Status of the Astrid Core at the End of the Pre-Conceptual Design Phase 1

Chenaud,; Devictor, Nicolas; Mignot, Guillaume; Varaine, F.; Venard, Christophe; Martin, Laurent; Phélip, M.; Lorenzo, D.; Serre, F.; Bertrand, Frédèric; Alpy, N.; Flem, Marion Le; Gavoille, P.; Lavastre, R.; Richard, P.; Verrier, D.; Schmitt, Didier

doi:10.5516/net.02.2013.519

Cited by 54 publications

(29 citation statements)

References 2 publications

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“…The selection of an SFR system for the ASTRID project was based, to a large extent, on the extensive and invaluable experience of the French nuclear industry with the PHENIX and SUPERPHENIX SFR systems. In recent years, several core layouts were proposed for the ASTRID core . A most promising concept was found to be the reduced void fraction (CFV) core, arranged in a hexagonal lattice and consists of four axial regions: the lower blanket, the lower fissile zone, the intermediate blanket, and the upper fissile zone, as described in Figure .…”

Section: Methodology and Examined Systemsmentioning

confidence: 99%

“…In recent years, several core layouts were proposed for the ASTRID core. 23 A most promising concept was found to be the reduced void fraction (CFV) core, arranged in a hexagonal lattice and consists of four axial regions: the lower blanket, the lower fissile zone, the intermediate blanket, and the upper fissile zone, as described in Figure 1. The main parameters of the CFV-V0 are given in Table 1.…”

Section: Representativity Methodsmentioning

confidence: 99%

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Modeling representative Gen-IV molten fuel reactivity effects in the ZEPHYR ZPR - LFR analysis

2018

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Summary Studies related to severe core accidents constitute a crucial element in the safety design of Gen‐IV systems. A new experimental program, related to severe core accidents studies, is proposed for the zero‐power experimental physics reactor (ZEPHYR) future reactor. The innovative program aims at studying reactivity effects at high temperature during degradation of Gen‐IV cores by using critical facilities and surrogate models. The current study introduces the European lead‐cooled system (ELSY) as an additional Gen‐IV system into the representativity arsenal of the ZEPHYR, in addition to the sodium‐cooled fast reactors. Furthermore, this study constitutes yet another step towards the ultimate goal of studying severe core accidents on a full core scale. The representation of the various systems is enabled by optimizing the content of plutonium oxide in the ZEPHYR fuel assembly. The study focuses on representing reactivity variation from 900°C at nominal state to 3000°C at a degraded state in both ELSY and Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) cores. The study utilizes the previously developed calculation scheme, which is based on the coupling of stochastic optimization process and Serpent 2 code for sensitivity analysis. Two covariance data are used: the ENDF 175 groups for ELSY and the Covariance Matrix Cadarache (COMAC) 33 groups for ASTRID. The effect of the energy group structure of the covariance data on the representativity process is found to be significant. The results for single degraded ELSY fuel assembly demonstrate high representativity factor (>0.95) for reactivity variation and for the criticality level. Also, it is shown that the finer energy group structure of the covariance matrices results in dramatic improvement in the representation level of reactivity variations.

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Section: Methodology and Examined Systemsmentioning

confidence: 99%

Section: Representativity Methodsmentioning

confidence: 99%

Modeling representative Gen-IV molten fuel reactivity effects in the ZEPHYR ZPR - LFR analysis

2018

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“…The models are based on the 1500 MWth French ASTRID CFV (Coeur à Faible effet de Vide, i.e. low sodium void core) concept developed by CEA with support of AREVA and EdF as described in [11,12]. The ASTRID core layout in plane is shown in Figure 1 [11].…”

Section: Assessment Of the Astrid-like Modelsmentioning

confidence: 99%

ASTRID-like Fast Reactor Cores for Burning Plutonium and Minor Actinides

et al. 2015

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A reduction of nuclear waste by transmutation of trans-uranium elements (TRUs), such as Pu and Minor Actinides (MAs) contained in Spent Nuclear Fuel (SNF), is a goal for future reactors. In general, countries with on-going nuclear scenarios would profit from MA mass stabilization, while transmutation of Pu and MAs from SNF could be desired in countries in nuclear phaseout. Both missions can be accomplished by employing fast reactors loaded with fuels containing different amounts of Pu and MAs in a closed (or partially closed) fuel cycle. In this paper, two 1200 MWth sodium-cooled fast reactor cores, based on the French ASTRID design, are proposed for burning TRUs (phase-out option) or only MAs (on-going option). Main attention is focused on the safety and on the transmutation performance. The coolant void effect, in the region including the core and the plenum above and the Doppler constant of both systems are negative also with irradiated fuel. The conversion ratios (CR) of the Pu and MA burners are in the ranges from 0.6 to 0.7 and from 0.5 to 0.6, respectively. These results show a large safety and transmutation potential of ASTRID type reactors.

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“…One of the main safety aspects of SFRs under study is the reactivity insertion caused by a reduction in the sodium density in some regions of the core, and how to minimize or eliminate it by design. As means of an example, the ASTRID design (Chenaud et al, 2013) favors an axially-heterogeneous layout and the presence of an upper sodium plenum, in addition to a large pin concept.…”

Section: Introductionmentioning

confidence: 99%