Download or read book Data Testing of ENDF written by and published by . This book was released on 1994 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Benchmarks and Integral Data Testing and Feedback Into ENDF written by and published by . This book was released on 1992 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The role of integral data testing and its feedback into the ENDF/B evaluated nuclear data files are reviewed. The use of the CSEWG reactor benchmarks in the data testing process is discussed and selected results based on ENDF/B Version VI data are presented. Finally, recommendations are given to improve the implementation in future integral data testing of ENDF/B.

Download or read book Integral Data Testing of ENDF written by R. J. LaBauve and published by . This book was released on 1981 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Data Testing for ENDF written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Calculations have been performed for 390 critical assemblies from the International Handbook of Evaluated Criticality Safety Benchmark Experiments using the beta2 release of ENDF/B-VII. 1. The results are compared to previous results for ENDF/B-VII. Cases that changed between the two versions are highlighted, and the results are discussed. The Cross Section Evaluation Working Group (CSEWG) is working on a new release of the ENDF/B-VII library of evaluated nuclear data, and the 'beta2' set of files was recently made available by the National Nuclear Data Center (NNDC). A set of about 850 input files for the MCNP Monte Carlo code to run critical assemblies from the International Handbook of Evaluated Criticality Safety Benchmark Experiments was available from our previous data testing work for ENDF/B-VII.0. We have now run 390 of those cases using data based on the beta2 files, and those results will be presented below. The ENDF files were downloaded from the NNDC to a Mac workstation. They were then processed using NJOY10 into ACE format files for use in the MCNP Monte Carlo code. The processing was limited to materials needed for the data testing work at this point. The existing MCNP input decks were used. No checking was done to see if any of the benchmarks had been updated since the ENDF/B-VII testing was finished. Most runs used 50 million histories in order to get Monte Carlo statistical uncertainties down the 0.01% range.

Download or read book Thermal Data Testing of ENDF B III and Prognosis for ENDF B IV written by and published by . This book was released on 1974 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Data Testing Results for the LLL Evaluated Nuclear Data Library ENDL 78 written by Robert J. Howerton and published by . This book was released on 1979 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ENDF B IV Thermal Data Testing written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Evaluated Nuclear Data File/Library B (ENDF/B) provides a computer-oriented reference set of evaluated neutron cross sections for thermal and fast reactor applications, photon interaction cross sections, and photon production data. The current evaluations span the energy range from 0 to 20 MeV. This paper presents ENDF/B-IV data testing results from seven organizations on seventeen thermal benchmark experiments. Development and testing of ENDF/B-IV is the latest contribution of the Cross Section Evaluation Group. The file is maintained at, and released through, the National Neutron Cross Section Center at Brookhaven National Laboratory. The ENDF/B-IV predictions for uranium systems are an improvement over ENDF/B-III. Recommendations include extending the benchmark experiments to plutonium, urania, thoria, and mixed oxide systems and preparing a revised library, ENDF/B-V.

Download or read book Initial Data Testing of ENDF written by and published by . This book was released on 1991 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper summarizes some early data testing of ENDF/B-VI by members of the Cross Section Evaluation Working Group (CSEWG) Thermal Reactor Data Testing Subcommittee. Projections of ENDF/B-VI performance in thermal benchmark calculations are beginning to be available; and in some cases the calculations were performed with only a portion of the cross sections taken from version VI, the remainder taken from earlier data files. A factor delaying the thermal reactor data testing is that the final 235U evaluation has not yet been officially released--only an earlier evaluation with a constant low-energy eta value (like in version V) is currently available. The official version VI 235U evaluation (scheduled for release as Mod-1) gives a drooping eta variation at low energy; i.e., eta decreases with decreasing energy. This behavior was suggested by European studies to improve the calculation of temperature coefficients in LWRs.

Download or read book Data Testing of ENDF B V 2 Nuclear Data for Fast Reactor Calculations written by Carol A. Atkinson and published by . This book was released on 1987 with total page 394 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Data Evaluation Methodology Proceedings Of The International Symposium written by C L Dunford and published by World Scientific. This book was released on 1993-08-12 with total page 756 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Symposium on Nuclear Data Evaluation Methodology provided a forum for the discussion of developments made over the past 12 years in the evaluation methods used for generating data files for applied technology. With a program that was prepared by an international committee of experts in this field, this set of proceedings gives a comprehensive overview of the development and progress of this field for the last 12 years. It serves as an important source of reference and historical update for those seeking an in-depth understanding of this study.

