International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA)

Table 2

Relevant hardware characteristics of considered PWR simulators and Doel-2 nuclear plant.

	Quantity	SPES	LOBI/Mod2	BETHSY	LSTF/ROSA IV	DOEL-2
1	Reference reactor	W-PWR	KWU-PWR	FRA-PWR	W-PWR	W-PWR
	Reference reactor power (MWt)	2775	3900	2700	3423	1187
2	Mximum power (MWt)/% of nominal power	9.0/138	5.4/100	3.0/10	10.0/14	1187.0/100
3	Reported Kv	1/427	1/712	1/100	1/48	1/1
4	No. of rods	97	64	428	1064	21659
5	Operating pressure of primary loop (MPa)	15.	15.8	15.51	15.5	15.5
6	Operating pressure of secondary loop (MPa)	6.1	6.54	6.91	7.3/7.4	5.88
7	Primary loop volume (m^3)	0.622	0.643	2.88	8.3	168.5
8	No. of U-tubes for each steam generators	13/13/13	8/24	34/34/34	141/141	3260/3260
9	Internal diameter of U-tubes (mm)	15.4	19.6	19.7	19.6	19.6
10	L/D ratio of Hot leg	57.2	73.1/119.1	38	17.8	10.64
11	Total head (“a” in Figure 1) m
	max	16.08	16.72	18.34	18.4	14.7
	min	15.91	16.47	16.87	16.9	13.2
12	Linear rod power at 5% overall power^(*)(Kv/m)	1.27^(°)	1.08	0.86	0.91	1.12
13	Actual Kv^(+)	1/640	1/619	1/144	1/48	1/2.5

^(*)The % value is the power related to the reported K_v.
⁽⁺⁾ Related to LSTF.
^(°)To compensate heat losses.