in the four supplements BROND-NDS1, BROND-NDS2, BROND-NDS3, BROND-NDS4. (author). 16 refs

MPI version of NJOY and its application to multigroup cross-section generation

Energy Technology Data Exchange (ETDEWEB)

Alpan, A.; Haghighat, A.

1999-07-01

Multigroup cross-section libraries are needed in performing neutronics calculations. These libraries are referred to as broad-group libraries. The number of energy groups and group structure are highly dependent on the application and/or user's objectives. For example, for shielding calculations, broad-group libraries such as SAILOR and BUGLE with 47-neutron and 20-gamma energy groups are used. The common procedure to obtain a broad-group library is a three-step process: (1) processing pointwise ENDF (PENDF) format cross sections; (2) generating fine-group cross sections; and (3) collapsing fine-group cross sections to broad-group. The NJOY code is used to prepare fine-group cross sections by processing pointwise ENDF data. The code has several modules, each one performing a specific task. For instance, the module RECONR performs linearization and reconstruction of the cross sections, and the module GROUPR generates multigroup self-shielded cross sections. After fine-group, i.e., groupwise ENDF (GENDF), cross sections are produced, cross sections are self-shielded, and a one-dimensional transport calculation is performed to obtain flux spectra at specific regions in the model. These fluxes are then used as weighting functions to collapse the fine-group cross sections to obtain a broad-group cross-section library. The third step described is commonly performed by the AMPX code system. SMILER converts NJOY GENDF filed to AMPX master libraries, AJAX collects the master libraries. BONAMI performs self-shielding calculations, NITAWL converts the AMPX master library to a working library, XSDRNPM performs one-dimensional transport calculations, and MALOCS collapses fine-group cross sections to broad-group. Finally, ALPO is used to generate ANISN format libraries. In this three-step procedure, generally NJOY requires the largest amount of CPU time. This time varies depending on the user's specified parameters for each module, such as reconstruction tolerances

MPI version of NJOY and its application to multigroup cross-section generation

International Nuclear Information System (INIS)

Alpan, A.; Haghighat, A.

1999-01-01

Multigroup cross-section libraries are needed in performing neutronics calculations. These libraries are referred to as broad-group libraries. The number of energy groups and group structure are highly dependent on the application and/or user's objectives. For example, for shielding calculations, broad-group libraries such as SAILOR and BUGLE with 47-neutron and 20-gamma energy groups are used. The common procedure to obtain a broad-group library is a three-step process: (1) processing pointwise ENDF (PENDF) format cross sections; (2) generating fine-group cross sections; and (3) collapsing fine-group cross sections to broad-group. The NJOY code is used to prepare fine-group cross sections by processing pointwise ENDF data. The code has several modules, each one performing a specific task. For instance, the module RECONR performs linearization and reconstruction of the cross sections, and the module GROUPR generates multigroup self-shielded cross sections. After fine-group, i.e., groupwise ENDF (GENDF), cross sections are produced, cross sections are self-shielded, and a one-dimensional transport calculation is performed to obtain flux spectra at specific regions in the model. These fluxes are then used as weighting functions to collapse the fine-group cross sections to obtain a broad-group cross-section library. The third step described is commonly performed by the AMPX code system. SMILER converts NJOY GENDF filed to AMPX master libraries, AJAX collects the master libraries. BONAMI performs self-shielding calculations, NITAWL converts the AMPX master library to a working library, XSDRNPM performs one-dimensional transport calculations, and MALOCS collapses fine-group cross sections to broad-group. Finally, ALPO is used to generate ANISN format libraries. In this three-step procedure, generally NJOY requires the largest amount of CPU time. This time varies depending on the user's specified parameters for each module, such as reconstruction tolerances, temperatures

Six-Year Planning Report for Crosby Library, Gonzaga University.

Science.gov (United States)

Gonzaga Univ., Spokane, WA.

A response to a call for six-year planning documents from Gonzaga University's instructional units, this report is divided into five broad sections: (1) library collections, an assessment of Crosby Library's holdings and comparison with the overall quantitative standards established by the Association of College and Research Libraries; (2) library…

Incorporating Library School Interns on Academic Library Subject Teams

Science.gov (United States)

Sargent, Aloha R.; Becker, Bernd W.; Klingberg, Susan

2011-01-01

This case study analyzes the use of library school interns on subject-based teams for the social sciences, humanities, and sciences in the San Jose State University Library. Interns worked closely with team librarians on reference, collection development/management, and instruction activities. In a structured focus group, interns reported that the…

Libraries serving dialogue

CERN Document Server

Dupont, Odile

2014-01-01

This book based on experiences of libraries serving interreligious dialogue, presents themes like library tools serving dialogue between cultures, collections dialoguing, children and young adults dialoguing beyond borders, story telling as dialog, librarians serving interreligious dialogue.

Endf/B-VII.0 Based Library for Paragon - 313

International Nuclear Information System (INIS)

Huria, H.C.; Kucukboyaci, V.N.; Ouisloumen, M.

2010-01-01

A new 70-group library has been generated for the Westinghouse lattice physics code PARAGON using the ENDF/B-VII.0 nuclear data files. The new library retains the major features of the current library, including the number of energy groups and the reduction in the U-238 resonance integral. The upper bound for the up-scattering effects in the new library, however, has been moved to 4.0 eV from 2.1 eV for better MOX fuel predictions. The new library has been used to analyze standard benchmarks and also to compare the measured and predicted parameters for different types of Westinghouse and Combustion Engineering (CE) type operating reactor cores. Results indicate that the new library will not impact the reactivity, power distribution and the temperature coefficient predictions over a wide range of physics design parameters; however, will improve the MOX core predictions. In other words, the ENDF/B-VI.3 and ENDF/B-VII.0 produce similar results for reactor core calculations. (authors)

Reference neutron activation library

International Nuclear Information System (INIS)

2002-04-01

Many scientific endeavors require accurate nuclear data. Examples include studies of environmental protection connected with the running of a nuclear installation, the conceptual designs of fusion energy producing devices, astrophysics and the production of medical isotopes. In response to this need, many national and international data libraries have evolved over the years. Initially nuclear data work concentrated on materials relevant to the commercial power industry which is based on the fission of actinides, but recently the topic of activation has become of increasing importance. Activation of materials occurs in fission devices, but is generally overshadowed by the primary fission process. In fusion devices, high energy (14 MeV) neutrons produced in the D-T fusion reaction cause activation of the structure, and (with the exception of the tritium fuel) is the dominant source of activity. Astrophysics requires cross-sections (generally describing neutron capture) or its studies of nucleosynthesis. Many analytical techniques require activation analysis. For example, borehole logging uses the detection of gamma rays from irradiated materials to determine the various components of rocks. To provide data for these applications, various specialized data libraries have been produced. The most comprehensive of these have been developed for fusion studies, since it has been appreciated that impurities are of the greatest importance in determining the overall activity, and thus data on all elements are required. These libraries contain information on a wide range of reactions: (n,γ), (n,2n), (n,α), (n,p), (n,d), (n,t), (n, 3 He)and (n,n')over the energy range from 10 -5 eV to 15 or 20 MeV. It should be noted that the production of various isomeric states have to be treated in detail in these libraries,and that the range of targets must include long-lived radioactive nuclides in addition to stable nuclides. These comprehensive libraries thus contain almost all the

