Measurements and Computation of the Reactivity Effects of Accident-Caused Core Distortions in Liquid-Metal Fast Breeder Reactors

Helm, F.; Henneges, G.; Maschek, W.

doi:10.13182/nse84-a17784

Cited by 9 publications

(5 citation statements)

References 5 publications

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“…5. The extrapolated ERANOS results then exhibit similar behavior observed in the Helm's original SNEAK-12A analysis with SIMMER-II[20] transport calculation as seen inFig. 8.…”

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confidence: 77%

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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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“…5. The extrapolated ERANOS results then exhibit similar behavior observed in the Helm's original SNEAK-12A analysis with SIMMER-II[20] transport calculation as seen inFig. 8.…”

supporting

confidence: 77%

“…In the case of the SNEAK-12A core the material volume fractions of the fuel, steel and sodium corresponded approximately to those of the SNR-300 reactor [20].…”

Section: Sneak-12a-benchmark Specificationmentioning

confidence: 79%

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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 SNEAK-12A experimental program ( Helm & Henneges (1985); Helm et al (1984); Margulis et al (2016a,b)) operated during the 80s in the Karlsruhe center (KfK). The aim of the program was to study neutronic behavior during large material relocation inside a hypothetical liquid-metal fast breeder reactor (LMFBR) configuration.…”

mentioning

confidence: 99%

“…The experimental programs included experiments such as -structure material relocation, fuel slump-in and slump-out, fuel compaction of different magnitudes and radial molten pool expansion. Those experiments were utilized for code validation like SIMMER ( Helm et al (1984)) and Monte Carlo based codes -Serpent, Tripoli and MCNP ( Margulis et al (2016a,b)).…”

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confidence: 99%

The path for innovative severe accident neutronics studies in ZPRs. part I.2 - Interpretation of SNEAK-12A experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients

Margulis

Blaise

Mellier

et al. 2017

Progress in Nuclear Energy

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The present work details a further investigation of the SNEAK-12A experimental program, which aimed to study material relocation in Sodium Fast Reactors (SFRs) leading to core degradation. The further investigation include sensitivity and uncertainty propagation analysis. In this paper, a comparison is made using two codes, a Monte Carlo based code Serpent 2 and the deterministic system code ERANOS. A sensitivity analysis was made utilizing the two codes, with comparison of two nuclear data libraries (ENDF/B-VII.1 and JEFF-3.1.1). The code-to-code comparison resulted in a very good agreement, while the comparison of libraries showed large discrepancies, manly due to the differences in the sodium cross-section data. The sensitivity analysis, was followed by a complete propagated uncertainty analysis based on the covariance evaluated data available in the COMAC data evaluation. The results of the uncertainties show that there are still large discrepancies linked to the nuclear data. This work is done within the frame work of new core design capacities and new ways of conducting in Zero Power Reactors, such as the ZEPHYR project led independently by CEA.

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Some remarks on 3D transport method needs and trends for development

Palmiotti

Salvatores

1991

Progress in Nuclear Energy

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Measurements and Computation of the Reactivity Effects of Accident-Caused Core Distortions in Liquid-Metal Fast Breeder Reactors

Cited by 9 publications

References 5 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. part I.2 - Interpretation of SNEAK-12A experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients

Some remarks on 3D transport method needs and trends for development

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