Nuclear data sensitivity, uncertainty and target accuracy assessment for future nuclear systems

Aliberti, G.; Palmiotti, G.; Salvatores, M.; Kim, T.K.; Taiwo, T. A.; Anitescu, Mihai; Kodeli, I.; Sartori, Enrico; Bosq, J. C.; Tommasi, J.

doi:10.1016/j.anucene.2006.02.003

Cited by 211 publications

(135 citation statements)

References 9 publications

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“…The two measurements are in good agreement with each other for [5][6][7][8][9][10][11][12][13][14][15][16][17][18][19][20] MeV and the averaged cross section agrees well with previous, direct, measurements in the 5-10 MeV range; it is somewhat higher (by less than 20%) than those at about 15 MeV. The ratio measurement does not, and is not expected to, produce highly-accurate fission results at low energies (< 5 MeV here), due to the underlying Weisskopf-Ewing assumption.…”

Section: Neutron-induced Fission Reactionssupporting

confidence: 72%

“…First, the level of precision required for the cross section is often higher than in the fission case: Recent advances in modeling the astrophysical s process have resulted in requests to determine capture cross sections within a few percent and nuclear-energy applications require cross sections to within 5-10% [18,19]. Achieving an accuracy of a few percent is challenging, but constraining an unknown (n,γ) cross section to within 20-30% should be considered a meaningful improvement of the situation, in particular since current cross section evaluations often show large deviations from each other.…”

Section: Capture Reactionsmentioning

confidence: 99%

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Neutron-capture cross sections from indirect measurements

Escher

Burke

Dietrich

et al. 2012

EPJ Web of Conferences

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Abstract.Cross sections for compound-nuclear reactions reactions play an important role in models of astrophysical environments and simulations of the nuclear fuel cycle. Providing reliable cross section data remains a formidable task, and direct measurements have to be complemented by theoretical predictions and indirect methods. The surrogate nuclear reactions method provides an indirect approach for determining cross sections for reactions on unstable isotopes, which are difficult or impossible to measure otherwise. Current implementations of the method provide useful cross sections for (n,f) reactions, but need to be improved upon for applications to capture reactions.

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Section: Neutron-induced Fission Reactionssupporting

confidence: 72%

Section: Capture Reactionsmentioning

confidence: 99%

Neutron-capture cross sections from indirect measurements

Escher

Burke

Dietrich

et al. 2012

EPJ Web of Conferences

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“…The recent interest in new Generation-IV nuclear reactor designs, many of which utilize fast neutrons [1], has increased the need for accurate data for neutron-induced reactions. Cross-section data, even of minor actinides, may alter reactor neutronics and burnup and are needed to engineer safer and more proliferation-resistant reactors.…”

Section: Introductionmentioning

confidence: 99%

Determining the239Np(n,f)cross section using the surrogate ratio method

et al. 2013

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Background: Neutron-induced fission cross-section data are needed in various fields of applied and basic nuclear science. However, cross sections of short-lived nuclei are difficult to measure directly due to experimental constraints. Purpose: The first experimental determination of the neutron-induced fission cross section of 239 Np at nonthermal energies was performed. This minor actinide is the waiting point to 240 Pu production in a nuclear reactor. Method: The surrogate ratio method was employed to indirectly deduce the 239 Np(n, f ) cross section. The surrogate reactions used were 236 U( 3 He, p) and 238 U( 3 He, p) with the reference cross section given by the well-known 237 Np(n, f ) cross section. The ratio of observed fission reactions resulting from the two formed compound nuclei, 238 Np and 240 Np, was multiplied by the directly measured 237 Np(n, f ) cross section to determine the 239 Np(n, f ) cross section. Results: The 239 Np(n, f ) cross section was determined with an uncertainty ranging between 4% and 30% over the energy range of 0.5-20 MeV. The resulting cross section agrees closest with the JENDL-4.0 evaluation. Conclusions:The measured cross section falls in between the existing evaluations, but it does not match any evaluation exactly (with JENDL-4.0 being the closest match); hence reactor codes relying on existing evaluations may under-or overestimate the amount of 240 Pu produced during fuel burnup. The measurement helps constrain nuclear structure parameters used in the evaluations.

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“…Two Na-cooled FRs with different core sizes and MA ÓAtomic Energy Society of Japan contents have been analyzed, 5) namely, SFR, i.e., a burner fast reactor, with a MA/Pu ratio that is approximately equal to $0:1 and a CR $ 0:20, and a standard large fast reactor (EFR) with a limited content of MA in the fuel, equivalent to the equilibrium value. A summary of the two core characteristics is given below and the respective TRU compositions are given in Table 1 Na void reactivity, Doppler coefficients, and effective delayed neutron fraction have been calculated with the ERANOS code system.…”

Section: Systems Considered and Reference Parametersmentioning

confidence: 99%

Impact of the Core Minor Actinide Content on Fast Reactor Reactivity Coefficients

Palmiotti¹,

Salvatores²,

Assawaroongruengchot³

2011

Journal of Nuclear Science and Technology

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A major challenge for future fast reactors could be the recycling of minor actinides (MAs) in the core fuel in order to minimize waste and to meet both the sustainability objective and the reduction in the burden of geological disposal. Although the prevailing issues will be found in the development and validation of the appropriate fuels, the presence of MAs in the core can deteriorate the core reactivity coefficients. However, in this paper, we will show that there is no well-defined physical limit to the amount of MAs in the core fuel, and that a careful physics analysis can indicate the most appropriate measures that reduce the MA impact on the reactivity coefficients, and in particular, for Na-cooled reactors, on the Na void reactivity coefficient.

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Nuclear data sensitivity, uncertainty and target accuracy assessment for future nuclear systems

Cited by 211 publications

References 9 publications

Neutron-capture cross sections from indirect measurements

Neutron-capture cross sections from indirect measurements

Determining the239Np(n,f)cross section using the surrogate ratio method

Impact of the Core Minor Actinide Content on Fast Reactor Reactivity Coefficients

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