keV Neutron Capture in 141Pr

Taylor, RB; Allen, B.J.; Musgrove, AR de L; Macklin, R. L.

doi:10.1071/ph790551

Cited by 18 publications

(9 citation statements)

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“…Capture cross sections for 141 Pr are compared to recent libraries and measurements as shown in fall 4. Our results reproduce the experimental data [12][13][14][15][16][17][18] below and above the URR. Sm-isotopes (n,2n) Sm-isotopes (n,2n) Fig.…”

Section: Resultssupporting

confidence: 88%

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Kim

Lee

Herman

et al. 2007

Nd2007

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Abstract. Neutron cross sections for fission products play an important role not only in the design of extended burnup core and fast reactors, but also in the study of the backend fuel cycle and the criticality analysis of spent fuel. New evaluations for the ENDF/B-VII.0 library were performed by the KAERI-BNL collaboration for the following 32 fission products: 95 Nd, 144,147,[148][149][150][151][152][153][154] and 156,158,[160][161][162][163][164] Dy. The evaluations cover a large amount of reaction channels, from 10 −5 eV to 20 MeV, including thermal, resolved, unresolved resonance regions, and fast neutron region.

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Section: Resultssupporting

confidence: 88%

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Kim

Lee

Herman

et al. 2007

Nd2007

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“…The Maxwellian-averaged cross section (MACS) of capture reaction is calculated combining the present data with the resolved resonance data evaluated in JENDL-4.0. The result is shown in Figure 3 comparing with ENDF/B-VII.1 and the experimental data measured by Voss [13] and Taylor [41]. The present calculation gives the similar result to JENDL-4.0 and ENDF/B-VII.1 as well as the two experimental data.…”

Section: Neutron Capture Cross Sectionsupporting

confidence: 78%

Evaluation of neutron nuclear data of praseodymium-141 and -143

Minato

2013

Journal of Nuclear Science and Technology

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For the next version of JENDL general purpose file, neutron nuclear data on 141,143 Pr are evaluated considering cross sections and spectra provided from experiments in the fast neutron energy region up to 20 MeV. Total and elastic cross sections are derived from optical model. Pre-equilibrium and direct-reaction processes are taken into account in addition to the compound process. The statistical model is applied to calculate the cross sections above the resolved resonance region. For unstable 143 Pr nuclide having less experimental data, we use the same parameters as 141 Pr for mass-dependent and -independent terms in the optical potential. The resolved resonance parameter remains unchanged from JENDL-4.0. The present evaluations give consistent results with experimental data, reflecting newly measured one. The evaluated data are compiled in ENDF-6 format for the next version of JENDL.Keywords: evaluation; neutron nuclear data; cross section; spectrum; fission product; praseodymium-141; praseodymium-143 IntroductionThe fourth version of the Japanese Evaluated Nuclear Data Library (JENDL-4.0 [1]) was released in May 2010. In the library, 215 nuclides are regarded as fission products in the region from Z = 30 to 68. The resolved and unresolved resonance parameters for all of those nuclides were examined by reviewing experimental data; however, the fast neutron region above the resolved resonances was re-evaluated only for 174 nuclides. The remaining 41 nuclides, which were not examined for the release of JENDL-4.0, need to be re-evaluated for the next version of JENDL general purpose file.Praseodymium-141 and -143, which are the target isotopes of the present work, are included in the remaining 41 nuclides. As mentioned, the resolved resonance parameters were re-examined in JENDL-4.0; however, cross sections in the fast neutron region were not revised. The last update was performed in JENDL-3.2 released at 1994, and the calculation was performed by the statistical-model code CASTHY [2] with the competing reaction using PEGASUS [3]. Several experimental data measured after the release of JENDL-3.2, which show a different value from old one referred by JENDL-4.0 (i.e., −3.2), also inclines us re-evaluation. The purpose of this study is to improve the nuclear data in the fast neutron

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“…The final states in 88Sr, which were included up to 4·04 MeV, were obtained from Bunting and Kraushaar (1976). Further general details relating to the statistical contribution, in particular calculation of the standard deviation, have been discussed by Taylor et al (1979). Nucleus …”

Section: Statistical Calculationsmentioning

confidence: 99%

“…Investigations of the resonance neutron capture mechanism for nuclei near the N = 50 closed shell (Toohey and Jackson 1974;Boldeman et al 1975Boldeman et al , 1976aBoldeman et al , 1976b . have indicated the presence of significant non-statistical effects.…”

Section: Introductionmentioning

confidence: 99%

Resonance Neutron Capture in 86,87Sr

Hicks¹,

Allen²,

Musgrove³

et al. 1982

Aust. J. Phys.

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The neutron capture cross sections of 86. 87 Sr have been measured with high energy resolution from 3 to 200 keY at the 40 m station of the Oak Ridge Electron Linear Accelerator. Individual resonances were analysed to 37 keY for 86Sr and to 14 keY for 87Sr, and average resonance parameters were deduced on the basis of assumed divisions between s-and p-wave resonances. The average radiative widths obtained on this basis are consistent with a capture mechanism which is predominantly statistical.

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keV Neutron Capture in 141Pr

Cited by 18 publications

References 4 publications

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Evaluation of neutron nuclear data of praseodymium-141 and -143

Resonance Neutron Capture in 86,87Sr

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