Safety analysis code SCTRAN development for SCWR and its application to CGNPC SCWR

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

“…It has been verified against the blowdown simulation from supercritical pressures to subcritical pressures (Markku and Joona, 2008) and compared against predictions of the APROS code. Code-to-code benchmarking exercises were performed between the SCTRAN and the RELAP5-3D codes for the postulated loss-of-feed-water accident (LOFA) and LOCA in the US SCWR concept (Wu et al, 2013). Comparable predictions were observed between the two codes.…”

“…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).…”

“…The objective of this study is to examine the effectiveness of heat transfer in preventing cladding melting for the postulated large-break loss-of-coolant accident (LOCA) coupled with the total loss of emergency core cooling (LOECC) scenario. As there are little codes which are able to simulate the trans-critical process of LOCA and evaluate the radiation heat transfer at the same time, a radiation heat transfer model is added to system code SCTRAN (Wu et al, 2013). …”

Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System

“…The development of a transient analysis code is presented in this paper. SCTRAN [27], which originally is a safety analysis code for SCWR, is selected to be upgraded to simulate the S-CO 2 Brayton cycle by adding accurate thermal property and constitutive model for CO 2 , turbomachinery models (including compressor, gas turbine, and shaft). Due to the lack of experiment data, the current validation strategy is to make simple validation with limited experiment data and code-to-code comparison with other codes like GAMMA+.…”

“…The item in the left hand of the equation denotes the neutron flux variation with time, the first item in the right hand of the equation denotes the neutron leakage rate, the second item denotes the neutron absorption rate, and the third and fourth item separately represent the neutron production rate of prompt neutron and delayed neutron. SCTRAN's ability to simulate the transients and accidents of SCWR has been verified by comparing with APROS code and RELAP5-3D code [27], respectively. It has been widely used in transient and accident analysis for supercritical water reactor [28,29].…”