Evaluated Nuclear Data Files ENDF

Several of the reactor physics parameters are both measurable and calculable from more fundamental properties such as the energy-dependent neutron cross sections and atom number densities. An extensive database. Evaluated Nuclear Data Files (ENDF), has been maintained over several decades. There is an interplay between theory and experiment to guide design of a reactor, as in other engineering systems. 

Evaluated Nuclear Data Files (ENDF) database, 17 566... 

Calculations of core cell bum-up in the N2 PWR were performed by the spectral code CETERA [16]. The fission product and actinide activities were estimated using the RECOL [17] library data base, which was generated on the bases of the latest versions of the evaluated nuclear data files, ENDF/B-V, with corrections based on the results of critical experiments [18]. The criticality problem was solved for a realistic 3-D geometry model of a TFC by Monte-Carlo with RECOL and checked with MCNP [19] for fresh fuel load. One-group cross-sections were prepared for bum-up calculation of critical loads of both fresh and spent fuel and input to ORIGEN-2 [20] for detailed radionuclide content calculations. 

A new coupled neutron-gamma multigroup library for 26 nuclides has been generated, based on Evaluated Nuclear Data File ENDF/B-IV for shielding calculations and validated. Activation cross sections for a number of materials used as activation foils for neutron flux and spectrum measurements have been prepared. 

Analysis of Critical Experiments Using Version II of the Evaluated Nuclear Data File (ENDF/B), W. W. Little, R. B. Kidman, R. E. Schenter, L. D. O Dell, R. W. Hardie, K. B. Stewart (PNL)... 

The second version (first revision) of the Evaluated Nuclear Data File (ENDF/B) has recently been released from the National Cross Section. Center for testing and evaluation. Version n differs from Version I in two respects it incorporates more recent microscopic data, and it offers a more flexible and realistic data format. Indeed, the extensive format changes, which In turn have necessitated extensive modifications in the jprocesslng codes, have delayed Version n processing and evaluation. This paper describes what is thought to be the first analysis of critical experiments using Version n. 

D. GARBER, C. DUNFORD, and S. PEARLSTEIN, Data Formats arid Procedures for the Evaluated Nuclear Data File, ENDF, BNL-NCS-50496. Brookhaven National Lab. (1975). 

The continuous energy cross sections are obtained from the Evaluated Nuclear Data Files (ENDF/B), which include smooth cross sections up to at least 20 MeV, secondary scattered neutron energy and directional distributions, thermal scattering kernel properties, and resonance parameters. 

Rose, P.F and Dunford, C.L. (Eds) ENDF 102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6 - BNL-NCS-44945 (1990). 

Figures 4.27 and 4.28 show the total cross section for two isotopes over the same neutron energy range. Notice the vast difference between the two o- s, both in terms of their variation with energy and their value in bams. [All available information about cross sections as a function of energy for all isotopes is contained in the Evaluated Nuclear Data Files (known as ENDF) stored at the Brookhaven National Laboratory, Upton, NY.]...

England, T. R. and Rider, B. F. 1994. Evaluation and compilation of fission product yields 1993. Los Alamos National Laboratory Report LA-UR-94-3106. ENDF (Evaluated Nuclear Data File) 349. Viewed on January, 2006. 

H. C. Honeck, ENDF Evaluated Nuclear Data File Description and Specifications, BNL 8381. Brookhaven Nat. Lab., Upton, New York, 1964. 

The Evaluated Nuclear Data File/Versioh B (ENOF/E) provides a computer-oriented reference set of evaluated neutron cross sections for thermal and st rmmtor applications. New versions of ENDF/B have been released at about a frequency of one every two years to improve its applicability, and its scope has been enlarged to. include shielding and dosimetry applications. The latest version, released in 1974 imd denoted ENDF/B-IV, provides reevaluations of the cross sections to... 

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