A new approach to measuring fission cross-section ratios

Várnagy, M.; Csikai, J.

doi:10.1016/0029-554x(82)90115-x

Cited by 14 publications

(11 citation statements)

References 7 publications

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“…There are a number of cross-sectional data on the 237 Np(n,f ) reaction in the international database EXFOR [1], most using 235 U(n,f ) as reference [2][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18], as well as 237 Np/ 235 U fission cross-sectional ratios [19][20][21][22]. However, these data exhibit discrepancies that reach 8%, mainly at the first and second chance fission plateaus.…”

Section: Introductionmentioning

confidence: 99%

Neutron-induced fission cross section ofNp237in the keV to MeV range at the CERN n_TOF facility

Diakaki¹,

Karadimos²,

Vlastou³

et al. 2016

Phys. Rev. C

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The neutron-induced fission cross section of 237 Np was experimentally determined at the high-resolution and high-intensity facility n TOF, at CERN, in the energy range 100 keV to 9 MeV, using the 235 U(n,f) and 238 U(n,f) cross section standards below and above 2 MeV, respectively. A fast ionization chamber was used in order to detect the fission fragments from the reactions and the targets were characterized as far as their mass and homogeneity are concerned by means of α spectroscopy and Rutherford backscattering spectroscopy respectively. Theoretical calculations within the Hauser-Feshbach formalism have been performed, employing the EMPIRE code, and the model parameters were tuned in order to successfully reproduce the experimental fission cross-sectional data and simultaneously all the competing reaction channels.

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Section: Introductionmentioning

confidence: 99%

Neutron-induced fission cross section ofNp237in the keV to MeV range at the CERN n_TOF facility

Diakaki¹,

Karadimos²,

Vlastou³

et al. 2016

Phys. Rev. C

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“…The variables N 1 or N 1 /N 2 are often determined via α-counting measurements (α-count.) 1 [25,[29][30][31][32][33][37][38][39]43,45,46,49,50,53,60,61,63] independent from fission counting measurements as can be seen in Table 1. A 1% value is assumed as a conservative bound ∆(N 1 ) 1 across all measurements using α-counting to determine N 1 in 239 Pu samples following the literature of individual measurements and reference [24].…”

Section: Sub-process: Determining N 1 and Nmentioning

confidence: 99%

“…Usually, this correction is calculated [29,36,37,45,49,50,60] using stopping power data which lead to strong cross-correlations across measurements correcting for this effect. The stopping power was measured in two cases [36,63]. -The inherent fission fragment angular distribution (FF ∠) also needs to be corrected when assessing ε.…”

Section: Sub-process: Determining ε 1 ε 2 or δεmentioning

confidence: 99%

“…-The inherent fission fragment angular distribution (FF ∠) also needs to be corrected when assessing ε. This correction is usually calculated [25,31,33,37,59,60,63]. It was also measured in a few cases [45,60].…”

Section: Sub-process: Determining ε 1 ε 2 or δεmentioning

confidence: 99%

“…magnet) [59] and by design of the measurement at large (design) [60,67,80]. The remaining background is often measured [25,29,32,33,36,38,41,43,45,46,49,51,52,56,57,60,61,63,65,66,68,79,80]. Some of these measurements are with sample out (Sample out) [43,49,71,75], use various monochromatic filters (monomchrom.…”

Section: Sub-process: Determining C B1 and C B2mentioning

confidence: 99%

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Validating nuclear data uncertainties obtained from a statistical analysis of experimental data with the “Physical Uncertainty Bounds” method

Neudecker

White

Vaughan

et al. 2020

EPJ Nuclear Sci. Technol.

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Concerns within the nuclear data community led to substantial increases of Neutron Data Standards (NDS) uncertainties from its previous to the current version. For example, those associated with the NDS reference cross section 239Pu(n,f) increased from 0.6–1.6% to 1.3–1.7% from 0.1–20 MeV. These cross sections, among others, were adopted, e.g., by ENDF/B-VII.1 (previous NDS) and ENDF/B-VIII.0 (current NDS). There has been a strong desire to be able to validate these increases based on objective criteria given their impact on our understanding of various application uncertainties. Here, the “Physical Uncertainty Bounds” method (PUBs) by Vaughan et al. is applied to validate evaluated uncertainties obtained by a statistical analysis of experimental data. We investigate with PUBs whether ENDF/B-VII.1 or ENDF/B-VIII.0 239Pu(n,f) cross-section uncertainties are more realistic given the information content used for the actual evaluation. It is shown that the associated conservative (1.5–1.8%) and minimal realistic (1.1–1.3%) uncertainty bounds obtained by PUBs enclose ENDF/B-VIII.0 uncertainties and indicate that ENDF/B-VII.1 uncertainties are underestimated.

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Measurement of the fission cross section of238U and235U nuclei by 14 MeV neutrons

Goverdovskii¹,

Gordyushin²,

Kuz'minov³

et al. 1984

At Energy

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A new approach to measuring fission cross-section ratios

Cited by 14 publications

References 7 publications

Neutron-induced fission cross section ofNp237in the keV to MeV range at the CERN n_TOF facility

Neutron-induced fission cross section ofNp237in the keV to MeV range at the CERN n_TOF facility

Validating nuclear data uncertainties obtained from a statistical analysis of experimental data with the “Physical Uncertainty Bounds” method

Measurement of the fission cross section of238U and235U nuclei by 14 MeV neutrons

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