Safety analysis of inadvertent control rods withdrawal of RSG-GAS research reactor for various initial powers-Reference-Cited by-同舟云学术

Safety analysis of inadvertent control rods withdrawal of RSG-GAS research reactor for various initial powers

Published:2024-09 Issue: Volume:426 Page:113405
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Khakim Azizul^ORCID,Hastuti Endiah Puji,Rohanda Anis,Dwijayanto R. Andika Putra,Adrial Hery,Yogatama Farisy

Funder

National Research and Innovation Agency Republic of Indonesia

Publisher

Elsevier BV

Reference11 articles.

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2. A comparative assessment of independent thermal-hydraulic models for research reactors: The RSG-GAS case;Chatzidakis;Nuclear Engineering and Design,2014

3. International Atomic Energy Agency, Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report, SSG-20 (Rev.1). Vienna: IAEA, 2022.

4. Transient analysis of simulaneous lofa and RIA in RSG GAS Reactor after 32 years operation;Isnaini;Jurnal Teknologi Reaktor Nuklir TRI DASA MEGA,2020

5. Safety analysis of MTR type research reactor during postulated beam tube break inducing positive reactivity;Khakim;Ann Nucl Energy,2014

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1. Preface for the ”OUTCOMES AND ACHIEVEMENTS FROM RESEARCHES ORIENTING THE FUTURE IN NUCLEAR FISSION TECHNOLOGY: Asia South-East (Vietnam, Thailand, Indonesia, Malaysia, Singapore, Bangladesh) and Australia”;Nuclear Engineering and Design;2024-11