An evaluated neutronic data file for elemental cobalt

Guenther, P.T.; Lawson, R. P. W.; Meadows, J.W.; Sugimoto, M.; Smith, A.B.; Smith, D.L.; Howerton, R.J.

doi:10.2172/6587546

Cited by 4 publications

(4 citation statements)

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“…[6][7][8][9][10][11][12] and Set III (Nos. [13][14][15][16][17][18][19][20][21][22][23][24][25][26][27].…”

Section: Methodsunclassified

“…ENDF/B-V [13] values (generally obtained from the Dosimetry File) were employed for this analysis except as noted for the following reactions: Ti-47(n,p)Sc-47 [16]; Co-59(n,p)Fe-59. Co-59(n,2n)Co- 58 and Co-59(n,fl-)Mn-56 [17]; Zn-64(n,p)Cu-64 [18]; Cu-65(n,p)Ni-65 [19]; In-113(n,n')In-113m [19]; and In-115(n,n')In-115m [20]. The resultant C/E comparisons are shown schematically in Fig.…”

Section: Comparison Of Measured and Calculated Cross Sectionsmentioning

confidence: 99%

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Microscopic Integral Cross Section Measurements in the Be(d,n) Neutron Spectrum for Applications in Neutron Dosimetry, Radiation Damage and the Production of Long-Lived Radionuclides

Smith¹,

Meadows²,

Greenwood³

1992

Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry

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“…[6][7][8][9][10][11][12] and Set III (Nos. [13][14][15][16][17][18][19][20][21][22][23][24][25][26][27].…”

Section: Methodsunclassified

Section: Comparison Of Measured and Calculated Cross Sectionsmentioning

confidence: 99%

Microscopic Integral Cross Section Measurements in the Be(d,n) Neutron Spectrum for Applications in Neutron Dosimetry, Radiation Damage and the Production of Long-Lived Radionuclides

Smith¹,

Meadows²,

Greenwood³

1992

Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry

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“…B. Smith for the ENDF/B-VI evaluation [4,5]. Only one of these measurements was processed at the time: Run 10454TS.…”

Section: The High Resolution Transmission Measurementsmentioning

confidence: 99%

“…These measurements have much better resolution than previously published measurements [2,31. The results of one of these measurements were used in the ENDF/B-VI evaluation of the S9 Co total cross section above 100 keV [4,5], but the data were not used below 100 keV where the ENDF/B-VI cross sections are represented by resolved resonance parameters based on a recent compilation of Mughabghab et al [Cj.…”

Section: Introductionmentioning

confidence: 99%

Multilevel resonance analysis of sup 59 Co neutron transmission measurements

Saussure¹,

Larson²

1991

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Large discrepancies exist between the high-resolution 59 Co neutron transmission data of Harvey et al. and the resolved resonance parameters of ENDF/D-VI. In order to provide new resonance parameters consistent with these data, the high-resolution transmission measurements have been analyzed with the computer code SAMMY. Results of that analysis are reported here.( 59 Co transmission measurements, R-matrix analysis, resonance parameters)

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ENDF/B-VI Nuclear Data Evaluations for Fusion Applications

1989

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The next release of the ENDF/B data library planned for 1989 contains improved ' data evaluations of Interest to the fusion neutronics community. New data formats permit inclusion of energy-angle correlated particle emission spectra and recoil nucleus energy spectra. Enhanced formats for covariance information have been developed. Many new isotopic evaluations will lead to improved energy conservation and kerna factor calculations. Improved nuclear model calculations will provide reliable particle emission data where experimental information is sparse. Improved Bayssian fitting codes will provide more accurate evaluations for data rich reactions such as Li(n,nt)a. All of the most important fusion material evaluations contain these new features. Planning for ENDF/B-VI began in 1979. As a first step, it was decided to perform a simultaneous evaluation of Che neutron "standard" cross sections. The plan was to complete ENDF/B-VI in 1984 or 1985. However, drastic cuts in funding in the United States fast breeder reactor program resulted in a reduction of more than 75 percent in the resources available for the project. Responsibility for the production of ENDF/B-VI was transferred from Reactor Technology to Energy Research within the U.S. Department of Energy. The simultaneous evaluation of the "standard" cross sections also required more time and staffing than originally envisioned, but was successfully completed In the summer of 1987. Significant enhancements in formats for ENDF data files have been developed since ENDF/B-V was released. The formats have been extended to incorporate the following new or improved data representations: 1) R-function and R-matrlx resonance region representations; 2) incident charged particle reactions; 3) emitted particle energy-angle distributions (File 6); 4) covariance formats for secondary angle distributions, secondary energy distributions, and lsoaer production. ENDF-B-VI is the first version of the ENDF/B data library in which fusion data requirements have provided the major impetus for format enhancements and for evaluation improvements for the non-fissile, non-fertile nuclides. The new data evaluations provide improved calculations of radiation damage, neutron transport, shielding, activation, dosimetry, tritium breeding, heating, and energy balance. More covariance Information will provide better parameter uncertainty calculations. To help meet these needs, the ENDF/B-VI data library includes, for the first Research has been carried under the aucpices of the U.S.D.O.E. under Contract No. DE-AC02-76CH00016.

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An evaluated neutronic data file for elemental cobalt

Cited by 4 publications

References 0 publications

Microscopic Integral Cross Section Measurements in the Be(d,n) Neutron Spectrum for Applications in Neutron Dosimetry, Radiation Damage and the Production of Long-Lived Radionuclides

Microscopic Integral Cross Section Measurements in the Be(d,n) Neutron Spectrum for Applications in Neutron Dosimetry, Radiation Damage and the Production of Long-Lived Radionuclides

Multilevel resonance analysis of sup 59 Co neutron transmission measurements

ENDF/B-VI Nuclear Data Evaluations for Fusion Applications

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