Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I

Delipei, Gregory; Hou, Jason; Avramova, Maria; Rouxelin, Pascal; Ivanov, Kostadin

doi:10.1016/j.nucengdes.2021.111474

Cited by 9 publications

(5 citation statements)

References 5 publications

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“…For the k eff , we see that the 235 U νp at low energies is the most significant input. This is in line with results from the LWR-UAM Phase I benchmark for steady state [40], since the νp has a direct contribution to the produced neutrons and thus to the k eff . The positive correlation is reasonable, since an increase of the νp will lead to an increase of the neutron population and then a higher k eff .…”

Section: Resultssupporting

confidence: 90%

“…The results for the scalar outputs of interest are shown in Figure 14. The k eff shows an uncertainty of 0.44%, which is a result in the same range of that found in the literature for typical LWR uncertainty quantification studies (0.5%) such as in [40]. Small uncertainties of 0.81% and 0.37% are obtained for P max lin and D min cool , respectively.…”

Section: Resultssupporting

confidence: 84%

“…With a similar reasoning, we analyze the cross-section correlations for P max lin , where we can see a very strong correlation for the 238 U elastic and inelastic scattering at high energies (above 1 MeV). From these two cross-sections, the inelastic scattering of 238 U is a quantity that has been shown to be one of the dominant inputs in uncertainty quantification studies such as in the LWR-UAM Phase I benchmark [40]. For the elastic cross-section, we have little information, but as we can see in Figure 16, it is strongly negatively correlated with the inelastic scattering of 238 U for this specific high-energy group.…”

Section: Resultsmentioning

confidence: 96%

“…Radial and axial reflector libraries were generated based on the LWR-UAM-Phase I specifications [40]. The radial reflector is constructed with three slabs neighboring a fuel assembly (Figure 12a).…”

Section: Modelingmentioning

confidence: 99%

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CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification

et al. 2022

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Best Estimate Plus Uncertainty (BEPU) approaches for nuclear reactor applications have been extensively developed in recent years. The challenge for BEPU approaches is to achieve multi-physics modeling with an acceptable computational cost while preserving a reasonable fidelity of the physics modeled. In this work, we present the core multi-physics computational framework developed for the efficient computation of uncertainties in Light Water Reactor (LWR) simulations. The subchannel thermal-hydraulic code CTF and the nodal expansion neutronic code PARCS are coupled for the multi-physics modeling (CTF-PARCS). The computational framework is discussed in detail from the Polaris lattice calculations up to the CTF-PARCS coupling approaches. Sampler is used to perturb the multi-group microscopic cross-sections, fission yields and manufacturing parameters, while Dakota is used to sample the CTF input parameters and the boundary conditions. Python scripts were developed to automatize and modularize both pre- and post-processing. The current state of the framework allows the consistent perturbation of inputs across neutronics and thermal-hydraulics modeling. Improvements to the standard thermal-hydraulics modeling for such coupling approaches have been implemented in CTF to allow the usage of 3D burnup distribution, calculation of the radial power and the burnup profile, and the usage of Santamarina effective Doppler temperature. The uncertainty quantification approach allows the treatment of both scalar and functional quantities and can estimate correlation between the multi-physics outputs of interest and up to the originally perturbed microscopic cross-sections and yields. The computational framework is applied to three exercises of the LWR Uncertainty Analysis in Modeling Phase III benchmark. The exercises cover steady-state, depletion and transient calculations. The results show that the maximum fuel centerline temperature across all exercises is 2474K with 1.7% uncertainty and that the most correlated inputs are the 238U inelastic and elastic cross-sections above 1 MeV.

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Section: Resultssupporting

confidence: 90%

Section: Resultssupporting

confidence: 84%

Section: Resultsmentioning

confidence: 96%

Section: Modelingmentioning

confidence: 99%

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CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification

et al. 2022

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“…When considering the presented results, it is useful to keep in mind results usually obtained for the same quantities in LWR analysis. A k eff uncertainty between 0.5% for fresh fuel and 0.8% for depleted fuel, and a fuel Doppler coefficient uncertainty between 1.2% and 1.8% is usually obtained (Aures et al, 2017;Delipei et al, 2021). Key contributors to these uncertainties are 238 U and 239 Pu radiative capture, as well as 235 U and 239 Pu neutron multiplicity.…”

Section: Nuclear Data Uncertainty Propagationmentioning

confidence: 99%

Key nuclear data for non-LWR reactivity analysis

2023

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An assessment of nuclear data performance for non-light-water reactor (non-LWR) reactivity calculations was performed at Oak Ridge National Laboratory that involved a thorough literature review to collect related observations made across different research institutions, an interrogation of the latest ENDF/B evaluated nuclear data libraries, and propagation of nuclear data uncertainties to key figures of merit associated with reactor safety for six non-LWR benchmarks. The outcome of this comprehensive study was published in a technical report issued by the US Nuclear Regulatory Commission. This paper provides a summary of the study’s key observations and conclusions and demonstrates with two examples how the various methods available in the SCALE code system were used to identify key cross section uncertainties for non-LWR reactivity analyses.

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Nuclear data uncertainty influence on the breeding ratio in sodium-cooled fast reactor systems

Ryzhkov

Тихомиров

Ternovykh

2023

Annals of Nuclear Energy

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Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I

Cited by 9 publications

References 5 publications

CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification

CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification

Key nuclear data for non-LWR reactivity analysis

Nuclear data uncertainty influence on the breeding ratio in sodium-cooled fast reactor systems

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