Concept

Advanced heavy-water reactor

Publications associées (19)

foamForNuclear: A unified OpenFOAM multi-physics platform for nuclear applications

OpenFOAM has been extensively used to develop dedicated physics solvers for nuclear applications, ranging from thermal-hydraulics to structural mechanics and neutronics. However, existing frameworks still lack a general-purpose structure for coupling arbitrary physics across multiple regions and meshes. This work presents foamForNuclear, a new OpenFOAM-based open-source multiphysics architecture that addresses this limitation. Building on the established GeN-Foam and OFFBEAT codes, the platform introduces a

2026

Modelling the Swiss Nuclear Fuel Cycle at Hourly Resolution

This report documents the technical continuation of P. Tessier's semester project [1] on the integration of fast neutron reactors (FNR) and nuclear fusion into the Swiss 2050 energy mix, modelled with the EnergyScope optimisation framework [2]. Two extensions are presented. First, the underlying model is ported from EnergyScope's monthly-resolution formulation to the hourly, typical-days (TD) formulation of EnergyScope TD, addressing a limitation explicitly identified at the end of the original project. The

École Polytechnique Fédérale de Lausanne2026

First neutron imaging experiments at the CROCUS zero-power reactor

The steady decline of neutron imaging (NI) facilities, exacerbated by the closure of several research reactors such as Orphée (LLB, France) and BER (HZB, Germany), has increased the importance of leveraging existing reactors for NI applications. Zero-power research reactors offer a low-cost and flexible platform for student training, materials research and development, and proof-of-principle studies that can support larger neutron facilities. Previously, no dedicated NI beamline was available at the EPFL ze

Elsevier BV2026

Collision Tracking in OpenMC: Methods and Applications in Neutron Noise, Neutron Imaging, Time-of-Flight, and Multiplicity Counting

We present the development and application of a collision tracking feature within the OpenMC Monte Carlo particle transport code, designed for diverse applications such as neutron spectroscopy, scatter camera system, neutron noise, and multiplicity counting simulations. This feature enables the tracking of individual particle collisions, with potential applications in nuclear nonproliferation, reactor physics, and nuclear security. Additionally, the feature holds potential for the calibration of neutron det

Taylor and Francis Group2026

Data-driven reduced-order modeling of zircaloy cladding deformation behavior under LOCA conditions

During a Loss-of-Coolant Accident (LOCA), fuel cladding may undergo high-temperature creep, oxidation, ballooning, and even rupture, potentially leading to the release of radioactive fission products into the primary circuit or beyond. High-fidelity fuel performance simulations are important for evaluating cladding behavior under LOCA conditions; however, their high computational cost limits their use for fast prediction, extensive parametric analysis, and full-core fuel safety assessment. This study develo

Elsevier BV2026

Top-Metal-Only RFIC Retargeting for Fast Specs-To-Silicon Iteration Enabled by AI-Assisted Inverse Design

AI and machine learning (ML) are increasingly used to accelerate Radio-Frequency Integrated Circuit (RFIC) design, where specs-to-layout inverse-design automation can shorten design cycles and lower the expertise barrier. In practice, RFIC turnaround and design migration are constrained not only by iterative EM-driven passive design, but also by layout-to-silicon latency dominated by long fabrication cycles and the cost of full-mask preparation. To address these challenges, this paper presents a fast specs-

IEEE2026

Leveraging microbial processes to mitigate hydrogen pressure buildup in radioactive waste repositories

Nuclear energy expanded rapidly during the second half of the twentieth century, to become a major source of low-carbon electricity in many countries, including Switzerland. However, reliance on nuclear power brings with it the challenge of long-term management of radioactive waste. Safety standards require that radioactive waste be isolated from humans over timescales of up to one million years. To date, a broad scientific consensus considers deep geological repositories to be the safest option for the fin

EPFL2026

Analysis and Reproduction of Stainless-steel Integral Experiments Towards Nuclear Data Assimilation

This thesis focuses on the analysis and reproduction of integral experiments for validating stainless-steel nuclear data, through two complementary programs conducted in the CROCUS zero-power reactor at EPFL. These programs are the semi-integral PETALE program, which includes criticality and transmission experiments with heavy reflectors, and the hybrid pile-oscillation program BLOOM. Both belong to HARVEST X, an EPFL coordinated initiative to reproduce, extend, and cross-validate experiments for stainless-

EPFL2025

From real life to scale model (and back again): The life of CROCUS in the student’s mind

The CROCUS nuclear reactor is primarily motivated by education, from public visits to advanced teaching at the Bachelor’s, Master’s, and doctoral levels, as well as professional training. It is a uranium-fueled, light-water moderated, zero power reactor with a maximum power of 100 W. As simple as an operational reactor can be, CROCUS effectively supports conceptual understanding through its tangible materiality, offering virtually no distance from the system, no significant risk, and negligible dose rates i