Reference neutron activation library

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-04-01

Many scientific endeavors require accurate nuclear data. Examples include studies of environmental protection connected with the running of a nuclear installation, the conceptual designs of fusion energy producing devices, astrophysics and the production of medical isotopes. In response to this need, many national and international data libraries have evolved over the years. Initially nuclear data work concentrated on materials relevant to the commercial power industry which is based on the fission of actinides, but recently the topic of activation has become of increasing importance. Activation of materials occurs in fission devices, but is generally overshadowed by the primary fission process. In fusion devices, high energy (14 MeV) neutrons produced in the D-T fusion reaction cause activation of the structure, and (with the exception of the tritium fuel) is the dominant source of activity. Astrophysics requires cross-sections (generally describing neutron capture) or its studies of nucleosynthesis. Many analytical techniques require activation analysis. For example, borehole logging uses the detection of gamma rays from irradiated materials to determine the various components of rocks. To provide data for these applications, various specialized data libraries have been produced. The most comprehensive of these have been developed for fusion studies, since it has been appreciated that impurities are of the greatest importance in determining the overall activity, and thus data on all elements are required. These libraries contain information on a wide range of reactions: (n,{gamma}), (n,2n), (n,{alpha}), (n,p), (n,d), (n,t), (n,{sup 3}He)and (n,n')over the energy range from 10{sup -5} eV to 15 or 20 MeV. It should be noted that the production of various isomeric states have to be treated in detail in these libraries,and that the range of targets must include long-lived radioactive nuclides in addition to stable nuclides. These comprehensive libraries thus contain

A revision of photon interaction data in the UKAEA nuclear data library

International Nuclear Information System (INIS)

Knipe, A.D.

1975-10-01

Photon interaction data in the UKAEA Nuclear Data Library have been updated and extended to cover all elements up to Atomic Number 94. Cross-sections for the photoelectric effect, Compton scattering, pair-production, and the total cross-section, are stored at 40 energy points in the range 0.01 MeV to 20 MeV. The angular distribution for Compton scattering is also included in the library. This report describes the derivation and accuracy of the data, and tabulates the cross-sections and angular distribution in the appendices. The preparation of multigroup cross-sections from the library's data is also discussed. (author)

Assessing the Library Homepages of COPLAC Institutions for Section 508 Accessibility Errors: Who's Accessible, Who's Not, and How the Online WebXACT Assessment Tool Can Help

Science.gov (United States)

Huprich, Julia; Green, Ravonne

2007-01-01

The Council on Public Liberal Arts Colleges (COPLAC) libraries websites were assessed for Section 508 errors using the online WebXACT tool. Only three of the twenty-one institutions (14%) had zero accessibility errors. Eighty-six percent of the COPLAC institutions had an average of 1.24 errors. Section 508 compliance is required for institutions…

The mathematics of a successful deconvolution: a quantitative assessment of mixture-based combinatorial libraries screened against two formylpeptide receptors.

Science.gov (United States)

Santos, Radleigh G; Appel, Jon R; Giulianotti, Marc A; Edwards, Bruce S; Sklar, Larry A; Houghten, Richard A; Pinilla, Clemencia

2013-05-30

In the past 20 years, synthetic combinatorial methods have fundamentally advanced the ability to synthesize and screen large numbers of compounds for drug discovery and basic research. Mixture-based libraries and positional scanning deconvolution combine two approaches for the rapid identification of specific scaffolds and active ligands. Here we present a quantitative assessment of the screening of 32 positional scanning libraries in the identification of highly specific and selective ligands for two formylpeptide receptors. We also compare and contrast two mixture-based library approaches using a mathematical model to facilitate the selection of active scaffolds and libraries to be pursued for further evaluation. The flexibility demonstrated in the differently formatted mixture-based libraries allows for their screening in a wide range of assays.

Development of library documents in BRICEM on network-based environment

International Nuclear Information System (INIS)

Gao Renxi

2010-01-01

With the development of the internet, the transformation from a traditional library to a modem one is essential to the development of BRICEM (Beijing Research Institute of Chemical Engineering and Metallurgy) Technology Library and the situations of other libraries, this thesis integrates the reality of BRICEM and its library in an effort to work out a tentative plan, as well as concrete measures and procedures of digitalising and online-sharing the resources of BRICEM Technology Library. (author)

37 CFR 201.23 - Transfer of unpublished copyright deposits to the Library of Congress.

Science.gov (United States)

2010-07-01

... copyright deposits to the Library of Congress. 201.23 Section 201.23 Patents, Trademarks, and Copyrights COPYRIGHT OFFICE, LIBRARY OF CONGRESS COPYRIGHT OFFICE AND PROCEDURES GENERAL PROVISIONS § 201.23 Transfer of unpublished copyright deposits to the Library of Congress. (a) General. This section prescribes...

Library of Alexandria's New Web Site

Directory of Open Access Journals (Sweden)

2004-06-01

Full Text Available A review for the new version of Library of Alexandria web site which lunched on May 2004, the review deals with general introduction to the new version , then the main 6 section of the site , and show some features of the new site, and finally talk in concentration about the library catalog on the internet and its search capabilities.

gLibrary/DRI: A grid-based platform to host multiple repositories for digital content

International Nuclear Information System (INIS)

Calanducci, A.; Gonzalez Martin, J. M.; Ramos Pollan, R.; Rubio del Solar, M.; Tcaci, S.

2007-01-01

In this work we present the gLibrary/DRI (Digital Repositories Infrastructure) platform. gLibrary/DRI extends gLibrary, a system with a easy-to-use web front-end designed to save and organize multimedia assets on Grid-based storage resources. The main goal of the extended platform is to reduce the cost in terms of time and effort that a repository provider spends to get its repository deployed. This is achieved by providing a common infrastructure and a set of mechanisms (APIs and specifications) that the repository providers use to define the data model, the access to the content (by navigation trees and filters) and the storage model. DRI offers a generic way to provide all this functionality; nevertheless the providers can add specific behaviours to the default functions for their repositories. The architecture is Grid based (VO system, data federation and distribution, computing power, etc). A working example based on a mammograms repository is also presented. (Author)

Super Summer Safari Manual: 1989 Summer Library Program. Bulletin No. 9240.

Science.gov (United States)

Roeber, Jane A., Ed.