Download or read book Status of Data Testing of ENDF written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The ENDF/B-V Reactor Dosimetry File was released August 1979, and Phase II data testing started. The results presented here are from Brookhaven National Laboratory only, and are considered preliminary. The tests include calculated spectrum-averaged cross sections using 235U fission spectrum (Watt), 252Cf spontaneous fission spectrum (Watt and Maxwellian), and the Coupled Fast Reactor Measurement Facility (CFRMF) spectrum. 6 tables.

Download or read book Testing of the ENDF B V nuclear data library in thermal benchmark experiments final report written by E. Schmidt and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Data Testing Results for the ENDF B V Evaluated Neutron Data File written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Integral Data Testing of ENDF B Fission product Data and Comparisons of ENDF B with Other Fission Product Data Files written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Three experiments (one from Oak Ridge and two from Los Alamos), in which samples of 235U and 238Pu were irradiated with thermal neutrons and either the total, gamma-ray, or gamma- and beta-ray fission product decay-energies were measured as functions of cooling time, were selected for comparisons with calculations made using four different fission product data files. The data files used were (1) the ENDF/B-IV fission product file, (2) the ENDF/B-V fission product file, (3) a file derived by substituting decay energies from JNDC into the ENDF/B-V file, and (4) a file derived by substituting decay-energies and spectra from the UK data file into the ENDF/B-V file. Direct summation calculations and spectral comparisons of the experiments were made using these data files as input, and both types of calculational analyses yielded the same results; namely, all data files are deficient, but the JNDC-ENDF/B-V results for the gamma- and beta-ray total decay-energy agree best with experiments. In addition, spectral comparisons with experiment generally indicate that calculated gamma-ray decay-energies are relatively high for early cooling times and small gamma-ray energies; they are low for early cooling times and large gamma-ray energies. The opposite is somewhat the case for the beta-ray decay energies; that is, the calculations are generally low for small beta-ray energies and high for large energies.

Download or read book ENDF B VII Data Testing with Icsbep Benchmarks written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ENDF B VII 0 Data Testing Using 1 172 Critical Assemblies written by and published by . This book was released on 2007 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: In order to test the ENDF/B-VII.0 neutron data library [1], 1,172 critical assemblies from [2] have been calculated using the Monte Carlo transport code TART [3]. TART's 'best' physics was used for all of these calculations; this included continuous energy cross sections, delayed neutrons in their spectrum that is slower than prompt neutrons, unresolved resonance region self-shielding, the thermal scattering (free atom for all materials plus thermal scattering law data S([alpha], [beta]) when available). In this first pass through the assemblies the objective was to 'quickly' test the validity of the ENDF/B-VII.0 data [1], the assembly models as defined in [2] and coded for use with TART, and TART's physics treatment [3] of these assemblies. With TART we have the option of running criticality problems until K-eff has been calculated to an acceptable input accuracy. In order to 'quickly' calculate all of these assemblies K-eff was calculated in each case to +/- 0.002. For these calculations the assemblies were divided into ten types based on fuel (mixed, Pu239, U233, U235) and median fission energy (Fast, Midi, Slow). A table is provided that shows a summary of these results. This is followed be details for every assembly, and statistical information about the distribution of K-eff for each type of assembly. After a review of these results to eliminate any obvious errors in ENDF/B data, assembly models, or TART physics, all assemblies will be run again to a higher precision. Only after this second run is finished will we have highly precise results. Until then the results presently here should only be interpreted as approximate values of K-eff with a standard deviation of +/- 0.002; for such a large number of assemblies we expected the results to be approximately normal, with a spread out to several times the standard deviation; see the calculated statistical distributions and their comparisons to a normal distribution.

Download or read book Data Testing Results for the ENDF written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The ENDF/B-V Evaluated Neutron Data File has been tested for validity by comparing calculated and experimental values of k/sub eff/ for 66 critical assemblies and emission neutron spectra for 20 spheres that were pulsed with 14-MeV neutrons. 20 figures, 7 tables.