Thermal cross sections and resonance integrals of fission and capture of241Am,243Am,245Cm,249Bk, and249Cf

Gavrilov, V.D.; Goncharov, V. A.; Ivanenko, V. V.; Kustov, V. N.; Smirnov, V. P.

doi:10.1007/bf01241062

Cited by 30 publications

(8 citation statements)

References 7 publications

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“…Cutoff energy (eV) Seaborg et al 4) 1946 560 AE 84 Hanna et al 5) 1951 568 AE 56:8 Street et al 6) 1952 300 Pomerance 7) 1955 625 AE 35 Ã Deal et al 8) 1964 770 900 0.5 Bak et al 9) 1967 670 AE 60 2100 AE 200 0.4 Harbour et al 10) 1973 748 AE 20 1330 AE 117 0.369 Gavrilov et al 11) 1976 780 AE 50 1570 AE 10 0.5 Shinohara et al 12) 1997 768 AE 58 1694 AE 146 0.5 Fioni et al 13) 2001 636 AE 46 Maidana et al 14) 2001 602 AE 9 1665 AE 91 0.5…”

Section: Sample Preparation and Neutron Irradiationunclassified

“…3) However, there are discrepancies among reported data for the thermal-neutron capture cross section ( 0,g ) and the resonance integral (I 0,g ) of the 241 Am(n, ) 242g Am reaction. Measured data [4][5][6][7][8][9][10][11][12][13][14] are listed in Table 1. Conflicting data have been reported by many measurements for the neutron capture cross section of 241 Am.…”

Section: Introductionmentioning

confidence: 99%

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Thermal-Neutron Capture Cross Section and Resonance Integral of Americium-241

Nakamura

Ohta

Harada

et al. 2007

J. Nucl. Sci. Technol.

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The thermal-neutron capture cross section (0;g) and the resonance integral (I 0;g) leading to the ground state of 242 Am were measured by an activation method for neutron capture by 241 Am. A method with gadolinium, which was similar to the cadmium difference method, was used to measure the cross section 0;g with attention to resonances of 241 Am. Americium chloride samples containing 241 Am radioisotope were irradiated for 68 h in the long-irradiation plug of the Kyoto University Research Reactor, KUR. Wires of Co/Al and Au/Al alloys were used as monitors to determine thermal-neutron fluxes and epithermal Westcott's indexes at the irradiation positions. An-ray spectrometer was used to measure the activity ratios of 242 Cm to 241 Am. On the basis of Westcott's convention, the 0;g and I 0;g values were determined as 628 AE 22 b and 3:5 AE 0:3 kb, respectively.

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Section: Sample Preparation and Neutron Irradiationunclassified

Section: Introductionmentioning

confidence: 99%

Thermal-Neutron Capture Cross Section and Resonance Integral of Americium-241

Nakamura

Ohta

Harada

et al. 2007

J. Nucl. Sci. Technol.

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“…<lard neutron spectrum field having a pure Maxwellian distribution in the Kyoto University Reactor (KUR) at KURRI. The current result is compared with the previous experimental and the evaluated data< 16 l< 23 )- ( 28 ).…”

Section: Introductionmentioning

confidence: 85%

Measurements of Neutron-induced Fission Cross Section of Americium-243 from Thermal Neutron Energy to 15 keV Using Lead Slowing-down Spectrometer and Thermal Neutron Facility