Based on the theme, "Super Summer Safari: Make Books Your Big Game," this manual describes library activities intended to stimulate family explorations of local and regional natural environments, of urban parks, and of agricultural settings. The manual is divided into 6 sections: (1) "Planning and Promoting Programs"; (2)…

Distance Learning Library Services in Ugandan Universities

Science.gov (United States)

Mayende, Jackline Estomihi Kiwelu; Obura, Constant Okello

2013-01-01

The study carried out at Makerere University and Uganda Martyrs University in 2010 aimed at providing strategies for enhanced distance learning library services in terms of convenience and adequacy. The study adopted a cross sectional descriptive survey design. The study revealed services provided in branch libraries in Ugandan universities were…

Teaching Electronic Literacy A Concepts-Based Approach for School Library Media Specialists

CERN Document Server

Craver, Kathleen W

1997-01-01

School library media specialists will find this concepts-based approach to teaching electronic literacy an indispensable basic tool for instructing students and teachers. It provides step-by-step instruction on how to find and evaluate needed information from electronic databases and the Internet, how to formulate successful electronic search strategies and retrieve relevant results, and how to interpret and critically analyze search results. The chapters contain a suggested lesson plan and sample assignments for the school library media specialist to use in teaching electronic literacy skills

Construction of naïve camelids VHH repertoire in phage display-based library.

Science.gov (United States)

Sabir, Jamal S M; Atef, Ahmed; El-Domyati, Fotouh M; Edris, Sherif; Hajrah, Nahid; Alzohairy, Ahmed M; Bahieldin, Ahmed

2014-04-01

Camelids have unique antibodies, namely HCAbs (VHH) or commercially named Nanobodies(®) (Nb) that are composed only of a heavy-chain homodimer. As libraries based on immunized camelids are time-consuming, costly and likely redundant for certain antigens, we describe the construction of a naïve camelid VHHs library from blood serum of non-immunized camelids with affinity in the subnanomolar range and suitable for standard immune applications. This approach is rapid and recovers VHH repertoire with the advantages of being more diverse, non-specific and devoid of subpopulations of specific antibodies, which allows the identification of binders for any potential antigen (or pathogen). RNAs from a number of camelids from Saudi Arabia were isolated and cDNAs of the diverse vhh gene were amplified; the resulting amplicons were cloned in the phage display pSEX81 vector. The size of the library was found to be within the required range (10(7)) suitable for subsequent applications in disease diagnosis and treatment. Two hundred clones were randomly selected and the inserted gene library was either estimated for redundancy or sequenced and aligned to the reference camelid vhh gene (acc. No. ADE99145). Results indicated complete non-specificity of this small library in which no single event of redundancy was detected. These results indicate the efficacy of following this approach in order to yield a large and diverse enough gene library to secure the presence of the required version encoding the required antibodies for any target antigen. This work is a first step towards the construction of phage display-based biosensors useful in disease (e.g., TB or tuberculosis) diagnosis and treatment. Copyright © 2014 Académie des sciences. Published by Elsevier SAS. All rights reserved.

Performance of the libraries in Isfahan University of Medical Sciences based on the EFQM model.

Science.gov (United States)

Karimi, Saeid; Atashpour, Bahareh; Papi, Ahmad; Nouri, Rasul; Hasanzade, Akbar

2014-01-01

Performance measurement is inevitable for university libraries. Hence, planning and establishing a constant and up-to-date measurement system is required for the libraries, especially the university libraries. The primary studies and analyses reveal that the EFQM Excellence Model has been efficient, and the administrative reform program has focused on the implementation of this model. Therefore, on the basis of these facts as well as the need for a measurement system, the researchers measured the performance of libraries in schools and hospitals supported by Isfahan University of Medical Sciences, using the EFQM Organizational Excellence Model. This descriptive research study was carried out by a cross-sectional survey method in 2011. This research study included librarians and library directors of Isfahan University of Medical Sciences (70 people). The validity of the instrument was measured by the specialists in the field of Management and Library Science. To measure the reliability of the questionnaire, the Cronbach's alpha coefficient value was measured (0.93). The t-test, ANOVA, and Spearman's rank correlation coefficient were used for measurements. The data were analyzed by SPSS. Data analysis revealed that the mean score of the performance measurement for the libraries under study and between nine dimensions the highest score was 65.3% for leadership dimension and the lowest scores were 55.1% for people and 55.1% for society results. In general, using the ninth EFQM model the average level of all dimensions, which is in good agreement with normal values, was assessed. However, compared to other results, the criterion people and society results were poor. It is Recommended by forming the expert committee on criterion people and society results by individuals concerned with the various conferences and training courses to improve the aspects.

Changing State Digital Libraries

Science.gov (United States)

Pappas, Marjorie L.

2006-01-01

Research has shown that state virtual or digital libraries are evolving into websites that are loaded with free resources, subscription databases, and instructional tools. In this article, the author explores these evolving libraries based on the following questions: (1) How user-friendly are the state digital libraries?; (2) How do state digital…

Adoption of Library 2.0 Functionalities by Academic Libraries and Users: A Knowledge Management Perspective

Science.gov (United States)

Kim, Yong-Mi; Abbas, June

2010-01-01

This study investigates the adoption of Library 2.0 functionalities by academic libraries and users through a knowledge management perspective. Based on randomly selected 230 academic library Web sites and 184 users, the authors found RSS and blogs are widely adopted by academic libraries while users widely utilized the bookmark function.…

The WIMS 69-group library tape 166259

International Nuclear Information System (INIS)

Taubman, C.J.

1975-07-01

This note describes the contents of the WIMS 69-group library, and includes a list of nuclides with details of data file or other source of data, resonance tabulations and thermal scattering models, and a list and details of resonance tabulations. Also included are condensation spectra used to obtain group cross-sections in fast energy range, group energy boundaries, and burn-up details, including fuel and fission product burn-up chains, fission product yields and energy release data. A fission spectrum for the 69-group library is given together with a lambda and sigma p values used in the calculation of resonance cross-sections, and 2200 m/sec absorption cross-sections and resonance absorption integrals. (U.K.)

Critical experiments analyses by using 70 energy group library based on ENDF/B-VI

Energy Technology Data Exchange (ETDEWEB)

Tahara, Yoshihisa; Matsumoto, Hideki [Mitsubishi Heavy Industries Ltd., Yokohama (Japan). Nuclear Energy Systems Engineering Center; Huria, H.C.; Ouisloumen, M.

1998-03-01

The newly developed 70-group library has been validated by comparing kinf from a continuous energy Monte-Carlo code MCNP and two dimensional spectrum calculation code PHOENIX-CP. The code employs Discrete Angular Flux Method based on Collision Probability. The library has been also validated against a large number of critical experiments and numerical benchmarks for assemblies with MOX and Gd fuels. (author)

Neutron Library (ENDL82) in the transmittal format

International Nuclear Information System (INIS)

Howerton, R.J.; Dye, R.E.; Perkins, S.T.

