The thermal-neutron fission cross section and the fission-resonance integral for243Cm

THERMAL FISSION CROSS SECTION MEASUREMENTS OF 243CM AND 245CM

“…Although these preliminary results deviate up to 12% from the values adopted by different nuclear data libraries, they overlap within error-bars with most of the previous experimental values [3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18]. A better agreement is obtained for 245 Cm, when using the recent g f value of Serot et al [19], which leads to a thermal crosssection value of (1957±65) b.…”

“…[5] and Alekseev [7] and it shows a deviation of 7% from the value adopted by JEFF-3.1.1 and 12% from the value adopted by JENDL nuclear data library. The statistical uncertainty of the present result is less than 1%, while the systematic uncertainty is almost 2%.…”

“…[2] have been used to correct for the deviation from the 1/v shape of these fission cross sections. [3][4][5][6][7]. Some of these authors did not consider the Westcott factor when extrapolating the cross section to E n = 25.3 meV [3,6].…”

243Cm neutron fission cross section

“…The values of the resonance fission integral and the Westcott factor g(T) are obtained. The error in the values obtained for the fission cross sections (taking account of normalization) is no better than 10%.The thermal-neutron (E 0 = 0.0253 eV) fission cross section of 244 Cm (σ 0 ) was measured in two experiments performed in reactor spectra: σ 0 = 609.6 ± 25.9 b (neutron spectrum temperature 323 K) in the first [4] and σ 0 = 672 ± 60 b (T = 353 K) in the second [5]. A new evaluation of the fission cross section for thermal neutrons is made.…”

“…The thermal-neutron (E 0 = 0.0253 eV) fission cross section of 244 Cm (σ 0 ) was measured in two experiments performed in reactor spectra: σ 0 = 609.6 ± 25.9 b (neutron spectrum temperature 323 K) in the first [4] and σ 0 = 672 ± 60 b (T = 353 K) in the second [5]. The ENDF/BVII recommended value is σ 0 = 620.3 b [6], which is the weighted-mean of the measured values.…”