R-matrix Analyses of the 235U and 239Pu Neutron Cross Sections

R-matrix Analyses of the 235U and 239Pu Neutron Cross Sections

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Published: 1988

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The resonance parameter analysis code SAMMY was used to perform consistent resonance analyses of several 235U and 239Pu fission and capture cross section and transmission measurements up to 110 eV for 235U and up to 1 keV for 239Pu. The method of analysis, the measurement selection and the results are briefly outlined in this paper.


R-matrix Analysis of the 239Pu Neutron Cross Sections

R-matrix Analysis of the 239Pu Neutron Cross Sections

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Published: 1985

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239Pu neutron cross-section data in the resolved resonance region were analyzed with the R-Matrix Bayesian Program SAMMY. Below 30 eV the cross sections computed with the multilevel parameters are consistent with recent fission and transmission measurements as well as with older capture and alpha measurements. Above 30 eV no suitable transmission data were available and only fission cross-section measurements were analyzed. However, since the analysis conserves the complete covariance matrix, the analysis can be updated by the Bayes method as transmission measurements become available. To date, the analysis of the fission measurements has been completed up to 300 eV. 14 refs.


R-matrix Analysis of the 235U Neutron Cross Sections

R-matrix Analysis of the 235U Neutron Cross Sections

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Published: 1988

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The ENDFB-V representation of the 235U neutron cross sections in the resolved resonance region is unsatisfactory: below 1 eV the cross sections are given by ''smooth files'' (file 3) rather than by resonance parameters; above 1 eV the single-level formalism used by ENDFB-V necessitates a structured file 3 contribution consisting of more than 1300 energy points; furthermore, information on level-spins has not been included. Indeed the ENDFB-V 235U resonance region is based on an analysis done in 1970 for ENDFB-III and therefore does not include the results of high quality measurements done in the past 18 years. The present paper presents the result of an R-matrix multilevel analysis of recent measurements as well as older data. The analysis also extends the resolved resonance region from its ENDFB-V upper limit of 81 eV to 110 eV. 13 refs., 2 figs., 1 tab.


R-matrix Analysis Of[sup 235]U Neutron Transmission and Cross Sections in the Energy Range 0 to 2.25 KeV.

R-matrix Analysis Of[sup 235]U Neutron Transmission and Cross Sections in the Energy Range 0 to 2.25 KeV.

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Published: 2001

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This document describes a new R-matrix analysis of[sup 235]U cross section data in the energy range from 0 to 2,250 eV. The analysis was performed with the computer code SAMMY, that has recently been updated to permit, for the first time, inclusion of both differential and integral data within the analysis process. Fourteen differential data sets and six integral quantities were used in this evaluation: two measurements of fission plus capture, one of fission plus absorption, six of fission alone, two of transmission, and one of eta, plus standard values of thermal cross sections for fission, capture, and scattering, and of K1 and the Westcott g-factors for both fission and absorption. An excellent representation was obtained for the high-resolution transmission, fission, and capture cross-section data as well as for the integral quantities. The result is a single set of resonance parameters spanning the entire range up to 2,250 eV, a decided improvement over the present ENDF/VI evaluation, in which eleven discrete resonance parameter sets are required to cover that same energy range. This new evaluation is expected to greatly improve predictability of the criticality safety margins for nuclear systems in which[sup 235]U is present.


R-matrix Analysis of /sup 239/Pu Neutron Cross Sections in the Energy Range Up to 1000 EV.

R-matrix Analysis of /sup 239/Pu Neutron Cross Sections in the Energy Range Up to 1000 EV.

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Published: 1989

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The report is a description of the analysis of the /sup 239/Pu neutron cross sections in the resolved resonance region using the multilevel-multichannel Reich-Moore code SAMMY. The resonance parameters were obtained in the energy range up to 1000 eV. The table of the resonance parameters is given with some statistical properties of the parameters. Tabulated and graphical comparisons between the experimental data and the calculated cross sections are given. The results are available in ENDF/B-V format and will be proposed for the evaluated data libraries JEF2 and ENDF/B-VI. 24 refs., 23 figs., 16 tabs.


R-matrix Analysis of the /sup 239/Pu Cross Sections Up to 1 KeV.

R-matrix Analysis of the /sup 239/Pu Cross Sections Up to 1 KeV.

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Published: 1986

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The results are reported of an R-matrix resonance analysis of the /sup 239/Pu neutron cross sections up to 1 keV. After a description of the method of analysis the nearly 1600 resonance parameters obtained are listed and extensive graphical and numerical comparisons between calculated and measured cross-section and transmission date are presented. 47 refs., 47 figs., 8 tabs.


Nuclear Science Abstracts

Nuclear Science Abstracts

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Published: 1975

Total Pages: 632

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NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.