EDP Sciences2025

Towards the Direct Observation of Xenon-135 Poisoning in a Zero-Power Reactor via Gamma Spectroscopy

Xenon-135 (Xe-135) is a high-yield fission product with high neutron-capture cross section. it is a commonly encountered reactor reactivity poison. Direct observation of Xe in reactors typically relies on off-gas measurement techniques, which can be challenging or costly to implement and often require high-flux reactors. Gamma spectroscopy of irradiated U or Pu samples provides an alternative method for obtaining fission yields and population estimates. When predicting the Xe populations of a given reactor,

EDP Sciences2025

Simulations of a new neutron imaging station at the CROCUS zero power reactor

Neutron imaging (NI) complements X-ray radiography by exploiting the strong interaction of neutrons with several light elements and a high penetration for many heavy elements. Hitherto no dedicated NI beamline currently exists at the zero-power CROCUS reactor. Establishing such a station would create a low-cost platform for student training, materials R&D, and proof-of-principle studies that feed larger facilities. Using the Serpent 2 Monte Carlo neutron transport code, we explored how to modify an existing

EDP Sciences2025

Demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors

Patrick Blanchard, Holger Reimerdes

Nuclear fusion could offer clean, abundant energy. However, managing the power exhausted from the core fusion plasma towards the reactor wall remains a major challenge. This is compounded in emerging compact reactor designs promising more cost-effective pathways towards commercial fusion energy. Alternative Divertor Configurations (ADCs) are a potential solution. In this work, we demonstrate exhaust control in ADCs, employing a novel method to diagnose the neutral gas buffer, which shields the target. Our w

Springer Science and Business Media LLC2025

On the determination of the reference temperature T0 of the Master-Curve method using subsized compact tension specimens

Philippe Spätig

Structural integrity of reactor pressure vessel (RPV) is of primary importance to ensure the long-term safety of light water reactors. The pressure vessel made of ferritic steel presents a ductile to brittle transition and experiences neutron embrittlement that needs to be quantified. The so-called Master-Curve (MC) method, standardized in the ASTM-E1921, is commonly used to determine a reference temperature T0, which indexes the median toughness-temperature curve in the transition at 100 MPam 1/2 for one i

Elsevier BV2024

Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Carlo Fiorina, Oskari Ville Pakari, Pavel Frajtag, Axel Guy Marie Laureau, Adolfo Rais, Daniel Godat

The Horizon2020 European project CORTEX aims at developing an innovative core monitoring technique that allows detecting anomalies in nuclear reactors, such as excessive vibrations of core internals, flow blockage, or coolant inlet perturbations. The techn ...

2021

Towards the Validation of Noise Experiments in the CROCUS Reactor Using the TRIPOLI-4 Monte Carlo Code in Analog Mode

Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari

Intrinsic neutron noise experiments offer a non-invasive manner to measure the prompt decay constant or reactivity of fissile systems. Using the fluctuations in the density of fission chains, one can infer the kinetics parameters via correlation analysis s ...

2021

Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

Minh Quang Tran

The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed. MAG analysed the technological readiness of structural, plasma facing and high heat flux materials for a DEMO concept to be constructed in ...

Elsevier2014

Design of solar driven supercritical water desalination plant

The objective of this master project is to develop model for the solar driven supercritical desalination plant. Furthermore we propose a possible system integration and examination of its performance in terms of energy and cost effectiveness. The model simulations and calculations are performed using Belsim Vali and in-house LENI developed program OSMOSE. Supercritical salt separation model was created based on the solubility models proposed by Leusbrock and research conducted by Khan and Rogak on salt mixt

2013

Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs

The Supercritical-Water-Cooled Reactor (SCWR) is the Generation IV reactor concept most closely related to current light water reactors (LWRs). The SCWR builds on the vast experience with today's LWRs and supercritical coal-fired power plants. Water at sup ...

EPFL2012

Heat Management in Single and Multi-injection Microstructured Reactors: Scaling Effects, Stability Analysis, and Role of Mixing

Albert Renken, Lioubov Kiwi

The exothermic reactions with fast intrinsic kinetics when carried out in conventional reactors are often limited by heat transfer. This results in the formation of hot spots, which affects product distribution of complex reactions and may lead to reactor runaway. Microstructured reactors (MSR) have been successfully used for this type of reaction, gaining increased temperature control and enhanced safety. Although different MSR concepts have been applied to various processes, the general design criteria ar

2012

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Publications associées (19)

Collision Tracking in OpenMC: Methods and Applications in Neutron Noise, Neutron Imaging, Time-of-Flight, and Multiplicity Counting

Taylor and Francis Group2026

Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

Minh Quang Tran

Elsevier2014

Design of solar driven supercritical water desalination plant

2013

Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs

EPFL2012

Heat Management in Single and Multi-injection Microstructured Reactors: Scaling Effects, Stability Analysis, and Role of Mixing

Albert Renken, Lioubov Kiwi

2012