Development of a Fast Breeder Reactor Fuel Bundle-Duct Interaction Analysis Code—BAMBOO: Analysis Model and Validation by the Out-of-Pile Compression Test-Reference-Cited by-同舟云学术

Development of a Fast Breeder Reactor Fuel Bundle-Duct Interaction Analysis Code—BAMBOO: Analysis Model and Validation by the Out-of-Pile Compression Test

Published:2001-10 Issue:1 Volume:136 Page:14-23
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Uwaba Tomoyuki¹,Tanaka Kosuke¹

Affiliation:

1. Japan Nuclear Cycle Development Institute, O-arai Engineering Center 4002, Narita-cho, O-arai-machi, Higashi-ibaraki-gun, Ibarakiken, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT01-A3225

Reference9 articles.

1. R. G. HILL and R. J. JACKSON, “Bundle Duct Clearance of HEDL Mixed Oxide Subassemblies,” HEDL-SA-897, Hanford Engineering Development Laboratory (1976).

2. Deformation analysis of fuel pins within the wire-wrap assembly of an LMFBR

3. Validation of Fuel Bundle Mechanical Performance Code ÉTOILE with Bundle/Duct Interaction Experimental Data

4. Étoile: A Three-Dimensional Finite Element Code for LMFBR Fuel Bundle Analysis

5. Development of a 3-D FBR fuel bundle-to-duct interaction analysis code marse

Cited by 11 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. Thermal hydraulic analysis of a deformed SFR fuel assembly using CFD;Annals of Nuclear Energy;2023-02

2. Application and Benchmarking of a Novel Coupled Methodology for Simulating the Thermomechanical Evolution of Sodium-cooled Fast Reactors Fuel Subassemblies;Nuclear Engineering and Design;2021-04

3. Full-scale finite element analysis of deformation and contact of a wire-wrapped fuel bundle subject to realistic thermal and irradiation conditions;Nuclear Engineering and Design;2020-08

4. Analyses of deformation and thermal-hydraulics within a wire-wrapped fuel subassembly in a liquid metal fast reactor by the coupled code system;Nuclear Engineering and Design;2017-06

5. Progress of thermal hydraulic evaluation methods and experimental studies on a sodium-cooled fast reactor and its safety in Japan;Nuclear Engineering and Design;2017-02