Search results for: H. Ferroukhi

Items from 1 to 20 out of 30 results

article

Correlation $\overline{\nu}_{p} - \sigma$ ν ¯ p - σ for U-Pu in the thermal and resonance neutron range via integral information

D. Rochman, A. Vasiliev, H. Ferroukhi, S. Pelloni, more

The European Physical Journal Plus > 2019 > 134 > 9 > 1-12

. This paper presents an application of the Backward-Forward Monte Carlo (BFMC) method using measured critical boron concentrations for a specific PWR cycle. The considered prior nuclear data are the fission cross sections, $\overline{\nu}_{p}$ ν ¯ p for ²³⁵U and ²³⁹Pu and the capture cross section of ²³⁸U. The posterior nuclear data exhibit cross-isotope correlations, moderate changes for...

article

Monte Carlo nuclear data adjustment via integral information

D. Rochman, E. Bauge, A. Vasiliev, H. Ferroukhi, more

The European Physical Journal Plus > 2018 > 133 > 12 > 1-23

. In this paper, we present three Monte Carlo methods to include integral benchmark information into the nuclear data evaluation procedure: BMC, BFMC and Mocaba. They allow to provide posterior nuclear data and their covariance information in a Bayesian sense. Different examples will be presented, based on 14 integral quantities with fast neutron spectra (k_eff and spectral indices). Updated nuclear...

article

Consistent criticality and radiation studies of Swiss spent nuclear fuel: The CS2M approach

D. Rochman, A. Vasiliev, H. Ferroukhi, M. Pecchia

Journal of Hazardous Materials > 2018 > 357 > C > 384-392

In this paper, a new method is proposed to systematically calculate at the same time canister loading curves and radiation sources, based on the inventory information from an in-core fuel management system. As a demonstration, the isotopic contents of the assemblies come from a Swiss PWR, considering more than 6000 cases from 34 reactor cycles. The CS₂M approach consists in combining four codes: CASMO...

article

Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments

A. Dokhane, G. Grandi, A. Vasiliev, D. Rochman, more

Annals of Nuclear Energy > 2018 > 118 > C > 178-184

This research aims at validating the SIMULATE-3K code and complementing the results with the quantification of nuclear data uncertainties against the Special Power Excursion Reactor Test III (SPERT-III) experiments. To that aim, the SHARK-X methodology, under development at PSI, for the propagation of nuclear data uncertainties in CASMO5 2-D lattice calculations to 3-D core transient simulations is...

article

Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores

J. Li, D. Rochman, A. Vasiliev, H. Ferroukhi, more

Annals of Nuclear Energy > 2017 > 110 > C > 1023-1029

Fuel assembly bowing effects on isotopic concentrations during depletion are investigated for a range of full-scale fuel assembly bow models for Simplified Pressurized Water Reactor (PWR) assemblies and full cores. First, two-dimensional (2D) 3×3 assembly arrays with a central fuel assembly displaced are simulated using both CASMO-5 and SERPENT-2. Investigations are carried out on burn-up evolutions...

article

Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles

O. Leray, H. Ferroukhi, M. Hursin, A. Vasiliev, more

Annals of Nuclear Energy > 2017 > 110 > C > 547-559

At the Paul Scherrer Institut, the development of the SHARK-X methodology to propagate nuclear data uncertainties in CASMO-5 2-D assembly depletion calculations started few years ago. Before that, the CMSYS platform had been established to serve as framework for the continuous development and validation of core models based on CASMO/SIMULATE for all the Swiss operating reactors and cycles. Recently,...

article

Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly

O. Leray, L. Fiorito, D. Rochman, H. Ferroukhi, more

Progress in Nuclear Energy > 2017 > 101 > PC > 486-495

The assessment of the fission yield uncertainties on neutronic parameters is of great interest for criticality and spent fuel behavior studies. In this work, several fission yield perturbation methodologies are used to propagate the uncertainties for a PWR fuel assembly. Aside from the TENDL-2011 fission yields, a Generalized Least Square method is used on the JEFF-3.1.1 and the ENDF/B-VII.1 fission...

article

Testing the NURESIM platform on a PWR main steam line break benchmark

S. Kliem, Y. Kozmenkov, J. Hadek, Y. Perin, more

Nuclear Engineering and Design > 2017 > 321 > C > 8-25

Within the NURESAFE project, a main steam line break benchmark has been defined and solved by codes integrated into the European code platform NURESIM. The paper describes the results of the calculations for this benchmark. Six different solutions using different codes and code systems are provided for the comparison. The quantitative differences in the results are dominated by the differences in...

article

UO2 fuel pin bowing effects on isotopic concentrations

J. Li, D. Rochman, J. Herrero, A. Vasiliev, more

Annals of Nuclear Energy > 2017 > 105 > C > 361-368

The effects of the fuel pin bowing are simulated in a 3×3 pin-cells lattice to assess the possible modeling biases on isotopic concentrations during depletion calculations. The central pin in the lattice is modeled with a deformation and as a function of burn-up, characterized by a displacement in the two-dimensional (2D) lattice and a C-shape bowing in the three-dimensional (3D) lattice. The relative...

