Experimental study of temperature distribution and development of a power monitoring channel for the IPR-R1 TRIGA® research nuclear reactor

Author:

Zacarias Mesquita Amir,Fernandes de Almeida Vitor,Artur Pinheiro Palma Daniel

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

Reference17 articles.

1. Bärs B. & Vaurio J. Power Increasing Experiments on a TRIGA Reactor. Technical University of Helsinki, Department of Technical Physics. Report No. 445. Otaniemi Finland. 1966.

2. Steady-state thermal-hydraulic analysis of the Moroccan TRIGA Mark II reactor by using PARET/ANL and COOLOD-N2 codes;Boulaich;Nuclear Engineering and Design.,2011

3. Büke T. & Yavuz H. Thermal-Hydraulic Analysis of the ITU TRIGA Mark-II Reactor. Proceeding of 1st Eurasia Conference on Nuclear Science and its Application. Izmir, Turquia, October 23-27, 2000.

4. Characterization of the TRIGA Mark II reactor full-power steady state;Cammini;Nuclear Engineering and Design.,2016

5. Thermal hydraulic analysis of the IPR-R1 TRIGA research reactor using a RELAP5 model;Costa;Nuclear Engineering and Design.,2010

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