Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis-Reference-Cited by-同舟云学术

Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis

Published:2018-08-29 Issue:4 Volume:74 Page:277-287
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Yang Jinan¹^ORCID,Wilson Stephen C.¹^ORCID,Mosher Scott W.¹^ORCID,Radulescu Georgeta¹

Affiliation:

1. Oak Ridge National Laboratory Radiation Transport Group, P.O. Box 2008, Building 5700, Oak Ridge, Tennessee 37831-6170

Publisher

Informa UK Limited

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/15361055.2018.1493325

Reference12 articles.

1. X-5 MONTE CARLO TEAM, “MCNP—A General Monte Carlo N-Particle Transport Code, Version 5, Volume I: Overview and Theory,” LA-UR-03-1987, Los Alamos National Laboratory (2003); https://mcnp.lanl.gov/mcnp_faq.shtml (current as of July 25, 2018).

2. S. LILLEY, T. EADE, and F. FOX, “ITER NBI Nuclear Analysis Phase 2, Deliverable 5: Final Report,” ITER Organization, Private Communication (Jan. 2015).

3. Status of the McCad geometry conversion tool and related visualization capabilities for 3D fusion neutronics calculations

4. T. BLACKER et al. “CUBIT Geometry and Mesh Generation Toolkit 15.3 User Documentation,” SAND 20170-6895 W, Sandia National Laboratories (2017).

Cited by 10 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. Impact of fusion reactor neutronics modeling for transmutation and thermal feedback ^*;Nuclear Fusion;2023-10-25

2. Shutdown dose rate analysis with the Shift Monte Carlo radiation transport code and modular verification workflow;Fusion Engineering and Design;2023-09

3. Fuel cycle depletion validation and code-to-code verification studies for High Flux Isotope Reactor highly and low-enriched uranium fuel designs;Annals of Nuclear Energy;2023-09

4. Layered CAD/CSG geometry for spatially complex radiation transport scenarios;Annals of Nuclear Energy;2023-02

5. Development of radiation sources for nuclear analysis beyond ITER bio-shield: SRC-UNED code;Computer Physics Communications;2022-06