Science and Technology of Nuclear Installations

Research Article

Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies

Table 1

Measurement variables from the IEA-R1 reactor utilized in the COTENP code validation. Temperature variables are measured in the IFA and flow rate and pressure drop are measured in the dummy fuel assembly (ΔP) [22].


Label	Location	Measurement variable

TC2	cladding lateral plate (side reflector)	Temperature (IFA)
TC3	cladding central plate	Temperature (IFA)
TC4	cladding lateral plate (side fuel assembly)	Temperature (IFA)
TC5	cladding lateral plate (side reflector)	Temperature (IFA)
TC6	cladding central plate	Temperature (IFA)
TC7	cladding lateral plate (side fuel) assembly	Temperature (IFA)
TC8	cladding lateral plate (side reflector)	Temperature (IFA)
TC10	cladding central plate	Temperature (IFA)
TC12	cladding lateral plate (side fuel assembly	Temperature (IFA)
TF14	fluid outlet (bottom of the core)	Temperature (IFA)
P	in dummy assembly	Pressure (ΔP assembly)
	in dummy assembly	Coolant velocity (ΔP assembly)
	IFA location (see Figure 7)	Position (6,8)
	DFA location (see Figure 7)	Position (0,0)