article

Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone

A. Dokhane, J. Judd, I. Gajev, O. Zerkak, more

Annals of Nuclear Energy > 2017 > 102 > C > 190-199

With the goal to enhance the capability to perform best-estimate simulations of Light Water Reactors (LWRs) transients, with strong coupling between core neutronics and plant thermal-hydraulic, a coupling between TRACE and SIMULATE-3K (TS3K) was developed in collaboration between PSI and Studsvik for analyses involving interactions between system and core. In order to verify the coupling scheme and...

article

Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19

M. Hursin, S. Bogetic, A. Dohkane, S. Canepa, more

Annals of Nuclear Energy > 2017 > 101 > C > 559-575

The paper deals with the development of a TRACE/PARCS plenum to plenum model for the Swiss Boiling Water Reactor (BWR) Leibstadt (KKL), for cycle 19. It summarizes a verification of the model against an existing SIMULATE-3 model and a validation against Travelling Incore Probes (TIP) at various points of the cycle 19.First, the TRACE/PARCS agreement with SIMULATE-3, for a simplified BWR reactor is...

article

Radiative neutron capture: Hauser Feshbach vs. statistical resonances

D. Rochman, S. Goriely, A.J. Koning, H. Ferroukhi

Physics Letters B > 2017 > 764 > C > 109-113

The radiative neutron capture rates for isotopes of astrophysical interest are commonly calculated on the basis of the statistical Hauser Feshbach (HF) reaction model, leading to smooth and monotonically varying temperature-dependent Maxwellian-averaged cross sections (MACS). The HF approximation is known to be valid if the number of resonances in the compound system is relatively high. However, such...

article

Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core

D. Rochman, O. Leray, M. Hursin, H. Ferroukhi, more

Nuclear Data Sheets > 2017 > 139 > C > 1-76

The impact of the current nuclear data library covariances such as in ENDF/B-VII.1, JEFF-3.2, JENDL-4.0, SCALE and TENDL, for relevant current reactors is presented in this work. The uncertainties due to nuclear data are calculated for existing PWR and BWR fuel assemblies (with burn-up up to 40 GWd/tHM, followed by 10 years of cooling time) and for a simplified PWR full core model (without burn-up)...

article

Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K

A. Dokhane, H. Ferroukhi, A. Pautz

Annals of Nuclear Energy > 2016 > 96 > C > 344-353

The OECD/NEA recently launched an international benchmark on a combined feedwater transient and stability event that occurred at the Swedish Oskarshamn-2 (O2) nuclear power plant (NPP). The primary benchmark objective is to assess advances in coupled neutronic/thermal–hydraulic codes for simulations of challenging transients including the appearance of unstable power oscillations. The Paul Scherrer...

article

A Bayesian Monte Carlo method for fission yield covariance information

D. Rochman, O. Leray, A. Vasiliev, H. Ferroukhi, more

Annals of Nuclear Energy > 2016 > 95 > C > 125-134

The present work proposes a Bayesian method to combine theoretical fission yields with a set of reference data. These two sources of information are merged using a Monte Carlo process, and leads to a so-called Bayesian Monte Carlo update. Examples are presented for the independent fission yields of four major actinides, using the GEF code as a source of theoretical calculations and an evaluated library...

article

Re-evaluation of the thermal neutron capture cross section of 147Nd

D. Rochman, O. Leray, G. Perret, A. Vasiliev, more

Annals of Nuclear Energy > 2016 > 94 > C > 612-617

In this paper we are proposing a re-evaluation of the thermal-neutron induced capture cross section of ¹⁴⁷Nd. A unique measurement exists from which this cross section was calculated in 1974. This original calculation is based on an assumed value for a specific gamma-ray fraction (called F₂), taken from the neighboring nucleus ¹⁴⁵Nd. With the availability of reaction codes such as TALYS, such fraction...

article

Nuclear data uncertainty propagation on spent fuel nuclide compositions

O. Leray, D. Rochman, P. Grimm, H. Ferroukhi, more

Annals of Nuclear Energy > 2016 > 94 > C > 603-611

Nuclear data uncertainty propagation plays a growing role in neutronic simulation by giving confidence bounds to physical macroscopic parameters used for safety and design of nuclear systems. This study deals with nuclear data uncertainty propagation (cross-sections, fission spectrum, neutron multiplicities and fission yields) on the nuclide composition of two UO₂ spent fuel samples of different burnup...