1982-01-01

There are four main libraries of data included within the system described. They are ENDL (Evaluated Neutron Data Library), ECPL (Evaluated Charged-Particle Data Library), ACTL (Evaluated Neutron-Induced Activation Cross-Section Library), and EGDL (Evaluated Photon Interaction Data Library). The first three deal with nuclear processes induced by neutrons or light charged particles (Z less than or equal to 2, A less than or equal to 4). The fourth (EGDL) contains the data appropriate to photons with energies between 100 eV and 100 MeV that interact with atoms of the elements in their ground state, i.e., cold targets. EGDL does not contain data for photonuclear reactions

Multi-Group Library Generation with Explicit Resonance Interference Using Continuous Energy Monte Carlo Calculation

Energy Technology Data Exchange (ETDEWEB)

Park, Ho Jin; Cho, Jin Young [KAERI, Daejeon (Korea, Republic of); Kim, Kang Seog [Oak Ridge National Laboratory, Oak Ridge (United States); Hong, Ser Gi [Kyung Hee University, Yongin (Korea, Republic of)

2016-05-15

In this study, multi-group cross section libraries for the DeCART code were generated using a new procedure. The new procedure includes generating the RI tables based on the MC calculations, correcting the effective fission product yield calculations, and considering most of the fission products as resonant nuclides. KAERI (Korea Atomic Energy Research Institute) has developed the transport lattice code KARMA (Kernel Analyzer by Ray-tracing Method for fuel Assembly) and DeCART (Deterministic Core Analysis based on Ray Tracing) for a multi-group neutron transport analysis of light water reactors (LWRs). These codes adopt the method of characteristics (MOC) to solve the multi-group transport equation and resonance fixed source problem, the subgroup and the direct iteration method with resonance integral tables for resonance treatment. With the development of the DeCART and KARMA code, KAERI has established its own library generation system for a multi-group transport calculation. In the KAERI library generation system, the multi-group average cross section and resonance integral (RI) table are generated and edited using PENDF (point-wise ENDF) and GENDF (group-wise ENDF) produced by the NJOY code. The new method does not need additional processing because the MC method can handle any geometry information and material composition. In this study, the new method is applied to the dominant resonance nuclide such as U{sup 235} and U{sup 238} and the conventional method is applied to the minor resonance nuclides. To examine the newly generated multi-group cross section libraries, various benchmark calculations such as pin-cell, FA, and core depletion problem are performed and the results are compared with the reference solutions. Overall, the results by the new method agree well with the reference solution. The new procedure based on the MC method were verified and provided the multi-group library that can be used in the SMR nuclear design analysis.

Effect of updated WIMSD libraries on neutron energy spectrum at irradiation site of Pakistan Research Reactor-1 using 3D modeling

International Nuclear Information System (INIS)

Ahmad, Siraj-ul-Islam; Ahmad, Nasir

2005-01-01

International Atomic Energy Agency (IAEA) has recently released new WIMSD libraries based on current cross-section evaluations. Using these libraries the effect of different evaluated data sets on effective multiplication factor and neutron energy spectrum was studied with the help of 3D reactor simulation code CITATION. Simulation methodology adopted in this work was validated by analyzing IAEA 10 MW benchmark reactor. The k eff values obtained using all newly released libraries are within 0.45% to the experimental value, while the old library released in 1981 resulted in calculated value 1.05% larger than experimental. The flux spectrum obtained for standard fuel element using 3D modeling is smaller in fast energy range and higher in thermal energy range than is calculated using the 1D model for the standard cell. In the flux trap, differences of about -4% to 13% were found in thermal flux using the newly released libraries as compared to that obtained using 1981 WIMSD library. The major differences in the flux spectra between newly available libraries and the 1981 WIMSD library in thermal energy range are due to the differences in cross-sections of hydrogen bound-in-water. The use of only newly available cross-sections of hydrogen bound-in-water with 1981 WIMSD library resulted in significant improvement in value of k eff as well as in the flux spectrum. Moreover the differences among new libraries in the thermal energy range are also due to these cross-sections. Difference in fission spectra from different libraries is responsible for differences of flux spectra in the fast energy range. These differences in flux are reduced significantly in the fast energy range by only replacement of fission spectra

Validation of tungsten cross sections in the neutron energy region up to 100 keV

Science.gov (United States)

Pigni, Marco T.; Žerovnik, Gašper; Leal, Luiz. C.; Trkov, Andrej

2017-09-01

Following a series of recent cross section evaluations on tungsten isotopes performed at Oak Ridge National Laboratory (ORNL), this paper presents the validation work carried out to test the performance of the evaluated cross sections based on lead-slowing-down (LSD) benchmarks conducted in Grenoble. ORNL completed the resonance parameter evaluation of four tungsten isotopes - 182,183,184,186W - in August 2014 and submitted it as an ENDF-compatible file to be part of the next release of the ENDF/B-VIII.0 nuclear data library. The evaluations were performed with support from the US Nuclear Criticality Safety Program in an effort to provide improved tungsten cross section and covariance data for criticality safety sensitivity analyses. The validation analysis based on the LSD benchmarks showed an improved agreement with the experimental response when the ORNL tungsten evaluations were included in the ENDF/B-VII.1 library. Comparison with the results obtained with the JEFF-3.2 nuclear data library are also discussed.

Development of automatic cross section compilation system for MCNP

International Nuclear Information System (INIS)

Maekawa, Fujio; Sakurai, Kiyoshi

1999-01-01

A development of a code system to automatically convert cross-sections for MCNP is in progress. The NJOY code is, in general, used to convert the data compiled in the ENDF format (Evaluated Nuclear Data Files by BNL) into the cross-section libraries required by various reactor physics codes. While the cross-section library: FSXLIB-J3R2 was already converted from the JENDL-3.2 version of Japanese Evaluated Nuclear Data Library for a continuous energy Monte Carlo code MCNP, the library keeps only the cross-sections at room temperature (300 K). According to the users requirements which want to have cross-sections at higher temperature, say 600 K or 900 K, a code system named 'autonj' is under development to provide a set of cross-section library of arbitrary temperature for the MCNP code. This system can accept any of data formats adopted JENDL that may not be treated by NJOY code. The input preparation that is repeatedly required at every nuclide on NJOY execution is greatly reduced by permitting the conversion process of as many nuclides as the user wants in one execution. A few MCNP runs were achieved for verification purpose by using two libraries FSXLIB-J3R2 and the output of autonj'. The almost identical MCNP results within the statistical errors show the 'autonj' output library is correct. In FY 1998, the system will be completed, and in FY 1999, the user's manual will be published. (K. Tsuchihashi)

Time-Driven Activity-Based Costing for Inter-Library Services: A Case Study in a University

Science.gov (United States)

Pernot, Eli; Roodhooft, Filip; Van den Abbeele, Alexandra

2007-01-01

Although the true costs of inter-library loans (ILL) are unknown, universities increasingly rely on them to provide better library services at lower costs. Through a case study, we show how to perform a time-driven activity-based costing analysis of ILL and provide evidence of the benefits of such an analysis.

