Measurement of thermal neutron cross section and resonance integral for (n,γ) reaction in 152Sm

Karadağ, Mustafa; Yücel, Haluk; Budak, Mustafa Güray

doi:10.1016/j.anucene.2006.12.001

Cited by 20 publications

(7 citation statements)

References 32 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This value is also shown in Figure 3 together with the values at 0.0253 eV and 0.0536 eV neutron energies [14] and the data in the ENDF/B-VII [20] and TENDL-2012 files [21]. Several authors have reported Brought to you by | New York University Bobst Library Technical Services Authenticated Download Date | 6/1/15 12:57 PM [12]. Most of these measurements are very old and it is very difficult to extract precise value from these reported values.…”

Section: Resultsmentioning

confidence: 65%

See 1 more Smart Citation

Experimental cross section for the ¹⁵²Sm(n, γ)¹⁵³Sm reaction at 0.0334 eV

Uddin¹,

Afroze

Datta³

et al. 2014

Radiochimica Acta

View full text Add to dashboard Cite

The neutron capture cross section for the 152 Sm( , ) 153 Sm reaction at an energy of 0.0334 eV was measured for the first time using monochromatic neutrons of a powder diffractometer at the TRIGA Mark II nuclear reactor at Dhaka, Bangladesh. The 197 Au( , ) 198 Au reaction was used to monitor the neutron beam intensity. The radioactivity of the products was determined via high resolution -ray spectrometry. The obtained cross section value is 184 ± 22 b, which is consistent with both the ENDF/B-VII and TENDL-2012 data libraries. The measured value at 0.0334 eV and the previous data at 0.0536 eV confirm the reliability of the data in the above libraries.

show abstract

Section: Resultsmentioning

confidence: 65%

“…Most of the measurements have been done in the thermal energy region [cf. [2][3][4][5][6][7][8][9][10][11][12]. Uddin et al described in detail the measurement of the neutron capture cross sections for several targets at 0.0536 eV for the first time [13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

Experimental cross section for the ¹⁵²Sm(n, γ)¹⁵³Sm reaction at 0.0334 eV

Uddin¹,

Afroze

Datta³

et al. 2014

Radiochimica Acta

View full text Add to dashboard Cite

show abstract

“…Neutron radiative capture cross sections for 2,200 m/s neutrons ( 0 ) and radiative capture resonance integrals (I 0 ) for various MAs and LLFPs have been measured in this point of view. [1][2][3][4][5][6][7][8][9][10][11] However, the cross section data is not sufficient for these analyses and studies in the current status, and there exist problems in terms of accuracies of the cross section data for some nuclides such as 237 Np, 238 Pu, 241 Am, and 243 Am. 12) Americium-243 is one of the important MAs in the study of nuclear transmutation because of not only its long half-life (7,370 yr) but also the production of higher-mass Cm isotopes, e.g.…”

Section: Introductionmentioning

confidence: 87%

Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons

Ohta

Nakamura

Harada

et al. 2006

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

The effective capture cross section of 243 Am for thermal neutrons was measured with an activation method. A sample of 243 Am was irradiated for 10 hrs at Kyoto University Reactor, KUR. After the irradiation, the sample was cooled for one month. In the cooling time, 244m Am and 244g Am produced by the irradiation decayed out to 244 Cm. The rays emitted from 243 Am and 244 Cm were measured with a silicon surface barrier detector. The neutron flux at the irradiation position was monitored using Au/Al and Co/Al wires. The effective capture cross section was deduced as 174:5AE5:3b from the -ray counts and the neutron flux. The quantity r ffiffiffiffiffiffiffiffiffiffi T=T 0 p in Westcott's convention was 0:037AE0:004. The present result was compared with the effective capture cross sections from the JENDL-3.3 and the Mughabghab evaluations.

show abstract

Section: Introductionmentioning

confidence: 99%

Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons

Ohta

Nakamura

Harada

et al. 2006

J. Nucl. Sci. Technol.

View full text Add to dashboard Cite

The effective capture cross section of 243 Am for thermal neutrons was measured with an activation method. A sample of 243 Am was irradiated for 10 hrs at Kyoto University Reactor, KUR. After the irradiation, the sample was cooled for one month. In the cooling time, 244m Am and 244g Am produced by the irradiation decayed out to 244 Cm. The rays emitted from 243 Am and 244 Cm were measured with a silicon surface barrier detector. The neutron flux at the irradiation position was monitored using Au/Al and Co/Al wires. The effective capture cross section was deduced as 174:5AE5:3b from the-ray counts and the neutron flux. The quantity r ffiffiffiffiffiffiffiffiffiffi T=T 0 p in Westcott's convention was 0:037AE0:004. The present result was compared with the effective capture cross sections from the JENDL-3.3 and the Mughabghab evaluations.

show abstract

Measurement of thermal neutron cross section and resonance integral for (n,γ) reaction in 152Sm

Cited by 20 publications

References 32 publications

Experimental cross section for the ¹⁵²Sm(n, γ)¹⁵³Sm reaction at 0.0334 eV

Experimental cross section for the ¹⁵²Sm(n, γ)¹⁵³Sm reaction at 0.0334 eV

Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons

Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons

Contact Info

Product

Resources

About

Measurement of thermal neutron cross section and resonance integral for (n,γ) reaction in 152Sm

Cited by 20 publications

References 32 publications

Experimental cross section for the 152Sm(n, γ)153Sm reaction at 0.0334 eV

Experimental cross section for the 152Sm(n, γ)153Sm reaction at 0.0334 eV

Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons

Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons

Contact Info

Product

Resources

About

Experimental cross section for the ¹⁵²Sm(n, γ)¹⁵³Sm reaction at 0.0334 eV

Experimental cross section for the ¹⁵²Sm(n, γ)¹⁵³Sm reaction at 0.0334 eV