Transient Analysis of Simultaneous Lofa and Ria in RSG-Gas Reactor After 32 Years Operation

Abstract

During the operation of the research reactor RSG-GAS, there are many design parameters should be verified based on postulated accidents. Several design basis accidents (DBA) such as loss of flow accident (LOFA) and reactivity-initiated accident (RIA) also have been conducted separately. This paper discusses about possibility of simultaneous accidents of LOFA and RIA. The accident analyses carry out calculation for transient condition during RIA, LOFA, and postulated accident of simultaneous LOFA-RIA. This study aims to conduct a safety analysis on simultaneous LOFA and RIA, and investigate the impact on safety margins. The calculations are conducted by using the PARET code. The maximum temperature of the center fuel meat at nominal power of 30 MW and steady state conditions is 126.10°C and MDNBR of 2.94. At transients condition, the maximum center fuel meat temperature for LOFA, RIA and simultaneous LOFA-RIA are consecutively 132.99°C, 135.67°C and 138.21°C, and the time of reactor trip are 3.2593s, 3.6494s and 2.7118s, respectively. While the MDNBR for LOFA, RIA and simultaneous LOFA-RIA are respectively at transient condition are 2.88, 2.58 and 2.63, respectively. It is shown that, simultaneous LOFA-RIA has the fastest trip time. In this case, the low flow trip occurs first in advance to over power trip. From these results, it can be concluded that the RSG-GAS has adequate safety margin against transient of simultaneous LOFA-RIA.Keywords: RSG-GAS, Simultaneous, LOFA, RIA, PARET

An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes

“…e reactor design seeks to make the RIA probability as low as possible and design the core to respond as quickly as possible to stop the increase in reactor power if an accident related to this condition occurs. Steady-state analysis and transient RIA condition analysis of the RSG-GAS reactor have been carried out previously using various programs using a few group cross-section data of fresh fuel elements [7][8][9][10].…”

Analysis of control rod effect on the safety operation parameter of the RSG-GAS Core

“…The moderator and coolant is water. The minimum flow rate of primary cooling system is 800 kg/s and flow rate in the fuel elements is 618 kg/s [2], [3]. The rsearch aims to evaluate the effect of control rods position to neutronic, kinetic, parameter and thermal hydraulic parameter at steady state at nominal power of 30 MW.…”