A Generic High-performance GPU-based Library for PDE solvers

DEFF Research Database (Denmark)

Glimberg, Stefan Lemvig; Engsig-Karup, Allan Peter

, the privilege of high-performance parallel computing is now in principle accessible for many scientific users, no matter their economic resources. Though being highly effective units, GPUs and parallel architectures in general, pose challenges for software developers to utilize their efficiency. Sequential...... legacy codes are not always easily parallelized and the time spent on conversion might not pay o in the end. We present a highly generic C++ library for fast assembling of partial differential equation (PDE) solvers, aiming at utilizing the computational resources of GPUs. The library requires a minimum...... of GPU computing knowledge, while still oering the possibility to customize user-specic solvers at kernel level if desired. Spatial dierential operators are based on matrix free exible order nite dierence approximations. These matrix free operators minimize both memory consumption and main memory access...

Customer Satisfaction with Public Libraries.

Science.gov (United States)

D'Elia, George; Rodger, Eleanor Jo

1996-01-01

Surveys conducted in 142 urban public libraries examined customer satisfaction, comparisons with other libraries, and factors affecting satisfaction. Overall, customers were satisfied with their libraries but experienced different levels of satisfaction based on convenience, availability of materials and information, and services facilitating…

Library Design-Facilitated High-Throughput Sequencing of Synthetic Peptide Libraries.

Science.gov (United States)

Vinogradov, Alexander A; Gates, Zachary P; Zhang, Chi; Quartararo, Anthony J; Halloran, Kathryn H; Pentelute, Bradley L

2017-11-13

A methodology to achieve high-throughput de novo sequencing of synthetic peptide mixtures is reported. The approach leverages shotgun nanoliquid chromatography coupled with tandem mass spectrometry-based de novo sequencing of library mixtures (up to 2000 peptides) as well as automated data analysis protocols to filter away incorrect assignments, noise, and synthetic side-products. For increasing the confidence in the sequencing results, mass spectrometry-friendly library designs were developed that enabled unambiguous decoding of up to 600 peptide sequences per hour while maintaining greater than 85% sequence identification rates in most cases. The reliability of the reported decoding strategy was additionally confirmed by matching fragmentation spectra for select authentic peptides identified from library sequencing samples. The methods reported here are directly applicable to screening techniques that yield mixtures of active compounds, including particle sorting of one-bead one-compound libraries and affinity enrichment of synthetic library mixtures performed in solution.

Serving remote users in selected public university libraries in Kenya ...

African Journals Online (AJOL)

The provision of information services to support teaching, learning and research has long been a major objective of libraries in higher education. The students being served by these libraries, specifically in Kenya, may consist of on-campus and remote user groups. This study set out to explore the library section heads' ...

More than a physics library

CERN Multimedia

2009-01-01

Particle physicists world wide and the CERN staff are well aware of the services offered by the CERN Library. However, the services and collections are not limited to scientific and technical information needs. Many tools that are useful for everyone at CERN such as electronic dictionaries, encyclopedia and writing-style guides are also available from the library web site: http://library.cern.ch Further, as the Laboratory considers it an important task to develop good communication and managerial skills for the staff, it is only natural that literature related to these subjects can be found in the reading room in-between the many books on experimental techniques and accelerator physics. Thanks to very favorable variations in the currency exchange rates during 2008, unforeseen funds became available and the Library, in collaboration with the HR Learning & Development Section, was able to make an additional effort to develop the collection of management li...

Libraries of Middlesex, Final Performance Report for Library Services and Construction Act (LSCA) Title VI, Library Literacy Program.

Science.gov (United States)

Director, Elissa

This final performance report for the Libraries of Middlesex literacy project begins with a section that compares actual accomplishments to the following objectives for 1992-93: (1) recruit and enroll at least 150 new volunteers in Basic Reading of English as a Second Language (ESL) tutor training; (2) have at least 125 volunteers successfully…

The Research and Education of Evidence Based Library and Information Practice; A Narrative Review

Directory of Open Access Journals (Sweden)

Vahideh Zareh Gavgani

2018-01-01

Full Text Available Background and Objectives: Evidence based librarianship (EBL was defined as “use of best available evidence from qualitative and quantitative research results and rational experience and decisions acquired from the daily practice of library”. However there are controversies about if the nature of EBL deals with library services or professional practice and if it needs a formal education or informal continuing education is enough? To shed light on this ambiguity, the aim of this study was to find out the state-of-the-art of education of EBL in the world. Material and Methods: The study utilized library and documentation methods to investigate the academic education of EBL through review of the available literature and websites. Results: The findings of the study revealed that evidence based librarianship does have formal curriculum for academic education in post graduate levels (post master and master. It also revealed that “Evidence Based Approach” (EBA and “Evidence Based Medicine” (EBM were also similar courses that are offered in Master and PhD levels. Conclusion: Based on the history and revolution of EBA, it is time to develop formal curriculum and field of study for Evidence Based Information Practice. This study suggests establishment of the academic field of Evidence Based and Information Science to overcome the problems and limitations that library science faces in practice.

Organizational prerequisites for the preservation of library collections in monastery libraries

Directory of Open Access Journals (Sweden)

Maja Krtalić

2012-02-01

libraries. The conceptual approach to heritage preservation in monastery libraries used in this paper is based on the theoretical model of written heritage preservation management that comprises five aspects bringing together the theoretical, strategic, legal, financial, educational, operative, and cultural components. Monastery libraries are facing many problems in protection and preservation of collections. Most of their problems fall under the economic, legal, material and operative aspects of preservation. In addition to the most common limitations, such as financial constraints, inadequate premises for keeping and storing the collections, they often have staff shortages, especially of trained staff with particular knowledge and skills required to protect the collections of such libraries, which brings the educational aspect of preservation into the foreground. Even though the protection and preservation of library collections in monastery libraries is mostly the responsibility of monastery monks, their knowledge is mostly not expert enough and they cannot be the only ones made responsible for preservation. This issue needs to be considered from the strategic and theoretical aspects of written heritage preservation management. One of the major hurdles is the inadequacy of legislation and its lack of recognition of those collections as national heritage. One of the factors that needs to be taken into consideration are changes that occur in the cultural and social contexts, i.e. changes in relations between church orders and communities in which they are active. Based on the data collected and relying on the conceptual model of written heritage preservation management in the Republic of Croatia, the current state of monastery library collections preservation has been established and measures for a systematic and more efficient management of written heritage preservation in monastery libraries have been proposed.

Influence of the ab initio n–d cross sections in the critical heavy-water benchmarks

International Nuclear Information System (INIS)

Morillon, B.; Lazauskas, R.; Carbonell, J.

