Safety Analysis of Advanced CANDU Reactor-700 (ACR-700) during Transient and Emergency Condition using ACR Simulator

Muhammad Fathoni Shidik; Rida Siti Nuraini Mahmudah

doi:10.21831/jsd.v10i1.39803

Safety Analysis of Advanced CANDU Reactor-700 (ACR-700) during Transient and Emergency Condition using ACR Simulator

Muhammad Fathoni Shidik, Jurusan Pendidikan Fisika, Fakultas Matematika dan Ilmu Pengetahuan Alam, Universitas Negeri Yogyakarta, Indonesia
Rida Siti Nuraini Mahmudah, Jurusan Pendidikan Fisika, Fakultas Matematika dan Ilmu Pengetahuan Alam, Universitas Negeri Yogyakarta, Indonesia

10.21831/jsd.v10i1.39803

Abstract

The development of nuclear technology leads to improvement in nuclear power plant design. The latest generation of the nuclear reactor tries to rely more on passive system to minimize the human intervention and increase the safety of the nuclear power plant itself. ACR-700 is designed to be able to cope with some transients condition. This study try to simulate the condition of ACR-700 during the transient condition loss of one of reactor coolant pump using ACR Simulator developed by IAEA. The ACR-700 safety system successfully identify the malfunction and stop the malfunction to escalate. In addition to that, this paper also try to simulate the previous transient condition with another malfunction in reactor setback and setback system, one of the safety system of the ACR-700.

Keywords

ACR 700; transient condition; ACR simulator; pump loss

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DOI: https://doi.org/10.21831/jsd.v10i1.39803