On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions-Reference-Cited by-同舟云学术

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On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions

Published:2024-04 Issue: Volume:419 Page:112992
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Angelucci Michela^ORCID,Herranz Luis E.,Paci Sandro

Publisher

Elsevier BV

Reference30 articles.

1. ACI, n.d.. ACI CODE 349-13: Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary.

2. Thermal analysis of HI-STORM 100S dry cask with the MELCOR code;Angelucci;J. Phys. Conf. Ser.,2021

3. Uncertainty and sensitivity analysis of a dry cask for spent nuclear fuel;Angelucci;Energies,2022

4. Ansys Inc. ANSYS Fluent User’s Guide.

5. Ansys Inc. ANSYS CFX-Solver Theory Guide.

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1. Preface for the special issue “NFT-05: Italy and Greece”: nuclear fission technology in Italy;Nuclear Engineering and Design;2024-11

2. Modeling and Design Parameter Optimization to Improve the Sensitivity of a Bimorph Polysilicon-Based MEMS Sensor for Helium Detection;Sensors;2024-06-04

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