2013-01-01

Highlights: ► We solve the three nucleon problem using different NN potential (MT, AV18 and INOY) to calculate the Neutron–deuteron cross sections. ► These cross sections are compared to the existing experimental data and to international libraries. ► We describe the different sets of heavy water benchmarks for which the Monte Carlo simulations have been performed including our new Neutron–deuteron cross sections. ► The results obtained by the ab initio INOY potential have been compared with the calculations based on the international library cross sections and are found to be of the same quality. - Abstract: The n–d elastic and breakup cross sections are computed by solving the three-body Faddeev equations for realistic and semi-realistic nucleon–nucleon potentials. These cross sections are inserted in the Monte Carlo simulation of the nuclear processes considered in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook). The results obtained using thes ab initio n–d cross sections are compared with those provided by the most renown international libraries

CORALINA: a universal method for the generation of gRNA libraries for CRISPR-based screening.

Science.gov (United States)

Köferle, Anna; Worf, Karolina; Breunig, Christopher; Baumann, Valentin; Herrero, Javier; Wiesbeck, Maximilian; Hutter, Lukas H; Götz, Magdalena; Fuchs, Christiane; Beck, Stephan; Stricker, Stefan H

2016-11-14

The bacterial CRISPR system is fast becoming the most popular genetic and epigenetic engineering tool due to its universal applicability and adaptability. The desire to deploy CRISPR-based methods in a large variety of species and contexts has created an urgent need for the development of easy, time- and cost-effective methods enabling large-scale screening approaches. Here we describe CORALINA (comprehensive gRNA library generation through controlled nuclease activity), a method for the generation of comprehensive gRNA libraries for CRISPR-based screens. CORALINA gRNA libraries can be derived from any source of DNA without the need of complex oligonucleotide synthesis. We show the utility of CORALINA for human and mouse genomic DNA, its reproducibility in covering the most relevant genomic features including regulatory, coding and non-coding sequences and confirm the functionality of CORALINA generated gRNAs. The simplicity and cost-effectiveness make CORALINA suitable for any experimental system. The unprecedented sequence complexities obtainable with CORALINA libraries are a necessary pre-requisite for less biased large scale genomic and epigenomic screens.

Criticality studies of fast assemblies with the new 27-group cross-section set

International Nuclear Information System (INIS)

Garg, S.B.; Shukla, V.K.

1976-01-01

A test of 27-group cross-section set (Garg-set) recently derived from ENDF/B library has been carried out in the criticality studies of the Pu 239 , U 235 and U 233 based metal, oxide and carbide fuelled fast critical assemblies. A total of twenty fast critical assemblies of different sizes and varying neutron spectra have been selected for analysis. Based on these analyses it has been observed that the Garg-set predicts well the criticality of uranium and plutonium based hard-spectra assemblies. In the soft-spectra systems it underpredicts criticality because of the following reasons: (a) It makes use of the higher capture cross-sections of structural and coolant elements given in ENDF/B - Version IV library. (b) It does not account for the resonance self-shielding effects of cross-sections. It has also been observed that the Garg-set gives better results than the MABBN-set for dense and dilute plutonium-based and the hard uranium-based assemblies. This superior trend of the Garg-set is slightly lost in the uranium-based dilute systems because of large differences in the capture cross-sections of structural elements of these two sets. (author)

phpMs: A PHP-Based Mass Spectrometry Utilities Library.

Science.gov (United States)

Collins, Andrew; Jones, Andrew R

2018-03-02

The recent establishment of cloud computing, high-throughput networking, and more versatile web standards and browsers has led to a renewed interest in web-based applications. While traditionally big data has been the domain of optimized desktop and server applications, it is now possible to store vast amounts of data and perform the necessary calculations offsite in cloud storage and computing providers, with the results visualized in a high-quality cross-platform interface via a web browser. There are number of emerging platforms for cloud-based mass spectrometry data analysis; however, there is limited pre-existing code accessible to web developers, especially for those that are constrained to a shared hosting environment where Java and C applications are often forbidden from use by the hosting provider. To remedy this, we provide an open-source mass spectrometry library for one of the most commonly used web development languages, PHP. Our new library, phpMs, provides objects for storing and manipulating spectra and identification data as well as utilities for file reading, file writing, calculations, peptide fragmentation, and protein digestion as well as a software interface for controlling search engines. We provide a working demonstration of some of the capabilities at http://pgb.liv.ac.uk/phpMs .

VALGALI: VERIFICATION AND VALIDATION TOOL FOR THE LIBRARIES PRODUCED BY THE GALILEE SYSTEM

International Nuclear Information System (INIS)

Mengelle, S.

2011-01-01

Full text: In this paper we present VALGALI the verification and validation tool for the libraries produced by the nuclear data processing system GALILEE. The aim of this system is to provide libraries with consistent physical data for various application codes (the deterministic transport code APOLLO2, the Monte Carlo transport code TRRIPOLI-4, the depletion code DARWIN, ...). For each library, are the data stored at the good place with the good format and so one. Are the libraries used by the various codes consistent. What is the physical quality of the cross sections and data present in the libraries. These three types of tests correspond to the classic stages of VandV. The great strength of VALGALI is to be generic and not dedicated to one application code Consequently, it is based on a common physical validation database which coverage is regularly increased. For all these test cases, the input data are declined for each relevant application code Moreover it can exist specific test case for each application code: At the present, VALGALI an check and validate the libraries of APOLLO2 and TRIPOLI4, but in the near future VALGALI wil also treat the libraries of DARWIN.

Improving e-book access via a library-developed full-text search tool.

Science.gov (United States)

Foust, Jill E; Bergen, Phillip; Maxeiner, Gretchen L; Pawlowski, Peter N

2007-01-01

This paper reports on the development of a tool for searching the contents of licensed full-text electronic book (e-book) collections. The Health Sciences Library System (HSLS) provides services to the University of Pittsburgh's medical programs and large academic health system. The HSLS has developed an innovative tool for federated searching of its e-book collections. Built using the XML-based Vivísimo development environment, the tool enables a user to perform a full-text search of over 2,500 titles from the library's seven most highly used e-book collections. From a single "Google-style" query, results are returned as an integrated set of links pointing directly to relevant sections of the full text. Results are also grouped into categories that enable more precise retrieval without reformulation of the search. A heuristic evaluation demonstrated the usability of the tool and a web server log analysis indicated an acceptable level of usage. Based on its success, there are plans to increase the number of online book collections searched. This library's first foray into federated searching has produced an effective tool for searching across large collections of full-text e-books and has provided a good foundation for the development of other library-based federated searching products.

The Electronic Library of the Thermal Physical Databases

International Nuclear Information System (INIS)

Zhuravleva, Y.; Mingaleeva, G.; Mokrousov, K.; Yashnikov, D.

