Publications related to Assessment of JEFF Nuclear Data Libraries for Reactor Physics and Spent Fuel Composition Applications

Related publications (15)

Advancing Multi-Dimensional Simulation of Nuclear Fuel Behavior: from LOCA Analysis to Fast Reactor Applications

Current research on nuclear fuel focuses on two primary objectives. The first is to optimize the fuel used in the current generation of nuclear reactors in terms of safety, efficiency, and economics. This has driven efforts to increase discharge burnup and ...

EPFL2025

Multi-physics Sub-pin Resolution Analysis of a PWR core with nTRACER/CTF for the OECD/NEA TVA Watts Bar 1 Benchmark

Andreas Pautz, Marianna Papadionysiou

The systematic use of high-fidelity high-resolution codes which allow the prediction of safety parameters on a local scale, can result in more efficient use of the nuclear fuel and of the nuclear reactor.The Laboratory of Reactor Physics and Thermal-Hydrau ...

American Nuclear Society2024

Investigation of Hydrogen Behaviour in Irradiated Zirconium-Based Fuel Claddings by Neutron Imaging and Complementary Techniques

Okan Yetik

Zirconium-based cladding tubes, mainly used as fuel cladding materials in light water reactors, serve as the primary barrier insulating the radioactive fission products from the environment. During operation, the cladding interacts with the coolant water, ...

EPFL2024

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari

Gamma-ray spectroscopy is an effective technique for radioactive material characterization, routine inventory verification, nuclear safeguards, health physics, and source search scenarios. Gamma-ray spectrometers typically cannot be operated in the immedia ...

MDPI2024

Validation of Intrapin Reaction Rate Distributions from Deterministic Transport Codes

Tom Mager

Efforts are underway worldwide to develop advanced simulation methods of nuclear power plants, with an improved resolution in space, angle and energy. These tools aim to enhance operational efficiency through the predictions of local phenomena critical for ...

EPFL2024

Investigation of scrape-off layer and divertor transport using infrared thermography and SOLPS-ITER simulations

Claudia Colandrea

Nuclear fusion, with its potential to provide a nearly unlimited energy source, has inspired scientists to work on the development of fusion power plants. Among the various devices designed to harness nuclear fusion, the tokamak confines the fusion fuel, w ...

EPFL2024

Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor

Mathieu Hursin

This paper presents nuclear reactor transient measurements with thermal feedback and corresponding coupled neutronic-thermohydraulic simulations performed for the natural circulation cooled Training Reactor of Budapest University of Technology and Economic ...

2023

Development of a High Fidelity Model of the CROCUS Experimental Reactor

Andreas Pautz, Carlo Fiorina, Tom Mager

Measurements of scalar flux distributions with fine spatial and energy resolutions are needed to remedy one of the validation shortcomings of the novel neutronics full core solvers, such as MPACT and nTRACER. While a very detailed resolution of the flux ca ...

American Nuclear Society2022

The OFFBEAT multi-dimensional fuel behavior solver

Andreas Pautz, Alessandro Scolaro, Carlo Fiorina

The OpenFOAM Fuel BEhavior Analysis Tool, or OFFBEAT, is a multi-dimensional fuel performance code under collaborative development at the Laboratory for Reactor Physics and Systems Behaviour (LRS) of the EPFL and at the PSI. The code can be used both for s ...

ELSEVIER SCIENCE SA2020

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Andreas Pautz, Hakim Ferroukhi, Dimitri Rochman

In this study, an optimization of the canister loading for used nuclear fuels is performed, solely based on their decay heat values. By taking into account the individual irradiation history for each fuel assembly, as well as with a number of assumptions o ...

ELSEVIER SCIENCE SA2020

Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor

Rakesh Chawla, Konstantin Mikityuk, Gaëtan Girardin

The present paper is related to the design and neutronic characterization of the principal control assembly system for the reference large (2400 MWth) Generation IV gas-cooled fast reactor (GFR), which makes use of ceramic-ceramic (CERCER) plate-type fuel- ...

Elsevier Science Ltd.2008

Comparison of 3D reaction rate distributions measured in an optima2 BWR assembly with MCNPX predictions

Rakesh Chawla, Michaël Plaschy

As part of a joint research programme between the Paul Scherrer Institute (PSI) and swissnuclear, with the co-operation of the Leibstadt nuclear power plant in Switzerland and fuel suppliers Westinghouse Sweden, measurements and calculations have been made ...

Elsevier Science Ltd.2008

BWR stability and bifurcation analysis using reduced order models and system codes: Identification of a subcritical Hopf bifurcation using RAMONA

Rakesh Chawla, Abdelhamid Dokhane

The system code RAMONA, as well as a recently developed BWR reduced order model (ROM), are employed for the stability analysis of a specific operational point of the Leibstadt nuclear power plant. This has been done in order to assess the ROM's applicabili ...

2007

Validation of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel

Rakesh Chawla, Stefano Caruso

A measurement station has been built for the non-destructive investigation of burnt fuel rod segments through high-resolution gamma spectrometry. Four UO2 pressurised water reactor fuel rod segments with different burnup levels between 50 and 100GWd/t and ...

Elsevier2007

Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples

Rakesh Chawla

Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission products and a high abundance of major and minor actinides. Of particular interest is the change in the reactivity of the fuel as a function of burnup and ...

Elsevier2006