New feature of DARWIN/PEPIN2 inventory code: Propagation of nuclear data uncertainties to decay heat and nuclide density

Tsilanizara, A.; Huynh, T.D.

doi:10.1016/j.anucene.2021.108579

Cited by 11 publications

(2 citation statements)

References 8 publications

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“…Concentrations of 136 Cs were calculated for a typical light water reactor with two di↵erent fuels (UOX and MOX) and a burnup of 48 GWd/t. A sensitivity analysis was performed with the DARWIN package [1]. The results are shown in table 1.…”

Section: Introductionmentioning

confidence: 99%

Measurement of the fission yield of ¹³⁶Cs in the ²³⁹Pu(n_th,f) reaction

Chebboubi,

Bernard,

Vallet

et al. 2023

EPJ Web of Conf.

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A recent experimental campaign performed at the LOHENGRIN spectrometer at ILL aimed at measuring the independent fission yield of 136Cs in the 239Pu(nth,f) reaction. This nuclide can have an important contribution to the total dose rate coming from spent light water reactor UOX and MOX fuels. Moreover, its impact is of first order on the uncertainty of the total dose rate calculated in specific areas of Nuclear Power Plants within accidental conditions. One of the most important sources of uncertainty is its independent fission yield. Therefore, a new measurement of its independent yield along with a rigorous uncertainty analysis was performed. Due to its low independent yield, a new measurement technique has been applied. Ions recoiling from neutron-irradiated 239Pu target were collected by implantation into an Al foil placed inside a vacuum chamber. This foil was then transferred to a low γ-ray background setup located at nearby laboratory (LPSC). The procedure was then repeated for different LOHENGRIN settings. Compared to the JEFF-3.1.1 library, a decrease of the fission yield of 136Cs with a reduced uncertainty is obtained.

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Section: Introductionmentioning

confidence: 99%

Measurement of the fission yield of ¹³⁶Cs in the ²³⁹Pu(n_th,f) reaction

Chebboubi,

Bernard,

Vallet

et al. 2023

EPJ Web of Conf.

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“…Nuclear data are the basic input parameters of activation calculations, and their accuracy directly affects the activation calculation results (Liem and Sembiring, 2013;Tsilanizara and Huynh, 2021). Uncertainties are unavoidable when nuclear data are obtained through experimental measurements (Awan et al, 2012;Katakura, 2013), and nuclear data uncertainties are propagated in activation calculations, which eventually affect the accuracy of activation calculation results.…”

Section: Introductionmentioning

confidence: 99%

Uncertainty Analysis of Reactor Structure Material Activation Calculation Induced From Nuclear Data

Jiebo

Yang

et al. 2022

Front. Energy Res.

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Highly accurate activation calculations are the basis of radiation protection optimization design, and the accuracy of activation calculations depends on nuclear data. Based on the ENDF/B-VIII.0 and JEFF3.3 decay evaluation libraries, the influence of different nuclear data on the reactor structural material activation calculation is analyzed, and the nuclear data-related sensitivity and uncertainty quantification of radioactivity, decay heat and photon sources are carried out by the global sensitivity analysis method and the Latin Hypercube Sampling method. Based on uncertainty data in ENDF/B-VIII.0 and JEFF3.3, quantifying the uncertainty of radioactivity, decay heat and photon source in the shutdown dose calculation of reactor structural materials, the maximum uncertainty of radioactivity and decay heat reach 4.54 and 1.45%, respectively. The half-life and decay energy of 55Fe are the main sources of uncertainty.

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The spectrum-averaged cross section investigation of 117Sn(n,n')117mSn and 67Zn(n,p)67Cu reactions

Krechlerová,

Košťál,

Losa

et al. 2024

Applied Radiation and Isotopes

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New feature of DARWIN/PEPIN2 inventory code: Propagation of nuclear data uncertainties to decay heat and nuclide density

Cited by 11 publications

References 8 publications

Measurement of the fission yield of ¹³⁶Cs in the ²³⁹Pu(n_th,f) reaction

Measurement of the fission yield of ¹³⁶Cs in the ²³⁹Pu(n_th,f) reaction

Uncertainty Analysis of Reactor Structure Material Activation Calculation Induced From Nuclear Data

The spectrum-averaged cross section investigation of 117Sn(n,n')117mSn and 67Zn(n,p)67Cu reactions

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New feature of DARWIN/PEPIN2 inventory code: Propagation of nuclear data uncertainties to decay heat and nuclide density

Cited by 11 publications

References 8 publications

Measurement of the fission yield of 136Cs in the 239Pu(nth,f) reaction

Measurement of the fission yield of 136Cs in the 239Pu(nth,f) reaction

Uncertainty Analysis of Reactor Structure Material Activation Calculation Induced From Nuclear Data

The spectrum-averaged cross section investigation of 117Sn(n,n')117mSn and 67Zn(n,p)67Cu reactions

Contact Info

Product

Resources

About

Measurement of the fission yield of ¹³⁶Cs in the ²³⁹Pu(n_th,f) reaction

Measurement of the fission yield of ¹³⁶Cs in the ²³⁹Pu(n_th,f) reaction