2008-01-01

base library collect experimental data-base not only for verification of one-dimensional thermal hydraulic system codes with average flow parameters but also include data useful for the subchannel thermal hydraulic analyses in rod bundles We update the library regularly. Now the library contains the following bases: critical heat flux databank (10000 experimental points, 136 test sections, 57 sourses); post-crisis heat transfer; void fraction in vertical pipes and rod bundles; critical flow from pipes, valves and flow limiters; heat transfer to supercritical water; local thermal hydraulic parameters in fuel rod assemblies; transient processes on test sites and nuclear power plants. MS Access was used for the creation of the library. The experiment description and results are saved in MS Word and Excel formats correspondently. The basic principles of the library are: the regular updating of the library; the searching and choosing data by user's specify parameters; the simple data processing; the information in each databank must be efficient both for traditional analyses methods and new approaches.(author)

EPDL97: the evaluated photon data library, '97 version. Summary documentation

International Nuclear Information System (INIS)

Pronyaev, V.G.; McLaughlin, P.

1998-01-01

The Evaluated Photon Data Library, 1997 version (EPDL97), is designed for use in photon transport calculations at Lawrence Livermore National Laboratory. This library includes photon interaction data for all elements with atomic number between Z = 1 (hydrogen) and 100 (fermium), including: photoionization, photoexcitation, coherent and incoherent scattering, and pair and triplet production cross sections. For use in applications data is provided for all elements over the energy range 1 eV to 100 GeV. EPDL97 completely supersedes the earlier 1989 version of EPDL(89) (see IAEA-NDS-158, Summary documentation to the EPDL) and it is highly recommended that users only use the most recent version of this library. The Evaluated Atomic Data Library (EADL), Evaluated Electron Data Library (EEDL) an Evaluated Excitation Data Library (EXDL) are included to allow consistent coupled photon-electron transport calculations. The data package is available from the IAEA Nuclear Data Section on CD-ROM (12 files, 74.2 MB). (author)

Generation of the library of neutron cross sections for the Record code of the Fuel Management System (FMS); Generacion de la biblioteca de secciones eficaces de neutrones para el codigo Record del Sistema de Administracion de Combustible (FMS)

Energy Technology Data Exchange (ETDEWEB)

Alonso V, G; Hernandez L, H [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1991-11-15

On the basis of the library structure of the RECORD code a method to generate the neutron cross sections by means of the ENDF-B/IV database and the NJOY code has been developed. The obtained cross sections are compared with those of the current library which was processed using the ENDF-B/III version. (Author)

BROND-2. USSR Evaluated Neutron Data Library

International Nuclear Information System (INIS)

Manokhin, V.N.

1992-01-01

BROND-2, the USSR computerized data library for evaluated neutron reaction data was released in 1992. Upon request it is available on magnetic tape, costfree, from the IAEA Nuclear Data Section. The Library BROND-2 reported in this document supersedes the earlier versions ''BROND-NDS1'' plus three supplements ''BROND-NDS2'', ''BROND-NDS3'', ''BROND-NDS4''. 16 refs

Analysis of PROTEUS phase II experiments performed using the AARE modular system and JEF-based libraries

International Nuclear Information System (INIS)

Pelloni, S.; Stepanek, J.; Vontobel, P.

1989-01-01

The capability of the advanced analysis of reactor engineering (AARE) modular code system and JEF-1-based nuclear data libraries to analyze light water high converter reactor (LWHCR) lattices is investigated by calculating the wet and dry cells of the PROTEUS-LWHCR phase II experiment. The results are compared to those obtained using several cell codes. Main features of the AARE code system, such as the self-shielding of resonance cross sections in the whole energy range, the generation of adequate fission source spectra, and the efficiency of the elastic removal correction,are investigated. In particular, it is shown that AARE results for the k ∞ void coefficient agree very well with the experiment, whereas other codes give larger deviations

FilTer BaSe: A web accessible chemical database for small compound libraries.

Science.gov (United States)

Kolte, Baban S; Londhe, Sanjay R; Solanki, Bhushan R; Gacche, Rajesh N; Meshram, Rohan J

2018-03-01

Finding novel chemical agents for targeting disease associated drug targets often requires screening of large number of new chemical libraries. In silico methods are generally implemented at initial stages for virtual screening. Filtering of such compound libraries on physicochemical and substructure ground is done to ensure elimination of compounds with undesired chemical properties. Filtering procedure, is redundant, time consuming and requires efficient bioinformatics/computer manpower along with high end software involving huge capital investment that forms a major obstacle in drug discovery projects in academic setup. We present an open source resource, FilTer BaSe- a chemoinformatics platform (http://bioinfo.net.in/filterbase/) that host fully filtered, ready to use compound libraries with workable size. The resource also hosts a database that enables efficient searching the chemical space of around 348,000 compounds on the basis of physicochemical and substructure properties. Ready to use compound libraries and database presented here is expected to aid a helping hand for new drug developers and medicinal chemists. Copyright © 2017 Elsevier Inc. All rights reserved.

Challenges and Opportunities for Libraries in Pakistan

OpenAIRE

Shafiq UR, Rehman; Pervaiz, Ahmad

2007-01-01

Abstract: This paper, based on review of literature, observation, and informal conversations, discusses various challenges regarding finance, collection development, ICTs, human resources, library education, library association and research & development faced by library profession in Pakistan. The opportunities to meet these challenges have also been explored. Keywords: Library challenges and opportunities (Pakistan); Librarianship (Pakistan); Library issues; Library profession in Pa...

36 CFR 1280.66 - May I use the National Archives Library?

Science.gov (United States)

2010-07-01

... Archives Library? 1280.66 Section 1280.66 Parks, Forests, and Public Property NATIONAL ARCHIVES AND RECORDS... the Washington, DC, Area? § 1280.66 May I use the National Archives Library? The National Archives Library facilities in the National Archives Building and in the National Archives at College Park are...

Library and Information Science Journal Prestige as Assessed by Library and Information Science Faculty

Science.gov (United States)

Manzari, Laura

2013-01-01

This prestige study surveyed full-time faculty of American Library Association (ALA)-accredited programs in library and information studies regarding library and information science (LIS) journals. Faculty were asked to rate a list of eighty-nine LIS journals on a scale from 1 to 5 based on each journal's importance to their research and teaching.…

About the Library - Betty Petersen Memorial Library

Science.gov (United States)

branch library of the NOAA Central Library. The library serves the NOAA Science Center in Camp Springs , Maryland. History and Mission: Betty Petersen Memorial Library began as a reading room in the NOAA Science Science Center staff and advises the library on all aspects of the library program. Library Newsletters

The academic library network

Directory of Open Access Journals (Sweden)

Jacek Wojciechowski

2012-01-01

Full Text Available The efficiency of libraries, academic libraries in particular, necessitates organizational changes facilitating or even imposing co-operation. Any structure of any university has to have an integrated network of libraries, with an appropriate division of work, and one that is consolidated as much as it is possible into medium-size or large libraries. Within thus created network, a chance arises to centralize the main library processes based on appropriate procedures in the main library, highly specialized, more effective and therefore cheaper in operation, including a co-ordination of all more important endeavours and tasks. Hierarchically subordinated libraries can be thus more focused on performing their routine service, more and more frequently providing for the whole of the university, and being able to adjust to changeable requirements and demands of patrons and of new tasks resulting from the new model of the university operation. Another necessary change seems to be a universal implementation of an ov rall programme framework that would include all services in the university’s library networks.

