Analysis of the SPERT-III E-Core Using ANCK Code with the Chord Weighting Method

Aoki, Shigeaki; Suemura, Takayuki; Ogawa, Junto; Takeda, Toshikazu

doi:10.3327/jnst.46.239

Cited by 3 publications

(2 citation statements)

References 12 publications

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“…The E-core has attracted a considerable amount of interest in view of the possibility of validating reactor physics and thermal-hydraulics 350 codes in both steady-state and transient conditions. Concerning reactor physics, most of the previous analyses have been carried out by means of deterministic codes, which can be easily coupled with thermal-hydraulics codes, but suffer from various approximations (Kosaka et al, 1988;Ikeda and Takeda, 2001; Ya-355 maji et al, 2014; Grandi and Moberg, 2012;Grandi, 2014;Aoki et al, 2009;Wang et al, 2013). In particular, the modelling of the complex and highly heterogeneous geometry of SPERT-III has been often dealt with by resorting to spatial homogenization methods, which may induce some discrepancies in the estimation of the physical parameters (see for instance the discussion in (Cao et al, 2015)).…”

Section: The Special Power Excursion Reactor Test III (Spert-iii)mentioning

confidence: 99%

Analysis of dynamic reactivity by Monte Carlo methods: The impact of nuclear data

Zoia

Jouanne

Siréta

et al. 2017

Annals of Nuclear Energy

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We compute the dynamic reactivity of several reactor configurations by resorting to Monte Carlo simulation. The adjoint-weighted kinetics parameters are first determined by the Iterated Fission Probability (IFP) method, together with precursor decay constants, and the reactivity is then estimated by the in-hour equation. When reference experimental values are available for the reactivity as a function of the asymptotic reactor period, comparison with the Monte Carlo simulation findings allows validating the IFP algorithm and at the same time probing the accuracy of the nuclear data libraries used in numerical simulations. For our calculations we resort to the Tripoli-4 R Monte Carlo code, developed at CEA, where IFP methods have been recently implemented. We perform a detailed analysis of the IPEN/MB-01 core, the SPERT III E-core, and the SPERT IV D-12/25 core, for which benchmark-quality reactor specifications have been published. We single out some systematic discrepancies between computed and measured core reactivity that might mirror possible inconsistencies in nuclear data libraries.

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Section: The Special Power Excursion Reactor Test III (Spert-iii)mentioning

confidence: 99%

Analysis of dynamic reactivity by Monte Carlo methods: The impact of nuclear data

Zoia

Jouanne

Siréta

et al. 2017

Annals of Nuclear Energy

View full text Add to dashboard Cite

show abstract

“…The E-core has attracted a considerable amount of interest in view of the possibility of validating reactor physics and thermal-hydraulics codes in both steady-state and transient conditions. Concerning reactor physics, most of the previous analyses have been carried out by means of deterministic codes, which can be easily coupled with thermal-hydraulics codes, but suffer from various approximations (Kosaka et al, 1988;Ikeda and Takeda, 2001;Yamaji et al, 2014;Grandi and Moberg, 2012;Grandi, 2014;Aoki et al, 2009;Wang et al, 2013). In particular, the modelling of the complex and highly heterogeneous geometry of SPERT-III has been often dealt with by resorting to spatial homogenization methods, which may induce some discrepancies in the estimation of the physical parameters (see for instance the discussion in (Cao et al, 2015)).…”

Section: Introductionmentioning

confidence: 99%

Reactor physics analysis of the SPERT III E-core with Tripoli-4®

Zoia

Brun

2016

Annals of Nuclear Energy

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In this paper we detail a Monte Carlo model for the SPERT III E-core and we illustrate the simulation results obtained for the reactor physics parameters (including the effective multiplication factor, the reactivity worth of the core components and the kinetics parameters) by resorting to the production code T-4 R . We have considered three reactor configurations, namely, initial core loading, zero cold power and hot zero power in stationary conditions, based on the large database of available experimental measurements. This analysis is aimed at establishing a firm background for the future investigation of the time-dependent behaviour of the E-core under reactivity excursions by resorting to reactor period calculations and dynamic Monte Carlo methods.

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SIMMER analysis of the SPERT I D-12/25 experiments: The counter reactivities

Wilhelm¹

2010

Nuclear Engineering and Design

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Analysis of the SPERT-III E-Core Using ANCK Code with the Chord Weighting Method

Cited by 3 publications

References 12 publications

Analysis of dynamic reactivity by Monte Carlo methods: The impact of nuclear data

Analysis of dynamic reactivity by Monte Carlo methods: The impact of nuclear data

Reactor physics analysis of the SPERT III E-core with Tripoli-4®

SIMMER analysis of the SPERT I D-12/25 experiments: The counter reactivities

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