Results 11 to 20 of about 138,969 (272)
Effects of ground movements on realistic guide models for the European Spallation Source
Physical Review Accelerators and Beams, 2020 We model the effect of ground movement, based on empirical experience, on the transport properties of long neutron guides by ray-tracing simulations. For a simple model, our results reproduce the large losses found by an earlier study, while for a more ...
Asla Husgard +6 more
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MULTI-PHYSICS TRANSIENT SIMULATIONS WITH TRIPOLI-4® [PDF]
EPJ Web of Conferences, 2021 In this work, we present the first dynamic calculations performed with the Monte Carlo neutron transport code TRIPOLI-4R with thermal-hydraulics feedback.
Faucher Margaux +2 more
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Brazilian Journal of Radiation Sciences, 2023 In this article, we present an application of the coarse-mesh Deterministic Spectral Method (SDM) to generate multigroup angular fluxes in one-dimensional spatial domains using the neutron transport stationary equation, in the formulation of discrete ...
F. T. C. S. Balbina +2 more
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Analysis of the Signal over Noise Ratio of the hodoscope determined by Monte Carlo calculation [PDF]
EPJ Web of Conferences, 2021 The CABRI experimental pulse reactor, located at the Cadarache nuclear research center, southern France, is devoted to the study of Reactivity Initiated Accidents (RIA) for the purpose of the CABRI International Program (CIP), managed by IRSN in the ...
Di Salvo J., Mirotta S., Chevalier V.
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Evaluation of PWR pressure vessel fast neutron fluence benchmarks from NUREG/CR-6115 with ares transport code [PDF]
Nuclear Technology and Radiation Protection, 2017 An accurate evaluation of PWR pressure vessel fast neutron fluence is essential to ensure pressure vessel integrity over the design lifetime. The discrete ordinates method is one of the main methods to treat such problems.
Zhang Liang +3 more
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Nuclear Engineering and Technology, 2017 With ever-advancing computer technology, the Monte Carlo (MC) neutron transport calculation is expanding its application area to nuclear reactor transient analysis.
Nadeem Shaukat, Min Ryu, Hyung Jin Shim
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Brazilian Journal of Radiation Sciences, 2021 This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose
Desirée Yael de Sena Tavares +2 more
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Influence of the neutron transport tube on neutron resonance densitometry
EPJ Web of Conferences, 2017 Neutron Resonance Densitometry (NRD) is a non-destructive assay technique of nuclear materials in particle-like debris that contains various materials.
Kitatani Fumito +5 more
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Probing Mechanical and Chemical Instabilities in Neutron-Rich Matter [PDF]
, 2001 The isospin-dependence of mechanical and chemical instabilities is investigated within a thermal and nuclear transport model using a Skyrme-type phenomenological equation of state for neutron-rich matter.
Akmal +49 more
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Variational nodal methods for neutron transport: 40 years in review
Nuclear Engineering and Technology, 2022 The variational nodal method for solving the neutron transport equation has evolved over 40 years. Based on a functional form of the Boltzmann neutron transport equation, the method now comprises a complete set of variants that can be employed for ...
Tengfei Zhang, Zhipeng Li
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