scholarly journals Neutron capture cross section measurements of 232Th in the 30-600 keV energy range

2019 ◽  
Vol 10 ◽  
pp. 173
Author(s):  
D. Karamanis ◽  
M. Petit ◽  
S. Andriamonje ◽  
G. Barreau ◽  
M. Bercion ◽  
...  
Keyword(s):  
Energy Range ◽  
Cross Section ◽  
Cross Sections ◽  
Neutron Capture ◽  
Energy Region ◽  
Preliminary Analysis ◽  
Capture Cross Section ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Capture Cross Sections

Neutron capture cross sections of 232T/i have been measured relative to 197Au in the energy region from 30 keV to 600 keV. The neutron source was the reaction 7Li(p, n) produced on the 4 MV Van de Graaff Accelerator of the Centre d' Etudes Nucléaires de Bordeaux (CENBG). Preliminary analysis of the measurements indicates that the cross sections are closer to the JENDL database values.

THERMAL NEUTRON CAPTURE CROSS-SECTION OF Na23 AND Mn55

1953 ◽  
Vol 31 (3) ◽  
pp. 204-206 ◽  
Author(s):  
Rosalie M. Bartholomew ◽  
R. C. Hawkings ◽  
W. F. Merritt ◽  
L. Yaffe
Keyword(s):  
Thermal Neutron ◽  
Cross Section ◽  
Cross Sections ◽  
Neutron Capture ◽  
Half Life ◽  
Capture Cross Section ◽  
Thermal Neutron Capture ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Capture Cross Sections

The thermal neutron capture cross sections of Na23 and Mn55 have been determined using the activation method. The values are 0.53 ± 0.03 and 12.7 ± 0.3 barns respectively with respect to σAul97 = 93 barns. These agree well with recent pile oscillator results. The half-life for Mn56 is found to be 2.576 ± 0.002 hr.

REACTOR NEUTRON CAPTURE CROSS SECTION OF 51-DAY Sr89

1957 ◽  
Vol 35 (10) ◽  
pp. 1215-1219 ◽  
Author(s):  
L. P. Roy ◽  
J. C. Roy
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
High Flux ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Naturally Occurring ◽  
Reactor Spectrum ◽  
Capture Cross Sections

The neutron capture cross section of Sr89 has been measured by an activation method. Naturally occurring strontium was irradiated in different high flux positions in the NRX reactor at Chalk River and the amount of Sr90 formed by successive neutron capture in Sr88 was determined by separating and measuring its daughter Y90. Using values of 36.6 and 0.005 barns for the respective neutron capture cross sections of Co59 and Sr88, the capture cross section of Sr89 for reactor spectrum neutrons was found to be 0.49 ± 0.10 barn.

scholarly journals Measurement of the 244Cm capture cross sections at both CERN n_TOF experimental areas

2020 ◽  
Vol 239 ◽  
pp. 01034
Author(s):  
V. Alcayne ◽  
E. Mendoza ◽  
D Cano-Ott ◽  
A. Kimura ◽  
O. Aberle ◽  
...  
Keyword(s):  
Experimental Data ◽  
Cross Section ◽  
Cross Sections ◽  
Neutron Capture ◽  
Capture Cross Section ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Experimental Area ◽  
High Burnup ◽  
Capture Cross Sections

Accurate neutron capture cross section data for minor actinides (MAs) are required to estimate the production and transmutation rates of MAs in light water reactors with a high burnup, critical fast reactors like Gen-IV systems and other innovative reactor systems such as accelerator driven systems (ADS). Capture reactions of 244Cm open the path for the formation of heavier Cm isotopes and of heavier elements such as Bk and Cf. In addition, 244Cm shares nearly 50% of the total actinide decay heat in irradiated reactor fuels with a high burnup, even after three years of cooling. Experimental data for this isotope are very scarce due to the difficulties of providing isotopically enriched samples and because the high intrinsic activity of the samples requires the use of neutron facilities with high instantaneous flux. The only two previous experimental data sets for this neutron capture cross section have been obtained in 1969 using a nuclear explosion and, more recently, at J-PARC in 2010. The neutron capture cross sections have been measured at n_TOF with the same samples that the previous experiments in J-PARC. The samples were measured at n_TOF Experimental Area 2 (EAR-2) with three C6D6 detectors and also in Experimental Area 1 (EAR-1) with the Total Absorption Calorimeter (TAC). Preliminary results assessing the quality and limitations of these new experimental datasets are presented for the experiments in both areas. Preliminary yields of both measurements will be compared with evaluated libraries for the first time.

Measurement of Neutron Capture Cross Section and Gamma-Ray Spectra of 88Sr in keV Energy Region

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1844-1847 ◽  
Author(s):  
T. Katabuchi ◽  
N. C. Hai ◽  
M. Igashira ◽  
S. Kamada ◽  
M. Tajika ◽  
...  
Keyword(s):  
Cross Section ◽  
Neutron Capture ◽  
Energy Region ◽  
Capture Cross Section ◽  
Gamma Ray ◽  
Capture Cross ◽  
Neutron Capture Cross Section

scholarly journals Neutron capture cross section of 185Re leading to ground and isomer states of 186Re in the keV-neutron energy region

2018 ◽  
Vol 178 ◽  
pp. 03005
Author(s):  
T. Katabuchi ◽  
K. Takebe ◽  
S. Umezawa ◽  
R. Fujioka ◽  
T. Saito ◽  
...  
Keyword(s):  
Cross Section ◽  
Neutron Capture ◽  
Energy Region ◽  
Capture Cross Section ◽  
Production Cross ◽  
Pulse Height ◽  
Capture Cross ◽  
Neutron Capture Cross Section ◽  
Section Data ◽  
The Difference

The neutron capture cross section of 185Re was measured in the astrophysically important energy region. Measurements were made using a neutron beam from a 7Li(p,n)7Be neutron source with energies ranging from 3 to 90 keV. Two different experimental techniques, time-of-flight (TOF) and activation methods, were employed. In the TOF experiments, the total neutron capture cross section of 185Re was determined by the pulse-height weighting technique. In the activation method, the partial capture cross section leading to the ground state of 186Re was measured by detecting decay γ-rays from neutron activated samples. The present cross section values were compared with evaluated cross section data and previous measurements. The difference between the TOF and activation results was smaller than experimental uncertainties. This suggests that the production cross section of isomer states of 186Re is very small.

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