Neutron-induced fission cross sections of 242Pu and 244Pu

Auchampaugh, G.F.; Farrell, J.A.; Bergen, D.W.

doi:10.1016/0375-9474(71)90360-5

Cited by 56 publications

(12 citation statements)

References 13 publications

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“…This also applies to the data of Meadows [14]. Bergen [15], Salvador-Castiñeira [10], Auchampaugh [17] and Weigmann [16] agree with our data within the error bars. The lower panel of Fig.…”

Section: Resultssupporting

confidence: 77%

Neutron induced fission cross section measurements of²⁴⁰Pu and²⁴²Pu

et al. 2017

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Abstract. Accurate neutron induced fission cross section of 240 Pu and 242 Pu are required in view of making nuclear technology safer and more efficient to meet the upcoming needs for the future generation of nuclear power plants (GEN-IV). The probability for a neutron to induce such reactions figures in the NEA Nuclear Data High Priority Request List [1].A measurement campaign to determine neutron induced fission cross sections of 240 Pu and 242 Pu at 2.51 MeV and 14.83 MeV has been carried out at the 3.7 MV Van De Graaff linear accelerator at PhysikalischTechnische Bundesanstalt (PTB) in Braunschweig. Two identical Frisch Grid fission chambers, housing back to back a 238 U and a A Pu target (A = 240 or A = 242), were employed to detect the total fission yield. The targets were molecular plated on 0.25 mm aluminium foils kept at ground potential and the employed gas was P10. The neutron fluence was measured with the proton recoil telescope (T1), which is the German primary standard for neutron fluence measurements. The two measurements were related using a De Pangher long counter and the charge as monitors. The experimental results have an average uncertainty of 3-4% at 2.51 MeV and for 6-8% at 14

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Section: Resultssupporting

confidence: 77%

Neutron induced fission cross section measurements of²⁴⁰Pu and²⁴²Pu

et al. 2017

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“…Besides that, above 1 MeV two groups of data sets can be distinguished. The first one being the values of Weigmann et al (1984) [7] and the second a subset of the other data sets Bergen and Fullwood (1970) [8], Auchampaugh et al (1971) [9], Meadows (1978) [10], Staples and Morley (1998) [11], and Tovesson et al (2009) [12]). Nevertheless, the two groups are converging at neutron energies above 2.5 MeV.…”

Section: Introductionmentioning

confidence: 99%

“…The ENDF/B-VII.1 evaluation follows perfectly the JENDL 4.0. The experimental data sets shown are Butler (1960) [5] (open crosses), Fomushkin and Gutnikova (1970) [6] (open stars), Bergen and Fullwood (1970) [8] (open circles), Auchampaugh et al (1971) [9] (open diamonds), Meadows (1978) [10] (open up triangles), Weigmann et al (1984) [7] (full squares), Staples and Morley (1998) [11] (open down triangles), and Tovesson et al (2009) [12] (full circles). Selected data are shown for visibility of the plot.…”

Section: Introductionmentioning

confidence: 99%

Neutron-induced fission cross sections ofPu242from 0.3 MeV to 3 MeV

et al. 2015

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The majority of the next generation of nuclear power plants (GEN-IV) will work in the fast-neutron-energy region, as opposed to present day thermal reactors. This leads to new and more accurate nuclear-data needs for some minor actinides and structural materials. Following those upcoming demands, the Organisation for Economic Cooperation and Development Nuclear Energy Agency performed a sensitivity study. Based on the latter, an improvement in accuracy from the present 20% to 5% is required for the 242 Pu(n,f) cross section. Within the same project both the 240 Pu(n,f) cross section and the 242 Pu(n,f) cross section were measured at the Van de Graaff accelerator of the Joint Research Centre at the Institute for Reference Materials and Measurements, where quasimonoenergetic neutrons were produced in an energy range from 0.3 MeV up to 3 MeV. A twin Frisch-grid ionization chamber has been used in a back-to-back configuration as fission-fragment detector. The 242 Pu(n,f) cross section has been normalized to three different isotopes: 237 Np(n,f), 235 U(n,f), and 238 U(n,f). A comprehensive study of the corrections applied to the data and the uncertainties associated is given. The results obtained are in agreement with previous experimental data at the threshold region up to 0.8 MeV. The resonance-like structure at 0.8 to 1.1 MeV, visible in the evaluations and in most previous experimental values, was not reproduced with the same intensity in this experiment. For neutron energies higher than 1.1 MeV, the results of this experiment are slightly lower than the Evaluated Nuclear Data File/B-VII.1 evaluation but in agreement with the experiment of Tovesson et al. (2009) as well as Staples and Morley (1998). Finally, for energies above 1.5 MeV, the results show consistency with the present evaluations.

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“…However, in EXFOR, no data set covering the entire RRR is available. The only data available are those of Bergen et al [7], starting at 50 eV, and those of Auchampaugh et al [8] starting at 200 eV. For this reason, our reference will be the JEFF3.3 evaluation [6], based on the Weigmann et al data [1] which are missing in EXFOR below 300 keV.…”

Section: Identification and Parametrizationmentioning

confidence: 99%

“…Two data sets are available in EXFOR covering the entire URR. As the data from Auchaupaugh et al [8] show the best energy resolution, this data-set will be used in this work. They are presented with their uncertainties in Fig.…”

Section: Identificationmentioning

confidence: 99%

Re-examining intermediate resonant structures in the ²⁴²Pu fission cross section

et al. 2023

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The study of the 242Pu fission cross section has become more important since this isotope is present in Pressurized Water Reactor Uranium Oxide and Mixed Oxide fuel, as well as in fast neutron reactors fuel. This nucleus has been also selected for monitoring the high neutron flux RJH reactor (CEA-Cadarache). For all these reasons, the fission cross section structure of this fertile isotope, and especially its class-II states resonances were investigated in this work. Two class-II states have been identified in the Resolved Resonance Range (RRR) and their parameters have been supplied to the CONRAD code. 68 class- II states have been identified in the Unresolved Resonant Range (URR) and their parameters have been added in the TALYS code data library to reproduce as well as possible the experimental fission cross section. The methodology to identify and insert the class-II states in RRR and URR is described here.

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Neutron-induced fission cross sections of 242Pu and 244Pu

Cited by 56 publications

References 13 publications

Neutron induced fission cross section measurements of²⁴⁰Pu and²⁴²Pu

Neutron induced fission cross section measurements of²⁴⁰Pu and²⁴²Pu

Neutron-induced fission cross sections ofPu242from 0.3 MeV to 3 MeV

Re-examining intermediate resonant structures in the ²⁴²Pu fission cross section

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Neutron-induced fission cross sections of 242Pu and 244Pu

Cited by 56 publications

References 13 publications

Neutron induced fission cross section measurements of240Pu and242Pu

Neutron induced fission cross section measurements of240Pu and242Pu

Neutron-induced fission cross sections ofPu242from 0.3 MeV to 3 MeV

Re-examining intermediate resonant structures in the 242Pu fission cross section

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Product

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Neutron induced fission cross section measurements of²⁴⁰Pu and²⁴²Pu

Neutron induced fission cross section measurements of²⁴⁰Pu and²⁴²Pu

Re-examining intermediate resonant structures in the ²⁴²Pu fission cross section