Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation-Reference-Cited by-同舟云学术

Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation

Published:2013-11 Issue: Volume:264 Page:153-160
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Freixa J.,Kim T.-W.,Manera A.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference14 articles.

1. LOCA frequency evaluation using expert elicitation;Tregoning;Nucl. Eng. Des.,2007

2. The United States Nuclear Regulatory Commission. “10 CFR Risk-Informed Changes to Loss-of-Coolant Accident Technical Requirements” Proposed Rule, Federal Register, 70(214), 2005.

3. The ROSA-V Group. “ROSA-V Large Scale Test Facility (LSTF) system description for the third and fourth simulated fuel assemblies”. Technical Report JAERI-Tech 2003-037, Japan Atomic Energy Agency, 2003.

4. Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facility including uncertainty evaluation;Freixa;Nucl. Eng. Des.,2011

5. CSNI, “Bemuse Phase II report, re-analysis of the ISP-13 exercise, post test analysis of the LOFT L2-5 Test Calculation” Committee on the Safety of Nuclear Installations OECD Nuclear Energy Agency, 2005.

Cited by 15 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 systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity;Nuclear Engineering and Design;2024-05

2. Effect of Locoregional Treatments in Hepatocellular Carcinoma: What Are the Pathologic/Radiologic Milan Criteria?;Experimental and Clinical Transplantation;2023-10

3. OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment;Nuclear Engineering and Design;2022-04

4. Methodology for phenomenological code assessment with integral test data;Nuclear Engineering and Design;2022-02

5. Assessing the effects of switching from multi-channel to three-dimensional nodalisations of the core in TRACE;Nuclear Engineering and Design;2021-11