Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics

Table 2

Thermal-hydraulic conditions for fuel lattice simulation.

Position (mm)	Upward coolant density (kg⋅m^−3)	Upward coolant temperature (K)	Cladding temperature (K)	Liner temperature (K)	Insulator temperature (K)	Pressure tube temperature (K)	Downward coolant temperature (K)	Downward coolant density (kg⋅m^−3)	Fuel temperature (K)	Center tube temperature (K)
4875	67.7	898	1028	869	679	454	625	621.1	1437	761
4625	70.7	875	1015	847	665	450	626	615.6	1443	751
4375	74.4	849	996	823	651	446	628	610.5	1437	738
4125	78.9	823	970	798	635	441	629	606.0	1410	726
3875	84.3	796	940	773	620	436	630	602.1	1371	713
3625	90.8	771	909	750	606	432	631	598.6	1328	701
3375	98.5	748	877	729	593	428	632	595.6	1284	690
3125	108.0	727	845	710	581	424	632	593.1	1242	680
2875	119.0	709	814	694	571	421	633	590.9	1200	671
2625	132.7	694	784	682	563	419	633	589.1	1159	664
2375	149.3	682	756	672	557	417	634	587.6	1120	658
2125	169.7	673	733	665	553	415	634	586.2	1083	654
1875	194.8	667	713	660	550	414	634	585.1	1053	651
1625	225.7	663	697	658	548	414	635	584.0	1033	649
1375	263.4	660	685	656	547	414	635	582.9	1017	648
1125	309.3	659	679	655	547	413	635	582.0	1006	647
875	363.7	657	680	654	546	413	635	581.1	995	646
625	423.8	655	685	651	544	412	636	580.3	976	645
375	483.4	651	689	646	541	411	636	579.7	947	643
125	535.8	644	684	638	536	410	636	579.4	907	640