PROLIB: code to create production library of nuclear data for design calculations

International Nuclear Information System (INIS)

Wittkopf, W.A.; Tilford, J.M.; Furtney, M.

1977-02-01

The PROLIB program creates, updates, and edits the production library used in the B and W nuclear design system. The production library contains the material cross section data required to perform the thermal and epithermal spectrum calculations in the NULIF program. PROLIB collapses cross section data from the master libraries, produced by the ETOGM and THOR programs, to the desired production library group structures. The physics models that are used, the calculations that are performed in PROLIB, the input, and the output are described. Information that is required to use PROLIB along with a sample problem that illustrates the input and output formats and that provides a benchmark problem are given

ZZ MCNPDATA, Standard Neutron, Photon and Electron Data Libraries for MCNP-4C and MCB1C

International Nuclear Information System (INIS)

2002-01-01

1 - Description: These cross-section libraries are released by the Diagnostics Applications Group, X-5, at Los Alamos National Laboratory for use with the MCNP Monte Carlo code package. This release includes all of the X-5 distributed neutron data libraries, the photon libraries MCPLIB1 and MCPLIB02, the electron libraries EL1 and EL03, an updated XSDIR file, and information files Readme.txt and Readme e ndf60.txt. This release is intended to completely replace previous RSICC releases DLC-105, DLC-181, and DLC-189 as well as the cross sections previously included with CCC-200/MCNP4A, and will be updated as new libraries become available. The README file provides information regarding each data library of this release. Additional documentation for some of the individual libraries and example SPECS files for use with MAKXSF are also provided. The XSDIR file is specific to this release and may not work with previous packages. Currently the neutron data library ENDF60 (based on ENDF/B-VI, up through and including release 2) is the default library for continuous-energy neutron transport. Additionally, the libraries MCPLIB02 and EL03 are the default libraries for photon and electron transport respectively. More information on the data libraries contained in this release is available in Appendix G of the MCNP4C manual. 2 - Description of program or function: ZZ-MCB-DLC200 contains the same cross section tables as the DLC-0200/03 package for the MCNP-4C code, except that the installation procedures are adapted to the MCB1C code system (NEA 1643/01). 3 - Application of the data: DLC-200/MCNPDATA is for use with Version 4C and later of the MCNP transport code. This data library provides a comprehensive set of cross sections for a wide range of radiation transport applications using the Monte Carlo code package CCC-700/MCNP4C. See Appendix G of the MCNP report LA-13709-M for information on the libraries and how to select specific nuclides for use in MCNP. 4 - Source and scope

Library science talks

CERN Document Server

Le Meur, Jean-Yves; Vigen, Jens; CERN. Geneva

1997-01-01

The new interface to the CERN library data base by Jean-Yves Le Meur / CERN-AS I will give a short (hands on) demonstration of the new interface to the whole library database. Emphasis will be given to the new feature allowing any user to build his personal virtual library. A user oriented interface to physics preprint servers by Carlos Loureno / CERN-PPE I will give a (hands-on) presentation of a first version of a tailor made WEB based interface to the preprints kept in the CERN or Los Alamos servers. This interface has already been successfully implemented for the field of high energy heavy ion physics, and can easily be expanded or adapted to other research fields of interest to the HEP community. For the already published papers, a direct link to the published e-journal version is provided (if available). Status of the digital library at CERN by Jens Vigen / CERN-AS I will review the present situation concerning the availability of the electronic versions of scientific publications at CERN and the el...

The library was used as Copernicus in Auersperg’s and Lyceal Libraries

Directory of Open Access Journals (Sweden)

Stanislav Južnič

2006-01-01

Full Text Available We described the beginnings of the Auersperg Prince’s Library of Ljubljana. The special concern was put on the most important bibliophile among the Auerpergs, Volk Engelbert. The work of his friend and librarian, Schönleben, was put in the limelight. We researched the catalogue of Auersperg’s mathematical books, including astronomy and discussed the importance and value of particular items. The library was used as the base for the analysis of Auersperg’s scientific interests just after they returned to the Catholic faith. We also examined their opinion about Copernicus. The contemporary destiny of the Auersperg Prince’s Library was mentioned. In this very moment just some books of the former Ljubljanian library could be traced in different foreign libraries, especially in USA. We discovered the second edition of Copernicus’ De Revolutionibus which National and University Library of Ljubljana inherited from the Ljubljanian Jesuit library. Because of the wrong year written in Cobiss record, this precious treasure was unknown to the researchers up to now.

Featured Library: Parrish Library

OpenAIRE

Kirkwood, Hal P, Jr

2015-01-01

The Roland G. Parrish Library of Management & Economics is located within the Krannert School of Management at Purdue University. Between 2005 - 2007 work was completed on a white paper that focused on a student-centered vision for the Management & Economics Library. The next step was a massive collection reduction and a re-envisioning of both the services and space of the library. Thus began a 3 phase renovation from a 2 floor standard, collection-focused library into a single floor, 18,000s...

Academic Job Placements in Library and Information Science Field: A Case Study Performed on ALISE Web-Based Postings

Science.gov (United States)

Abouserie, Hossam Eldin Mohamed Refaat

2010-01-01

The study investigated and analyzed the state of academic web-based job announcements in Library and Information Science Field. The purpose of study was to get in depth understanding about main characteristics and trends of academic job market in Library and Information science field. The study focused on web-based version announcement as it was…

FENDL/MC. Library of continuous energy cross sections in ACE format for neutron-photon transport calculations with the Monte Carlo N-particle Transport Code system MCNP 4A. Version 1.1 of March 1995. Summary documentation

International Nuclear Information System (INIS)

Pashchenko, A.B.; Wienke, H.; Ganesan, S.

1996-01-01

Selected neutron reaction nuclear data evaluations for elements of interest to the IAEA's program on Fusion Evaluated Nuclear Data Library (FENDL) have been processed into ACE format using the NJOY system by R.E. MacFarlane. This document summarizes the resulting continuous energy cross-section data library FENDL/MC version 1.1. The data are available cost free, upon request from the IAEA Nuclear Data Section, online or on magnetic tape. (author). 1 tab

Strategic marketing planning in library

Directory of Open Access Journals (Sweden)

Karmen Štular-Sotošek

2000-01-01

Full Text Available The article is based on the idea that every library can design instruments for creating events and managing the important resources of today's world, especially to manage the changes. This process can only be successful if libraries use adequate marketing methods. Strategic marketing planning starts with the analysis of library's mission, its objectives, goals and corporate culture. By analysing the public environment, the competitive environment and the macro environment, libraries recognise their opportunities and threats. These analyses are the foundations for library definitions: What does the library represent?, What does it aspire to? Which goals does it want to reach? What kind of marketing strategy will it use for its target market?