Publikationen, an denen er mitarbeitet RAFAEL JUAREZ MAÑAS (20)

2024

  1. Corrigendum to “Total Ionizing Dose Estimation of ITER Upper Port Remote Handling Equipment” [Fusion Engineering and Design volume 202 (2024) 114359] (Fusion Engineering and Design (2024) 202, (S0920379624002126), (10.1016/j.fusengdes.2024.114359))

    Fusion Engineering and Design

  2. ITER full model in MCNP for radiation safety demonstration

    Nature Communications , Vol. 15, Núm. 1

  3. Neural network-based source biasing to speed-up challenging MCNP simulations

    Fusion Engineering and Design, Vol. 202

2023

  1. Computational study of the dose-rate field of an ITER heat exchanger due to activated corrosion products

    Fusion Engineering and Design, Vol. 193

  2. Development and validation in water of FLUNED, an open-source tool for fluid activation calculations

    Computer Physics Communications, Vol. 291

  3. Uncertainty Propagation Scheme for Two-Step Monte Carlo Neutronic Simulations Applied to the Stochastic Uncertainty of the Intermediate Radiation Source in SRC-UNED

    Fusion Engineering and Design, Vol. 192

2022

  1. Development of radiation sources for nuclear analysis beyond ITER bio-shield: SRC-UNED code

    Computer Physics Communications, Vol. 275

  2. Overview of JET results for optimising ITER operation

    Nuclear Fusion, Vol. 62, Núm. 4

  3. Shielding conceptual designs of ITER TCP ports to protect electronics

    Fusion Engineering and Design, Vol. 176

2021

  1. A full and heterogeneous model of the ITER tokamak for comprehensive nuclear analyses

    Nature Energy, Vol. 6, Núm. 2, pp. 150-157

  2. Improved radiation shielding analysis considering vector calculus

    International Journal of Energy Research, Vol. 45, Núm. 8, pp. 11904-11915

  3. Integral modelling of the ITER cooling water systems radiation source for applications outside of the Bio-shield

    Fusion Engineering and Design, Vol. 171

  4. Nuclear data for D1SUNED for the study of ITER planned in-situ maintenance dose scenarios

    Fusion Engineering and Design, Vol. 170

2020

  1. D1SUNED system for the determination of decay photon related quantities

    Fusion Engineering and Design, Vol. 151

2019

  1. Nuclear analysis of the ITER torus cryopumps

    Nuclear Fusion, Vol. 59, Núm. 10

2018

  1. Assessment and optimization of MCNP memory management for detailed geometry of nuclear fusion facilities

    Fusion Engineering and Design, Vol. 136, pp. 386-389

  2. Shutdown dose rate mitigation in the ITER upper ports

    Fusion Engineering and Design, Vol. 136, pp. 228-232

  3. The use of the long modular diagnostics shield module to mitigate shutdown dose rates in the ITER diagnostics equatorial ports

    Nuclear Fusion, Vol. 58, Núm. 5

  4. Update in the nuclear responses of the European TBMs for ITER during operation and shutdown

    Fusion Engineering and Design, Vol. 134, pp. 92-96

2017

  1. How to reduce shutdown dose rates in ITER diagnostics quatorial ports

    Transactions of the American Nuclear Society