Preliminary safety evaluation for CSR1000 with passive safety system

Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario

“…In the simulation, the break at the cold leg occurs at 0.5 s. The reactor scram signal is produced after the cold-leg break occurrence by detecting the signal of ''low pressure (24 MPa)'' (Wu et al, 2014). After a 0.5 s delay, the control rods are inserted, which resulting in a reduction of the core power.…”

“…This provides the confidence that the SCTRAN code is applicable for safety analyses of SCWR concepts. Subsequently, the SCTRAN has been applied in analyzing the accident scenarios for the CSR1000, which is a pressure-vessel type of the SCWR concept being developed at the Nuclear Power Institute of China (Wu et al, 2014), and the SCWR concept being developed at the China General Nuclear Power Group (Wu et al, 2013).…”

SCWR transient safety analysis code SCAC-CSR1000

“…The actuation conditions of the safety system is summarized by Xi'an Jiaotong University (Wu et al, 2014). The control system is shown in Fig.…”

“…The overall parameters CSR1000 (Wu et al, 2014) is a thermal spectrum reactor, which is cooled and moderated by light water. The thermal efficiency is 43.5%.…”

“…Using different codes or programs to analysis the same reactor type can make the reliability more confident. As for CSR1000, the Preliminary safety evaluation has been made (Wu et al, 2014). The analyses have shown that the core design of CSR1000 is feasible and the proposed passive safety system is capable.…”