Development of a general coupling interface for the fuel performance code TRANSURANUS – Tested with the reactor dynamics code DYN3D-Reference-Cited by-同舟云学术

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Development of a general coupling interface for the fuel performance code TRANSURANUS – Tested with the reactor dynamics code DYN3D

Published:2015-10 Issue: Volume:84 Page:73-85
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Holt L.,Rohde U.,Seidl M.,Schubert A.,Van Uffelen P.,Macián-Juan R.

Funder

E.ON Kernkraft GmbH

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference42 articles.

1. AREVA, 2010. COBRA-FLX: A core thermal-hydraulic analysis code. Topical report, ANP-10311NP.

2. Discussion about HBS transformation in high burn-up fuels;Baron;Nucl. Eng. Technol.,2009

3. MCNP - A General Monte Carlo N-Particle Transport Code;Briesmeister,2000

4. Chemin, S., Moal, A., 2014. NURESAFE, D11.11 - Specifications for SCANAIR Integration and D11.12 - Specifications CEA coupling in-core N/T-M/T-H.

5. Extension of the TRANSURANUS plutonium redistribution model for fast reactor performance analysis;Di Marcello;Nucl. Eng. Des.,2012

Cited by 17 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A review on the thermo-mechanical modelling needs in system codes;Nuclear Engineering and Design;2023-05

2. Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS;Nuclear Engineering and Technology;2022-12

3. A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution;Energies;2021-02-05

4. Nuclear physics deterministic code;Nuclear Power Plant Design and Analysis Codes;2021

5. Development of coupled neutronics and fuel performance analysis capabilities between Serpent and TRANSURANUS;Nuclear Engineering and Design;2020-04

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