A fast ionization chamber for fission cross-section measurements at n_TOF

Calviani, M.; Cennini, P.; Karadimos, D.; Ketlerov, V.; Konovalov, V.; Furman, W.; Goverdowski, A.; Vlachoudis, V.; Zanini, L.

doi:10.1016/j.nima.2008.06.006

Cited by 50 publications

(44 citation statements)

References 20 publications

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“…From the performed Monte Carlo simulations [21] the efficiencies were found to be 50.7% and 45.3% for 241 Am and 235 U, respectively. The resulting efficiency correction is 5.4%.…”

Section: Discussionmentioning

confidence: 98%

“…Major difficulties in data analysis were related to energy losses in the samples and to pile-up signals produced by the high background of α-particles from the decay of 241 Am, which were investigated by realistic FLUKA [20] Monte Carlo simulations of the detector response [21]. In these simulations, kinetic energies and fragment masses were randomly generated according to the respective distributions [22] to evaluate the corrections for absorption losses in the samples and for the threshold effect imposed by the α activity (see fig.…”

Section: Discussionmentioning

confidence: 99%

“…The measurement has been performed with a stack of fast ionization chambers in a common housing; this setup allowed the simultaneous measurement on several isotopes [21]. Each chamber consists of a central Al cathode 100 μm in thickness plated on both sides with sample material, and two 15 μm thick Al anodes at a distance of 5 mm from the cathode for the definition of the electric field.…”

Section: The Experimental Set-upmentioning

confidence: 99%

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Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

et al. 2013

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Abstract. The neutron-induced fission cross-section of 241 Am has been measured relative to the standard fission cross-section of 235 U between 0.5 and 20 MeV. The experiment was performed at the CERN n TOF facility. Fission fragments were detected by a fast ionization chamber by discriminating against the α-particles from the high radioactivity of the samples. The high instantaneous neutron flux and the low background of the n TOF facility enabled us to obtain uncertainties of ≈ 5%. With the present results it was possible to resolve discrepancies between previous data sets and to confirm current evaluations, thus providing important information for design studies of future reactors with improved fuel burn-up.

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“…From the performed Monte Carlo simulations [21] the efficiencies were found to be 50.7% and 45.3% for 241 Am and 235 U, respectively. The resulting efficiency correction is 5.4%.…”

Section: Discussionmentioning

confidence: 98%

Section: Discussionmentioning

confidence: 99%

Section: The Experimental Set-upmentioning

confidence: 99%

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Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

et al. 2013

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“…The detector and its performance are described in detail in Ref. [5]. It consists of a stack of ionization chambers, assembled along the direction of the neutron beam, thus allowing the simultaneous measurement on several isotopes.…”

Section: B Detector and Data Acquisitionmentioning

confidence: 99%

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C
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The 233 U(n,f ) cross section has been measured at the white neutron source n TOF in a wide energy range with a dedicated fission ionization chamber. We report here the results from ∼30 meV to 1 MeV neutron energy. The 233 U(n,f ) cross section has been determined relative to a reference sample of 235 U(n,f ) measured simultaneously with the same detector. The very high instantaneous neutron flux and the intrinsically low background of the n TOF installation result in an accuracy around 3% in the whole energy range, while the energy resolution of the neutron beam allows for an accurate description of the fission cross section by means of R-matrix analysis over a wide energy range. The results are, in general, in good agreement with the most recent high-accuracy measurement of this fission cross section, over the more limited range of the previous measurements, and indicated that even the latest evaluations underestimate the cross section in the epithermal region. The present high-quality data provide the basis for a more precise evaluation of the 233 U fission cross section and for improving the reliability of databases needed for the design of new energy systems based on the Th/U cycle.

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“…The CERN built a new ionization chamber with fast timing properties for the measuring of cross-section which particularly focused on fast time response, the good background rejection capability, low-background and high detection efficiency [9]. In this work we choose the 239 …”

Section: Introductionmentioning

confidence: 99%

Influence of thermal and resonance neutron on fast neutron flux measurement by ²³⁹ Pu fission chamber

Zeng¹,

Wang²,

Lingli³

et al. 2015

Chinese Phys. C

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Abstract:The 239 Pu fission chambers are widely used to measure fission spectrum neutron flux due to a flat response to fast neutrons. However, in the mean time the resonance and thermal neutrons can cause a significant influence on the measurement if they are moderated, which could be eliminated by using 10 B and Cd covers. At a column enriched uranium fast neutron critical assembly, the fission reaction rates of 239 Pu are measured as 1.791×10 -16 , 2.350×10 -16 and 1.385×10 -15 per second for 15mm thick 10 B cover, 0.5mm thick Cd cover, and no cover respectively. While the fission reaction rate of 239 Pu is rapidly increased to 2.569×10 -14 for a 20mm thick polythene covering fission chamber. The average 239 Pu fission cross-section of thermal and resonance neutrons is calculated to be 500b and 24.95b with the assumption of 1/v and 1/E spectra respectively, then thermal, resonance and fast neutron flux are achieved to be 2.30×10 6 , 2.24×10 6 and 1.04×10 8 cm -2 ·s -1 .

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A fast ionization chamber for fission cross-section measurements at n_TOF

Cited by 50 publications

References 20 publications

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C
Self Cite

Influence of thermal and resonance neutron on fast neutron flux measurement by ²³⁹ Pu fission chamber

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A fast ionization chamber for fission cross-section measurements at n_TOF

Cited by 50 publications

References 20 publications

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal toCalviani1, Praena2, Abbondanno3 et al. 2009Phys. Rev. CSelf Cite

Influence of thermal and resonance neutron on fast neutron flux measurement by 239 Pu fission chamber

Contact Info

Product

Resources

About

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C
Self Cite

Influence of thermal and resonance neutron on fast neutron flux measurement by ²³⁹ Pu fission chamber