Kobayashi¹,

Kai²,

Yamamoto³

et al. 1999

Journal of Nuclear Science and Technology

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The neutron-induced fission cross section of 243 Am was measured relative to that of 235 U from thermal neutron energy to 15 keV making use of a double fission chamber with 243 Am and 235 U electrodeposited layers. The data above 0.05eV were measured using a lead slowing-down spectrometer coupled to an electron linear accelerator. A relative measurement to the 10 B(n, a) reaction was also made using a BF3 counter at energies below lkeV, and normalized to the absolute value obtained by using the cross section of the 235 U(n, f) reaction between 200 e V and 1 ke V. The existing experimental data by \Visshak and Kappeler, and by Knitter and Budtz-J0rgensen are in general agreement with the current measurement in the relevant energy region. However, the data by Seeger are considerably higher. The evaluated nuclear data in JENDL-3.2, ENDF /B-VI and JEF-2.2, whose data were broadened by the energy resolution function of the spectrometer, have been compared with the measured result. The fission cross section for thermal neutrons was measured in a neutron field with a pure Maxwellian spectrum. The derived result at 0.0253 e Vis 81.3±2.5 mb. The data by Wagemans et al. and in ENDF /B-VI are close to the current measurement. However, the values by Asghar et al., Gavrilov et al. and Mughabghab, and the evaluated data in JENDL-3.2 and JEF-2.2 are discrepant from the current result by a factor of 1.4 to 2.4.

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“…The differences in data are reflected in the resonance parameters found in evaluated libraries. The evaluation present in JEFF-3.2 adopts essentially the results provided by Lampoudis Gavrilov (1976) [64] 1800(90) 1570(10) b Harbour (1973) [65] 1538(118) 1330(117) b Hellstrand (1970) [66] 2700 c Bak (1967) [67] 2400 (200) 2100(200) b Nakamura 3500 (2007) [68] (300) b Maidana (2001) [69] 1665(91) b Deal (1964) [70] 900 Additional information concerning the capture cross section in the few-eV neutron energy range can be obtained from direct measurements of the resonance integral I 0 , I 0 = ∞ E c σ γ (E)/EdE, with E c usually being taken as 0.5 eV. In the case of the 241 Am(n,γ ) cross section the contribution of the first three resonances to I 0 is ∼75%, whereas the value of the integral above 20 eV represents less than 10%, according to parameters from JEFF-3.2.…”

Section: Comparison With Previous Measurements and Evaluationsmentioning

confidence: 99%

“…The total resonance integral is given by I 0 = I m 0 + I g 0 . Depending on the experimental technique, the integral experiments provide either all three resonance integrals [63][64][65]67], the total resonance integral [66], or the resonance integral feeding the ground state [68][69][70].…”

Section: Comparison With Previous Measurements and Evaluationsmentioning

confidence: 99%

Measurement and analysis of theAm241neutron capture cross section at the n_TOF facility at CERN

Mendoza¹,

Cano‐Ott²,

Altstadt³

et al. 2018

Phys. Rev. C

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The 241 Am(n,γ ) cross section has been measured at the n_TOF facility at CERN with the n_TOF BaF 2 Total Absorption Calorimeter in the energy range between 0.2 eV and 10 keV. Our results are analyzed as resolved resonances up to 700 eV, allowing a more detailed description of the cross section than in the current evaluations, which contain resolved resonances only up to 150-160 eV. The cross section in the unresolved resonance region is perfectly consistent with the predictions based on the average resonance parameters deduced from the resolved resonances, thus obtaining a consistent description of the cross section in the full neutron energy range under study. Below 20 eV, our results are in reasonable agreement with JEFF-3.2 as well as with the most recent direct measurements of the resonance integral, and differ up to 20-30% with other experimental data. Between 20 eV and 1 keV, the disagreement with other experimental data and evaluations gradually decreases, in general, with the neutron energy. Above 1 keV, we find compatible results with previously existing values.

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Thermal cross sections and resonance integrals of fission and capture of241Am,243Am,245Cm,249Bk, and249Cf

Cited by 30 publications

References 7 publications

Thermal-Neutron Capture Cross Section and Resonance Integral of Americium-241

Thermal-Neutron Capture Cross Section and Resonance Integral of Americium-241

Measurements of Neutron-induced Fission Cross Section of Americium-243 from Thermal Neutron Energy to 15 keV Using Lead Slowing-down Spectrometer and Thermal Neutron Facility

Measurement and analysis of theAm241neutron capture cross section at the n_TOF facility at CERN

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