article

Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation

D. Rochman, A. Vasiliev, H. Ferroukhi, T. Zhu, more

Annals of Nuclear Energy > 2016 > 92 > C > 150-160

This work is presenting a comparison of results for different methods of uncertainty propagation due to nuclear data for 330 criticality-safety benchmarks. Covariance information is propagated to k_eff using either Monte Carlo methods (NUSS: based on existing nuclear data covariances, and TMC: based on reaction model parameters) or sensitivity calculations from MCNP6 coupled with nuclear data covariances...

article

Localized neutron flux assessment and verification studies using MCNPX PWR full core model

A. Vasiliev, H. Ferroukhi, M. Pecchia, A. Pautz

Annals of Nuclear Energy > 2016 > 92 > C > 317-332

The existence of significant local intra-assembly and azimuthal neutron flux variations at or around PWR control rod fingers and which would eventually not be captured by lower order transport deterministic reactor analysis methods, was examined using simplified full-core Monte Carlo calculations. The locations of specific interest were the clad surfaces and absorber material zones around the tips...

article

Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data

A. Dupré, A. Vasiliev, H. Ferroukhi, A. Pautz

Annals of Nuclear Energy > 2015 > 85 > C > 820-829

At the Paul Scherrer Institute (PSI), a computational scheme aimed at high fidelity fast neutron fluence estimations for Light-Water-Reactors (LWRs) was in previous years developed. In this scheme, the neutron transport calculations are performed with the stochastic Monte Carlo N-Particle Transport Code MCNPX using as basis a three-dimensional pin-level volumetric source obtained from validated deterministic...

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Keywords

PWR (5)
SIMULATE-3K (4)
CASMO-5 (3)
MCNPX (3)
SHARK-X (3)
DOSIMETRY (2)
GEF (2)
HBR-2 BENCHMARK (2)
NUCLEAR DATA (2)
OSKARSHAMN-2 (2)
RPV (2)
SIMULATE-3 (2)
UNCERTAINTY PROPAGATION (2)
ASSEMBLY BOW (1)
BAYESIAN UPDATE (1)
BOWING EFFECTS (1)
BURN-UP (1)
BURN-UP INDICATOR (1)
BWR (1)
BWR STABILITY (1)
BWR STABILITY AND DYNAMICS (1)
CANONICAL MODELING (1)
CAPTURE CROSS SECTION (1)
CASMO/SIMULATE (1)
CASMO5 (1)
CONTROL RODS (1)
COUPLING (1)
CRITICALITY BENCHMARK (1)
DECAY HEAT (1)
DISCRETE AND CONTINUOUS TIME SIGNALS (1)
DOSE (1)
ENDF/B-VII.1 (1)
FAST NEUTRONS (1)
FEEDWATER TRANSIENT (1)
FISSION YIELD PERTURBATION (1)
FISSION YIELD UNCERTAINTY (1)
FISSION YIELDS (1)
FLUENCE (1)
FULL CORE SIMULATION (1)
HOPF BIFURCATION (1)
ISOTOPE INVENTORY (1)
JEFF-3.1 (1)
LIMIT CYCLE (1)
LONG TERM STORAGE (1)
MONTE-CARLO METHODS (1)
MULTIVARIATE AR/ARMA MODELING (1)
ND147 (1)
NEUTRON FLUENCE (1)
NUCLEAR ASTROPHYSICS (1)
OUT-OF-PHASE (1)
PARCS (1)
RADIATIVE NEUTRON CAPTURES (1)
REACTOR NOISE AND CAUSALITY ANALYSIS (1)
RIA ANALYSIS (1)
ROTATIONAL SYMMETRY LINE (1)
SANDY (1)
SENSITIVITY (1)
SERPENT-2 (1)
SPENT NUCLEAR FUEL (1)
SPERT-III (1)
STABILITY (1)
STABILITY OF BWR (1)
STATISTICAL HAUSER–FESHBACH MODEL (1)
TRACE (1)
TRACE/CORE BWR CORE MODEL (1)
TRANSPORT (1)
UNCERTAINTY (1)
UNCERTAINTY QUANTIFICATION (1)
VALIDATION (1)
VERIFICATION (1)
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Elsevier (28)
Springer (2)

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Search results for: H. Ferroukhi

Correlation $\overline{\nu}_{p} - \sigma$ ν ¯ p - σ for U-Pu in the thermal and resonance neutron range via integral information

Monte Carlo nuclear data adjustment via integral information

Consistent criticality and radiation studies of Swiss spent nuclear fuel: The CS2M approach

Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments

Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores

Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles

Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly

Testing the NURESIM platform on a PWR main steam line break benchmark

UO2 fuel pin bowing effects on isotopic concentrations

Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone

Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19

Radiative neutron capture: Hauser Feshbach vs. statistical resonances

Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core

Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K

A Bayesian Monte Carlo method for fission yield covariance information

Re-evaluation of the thermal neutron capture cross section of 147Nd

Nuclear data uncertainty propagation on spent fuel nuclide compositions

Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation

Localized neutron flux assessment and verification studies using MCNPX PWR full core model

Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data

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