Measurement of resolved resonances of232Th(n,γ) at the n_TOF facility at CERN (original) (raw)
Related papers
Physical Review C, 2006
We have measured the neutron capture reaction yield of 232 Th at the neutron time-of-flight facility n TOF at CERN in the energy range from 1 eV to 1 MeV. The average capture cross section has been extracted in the energy range from 4 keV up to 1 MeV with an overall accuracy better than 4%. An independent IAEA evaluation shows good agreement with the data. The average cross section has been expressed in terms of average resonance parameters using the partial waves ℓ = 0, 1, and 2.
Measurement and resonance analysis of the ^{237}Np neutron capture cross section
Physical Review C, 2012
The neutron capture cross section of 237 Np was measured between 0.7 and 500 eV at the CERN n_TOF facility using the 4π BaF 2 Total Absorption Calorimeter. The experimental capture yield was extracted minimizing all the systematic uncertainties and was analyzed together with the most reliable transmission data available using the SAMMY code. The result is a complete set of individual as well as average resonance parameters [D 0 = 0.56(2) eV, γ = 40.9(18) meV, 10 4 S 0 = 0.98(6), R = 9.8(6) fm]. The capture cross section obtained in this work is in overall agreement with the evaluations and the data of Weston and Todd [Nucl. Sci. Eng. 79, 184 (1981)], thus showing sizable differences with respect to previous data from Scherbakov et al. [J. Nucl. Sci. Technol. 42, 135 (2005)] and large discrepancies with data Kobayashi et al. [J. Nucl. Sci. Technol. 39, 111 (2002)]. The results indicate that a new evaluation combining the present capture data with reliable transmission data would allow reaching an accuracy better than 4%, in line with the uncertainty requirements of the nuclear data community for the design and operation of current and future nuclear devices.
First high resolution measurement of neutron capture resonances in 176Yb at the n_TOF CERN facility
EPJ Web of Conferences
Several international agencies recommend the study of new routes and new facilities for producing radioisotopes with application to nuclear medicine. 177Lu is a versatile radioisotope used for therapy and diagnosis (theranostics) of cancer with good success in neuroendocrine tumours that is being studied to be applied to a wider range of tumours. 177Lu is produced in few nuclear reactors mainly by the neutron capture on 176Lu. However, it could be produced at high-intensity celeratorbased neutron facilities. The energy of the neutrons in accelerator-based neutron facilities is higher than in thermal reactors.Thus, experimental data on the 176Yb(n,γ) cross-section in the eV and keV region are mandatory to calculate accurately the production of 177Yb, which beta decays to 177Lu. At present, there are not experimental data available from thermal to 3 keV of the 176Yb(n,γ) cross-section. In addition, there is no data in the resolved resonance region (RRR). This contribution shows the fi...
The 236U neutron capture cross-section measured at the n_TOF CERN facility
EPJ Web of Conferences
The 236 U isotope plays an important role in nuclear systems, both for future and currently operating ones. The actual knowledge of the capture reaction of this isotope is satisfactory in the thermal region, but it is considered insufficient for Fast Reactor and ADS applications. For this reason the 236 U(n, γ) reaction crosssection has been measured for the first time in the whole energy region from thermal energy up to 1 MeV at the n TOF facility with two different detection systems: an array of C 6 D 6 detectors, employing the total energy deposited method, and a 4π total absorption calorimeter (TAC), made of 40 BaF 2 crystals. The two n TOF data sets agree with each other within the statistical uncertainty in the Resolved Resonance Region up to 800 eV, while sizable differences (up to 20%) are found relative to the current evaluated data libraries. Moreover two new resonances have been found in the n TOF data. In the Unresolved Resonance Region up to 200 keV, the n TOF results show a reasonable agreement with previous measurements and evaluated data.
Neutron resonance spectroscopy at n_TOF at CERN
2008
Neutron resonance spectroscopy plays an important role in the investigation of neutron induced reaction cross sections and nuclear structure in the MeV excitation range. Neutron time-of-flight facilities are the most used installations to explore neutron resonances. In this paper we describe the basic features of neutron resonance spectroscopy together with recent results from the time-of-flight facility n TOF at CERN.
The 234 U neutron capture cross section measurement at the n_TOF facility
Proceedings of the …, 2007
The neutron capture cross-section of 234 U has been measured for energies from thermal up to the keV region in the neutron time-of-flight facility n TOF, based on a spallation source located at CERN. A 4π BaF 2 array composed of 40 crystals, placed at a distance of 184.9 m from the neutron source, was employed as a total absorption calorimeter (TAC) for detection of the prompt γ-ray cascade from capture events in the sample. This text describes the experimental setup, all necessary steps followed during the data analysis procedure. Results are presented in the form of R-matrix resonance parameters from fits with the SAMMY code and compared to the evaluated data of ENDF in the relevant energy region, indicating the good performance of the n TOF facility and the TAC.
Determination of the neutron capture resonance integrals of 55Mn, 115In, 121Sb, 123Sb and 139La
Journal of Inorganic and Nuclear Chemistry, 1968
The neutron capture resonance integrals of Mn55, In115, Sbl21, Sb123 and La139 have been measured by activation techniques taking the neutron capture reaction on Au 197 as the reference. The following values have been measured for the resonance integrals with a lower limit 0.55 eV: 55Mn 13-7+__0-7 b, rain 3350_ + 150b, 121Sb 200_+ 17 b, lzzSb 116_+ 10 b, ~ZgLa 10.8_+ 1-1 b. The reported errors for mSb, ~2sSb and l~gLa are mainly due to uncertainty in the knowledge of the 2200 msec cross-sections,