Research Article

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

Table 1

Nuclear design parameters [22].

TypesMTR

Number of standard fuel elements at the typical working core40
Fuel plates per standard fuel element21
Number of fuel control elements at the typical working core8
Fuel plates per fuel control element15
Active length, (cm)60
Type of fuelU3Si2–Al
Enrichment, %19.75
Uranium density in meat, (g/cm3)2.96
Cladding materialAlMg2
Type of absorberFork type
Material absorberAg–in–Cd
Thickness (mm)3.38
Cladding materialSteels

Thermal-hydraulic design
Heat generation in reactor core, (MW)30
Total flow rate of primary system, (kg/s)860
Design value of minimum flow rate, (kg/s)800
Effective flow rate for fuel cooling plates, (kg/s)618
Nominal inlet temperature, (°C)40.5
Average temperature increases in reactor core, (K)10.7
Average outlet temperature in reactor core, (°C)50.57
Outlet maximum temperature of the hot channel, (°C)75.3
The surface area of fuel plates, (m2)72.29
Available heat flux, (W/m2)41.5 × 104
Maximum heat flux for normal operation, (W/m2)263.3 × 104