Validation of Neutronic Codes for Distorted Core Configurations with the SNEAK-12 Critical Assemblies

Henneges, G.

doi:10.13182/nse88-a29045

Cited by 3 publications

(2 citation statements)

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“…Severe core accident (SCA) in Liquid Metal-cooled Fast Breeder Reactors (LMFBRs) could occur either due to prompt or super-prompt recriticality or serious loss of heat sink [1]. The progression of a SCA in fast breeder reactors (FBRs) is significantly influenced by the core physics, which is the primary focus of the SNEAK-12A experimental series [2][3][4], since the core is not assembled in its most reactive configuration. Hence, redistribution processes of core materials (fuel, sodium, absorbers, or structural materials) can potentially lead to severe power excursion.…”

Section: Introductionmentioning

confidence: 99%

“…Furthermore, the validation of computational tools against experimental measurements of critical assemblies that represent different stages of the disrupted core configurations is mandatory for evaluating the code performances and quantify any discrepancies between experiment and theory. This paper presents a new benchmark problem based on the SNEAK-12A critical assembly experiments [2,3].…”

Section: Introductionmentioning

confidence: 99%

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The path for innovative severe accident neutronics studies in ZPRs. Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs

Margulis

Blaise

Gabrielli

et al. 2017

Progress in Nuclear Energy

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The present work details a new benchmark to be produced to the International Community, for dealing with neutronics code validation in the frame of SFRs (Sodium Fast Reactors) severe accidents sequences leading to core degradation and material relocation. The benchmark is based on a complete re-analysis of the SNEAK-12A experimental program, using TRIPOLI-4, MCNP and Serpent-2 Monte Carlo codes as reference tools, and the ERANOS system of codes for deterministic calculations, all based on JEFF-3.1.1 nuclear data libraries. The complete material balance is resumed, and the main degradation sequences are detailed. Preliminary results on available experimental results (k eff) are given, and additional local quantities are calculated, such as axial flux distributions, as well as detector responses in function of the distance to the degraded part. The benchmark offers an excellent opportunity to validate calculation schemes for strongly heterogeneous interfaces, in particular the preparation of homogenized and condensed cross sections for deterministic core calculations, as well as leakage treatment in locally very heterogeneous media. This work is made within the frame of new core design capacities and new ways of conducting experiment in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. The present analysis will be completed by a full nuclear data sensitivity and uncertainty analysis of the reactivity coefficients in a companion paper.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

The path for innovative severe accident neutronics studies in ZPRs. Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs

Margulis

Blaise

Gabrielli

et al. 2017

Progress in Nuclear Energy

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The path for innovative severe accident neutronics studies in ZPRs – Analysis of SNEAK-12B experiments for core disruption in LMFBRs

Margulis

Blaise

Gabrielli

et al. 2019

Annals of Nuclear Energy

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A higher order hexagonal-z nodal transport method

Velde

Beauwens

1995

Transport Theory and Statistical Physics

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A higher order one-dimensional transport solution module based on the boundary sources method is implemented in Wagner's (hexagonal-z nodal) code HEXNOD. We first describe and slightly simplify Wagner's nodal technique for reducing the multidimensional transport equation to a set of coupled one-dimensional equations, taking this opportunity to stress that nodal engineering methods of this type make use of a nonltnear (actually affine) approximation to the nodal response. We next summarize the basics of the boundary sources method, whose combined use with Wagner's nodal approach leads to the new HEXBS method.Numerical results reported for a series of benchmark problems show that the new method is more accurate that the original one and that it successfully applies to distorted core configurations. On the other hand, it is somewhat slower than the original method but this may be ascribed to the fact that the present version is far from optimized.

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Validation of Neutronic Codes for Distorted Core Configurations with the SNEAK-12 Critical Assemblies

Cited by 3 publications

References 0 publications

The path for innovative severe accident neutronics studies in ZPRs. Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs

The path for innovative severe accident neutronics studies in ZPRs. Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs

The path for innovative severe accident neutronics studies in ZPRs – Analysis of SNEAK-12B experiments for core disruption in LMFBRs

A higher order hexagonal-z nodal transport method

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