atw 2018-04v6

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atw Vol. 63 (2018) | Issue 4 ı April

Location of the Thermocouples

Thermocouple

| | Fig. 8.

SCWL Maximum EP Temperature in LOFA.

Parameter Value Unit

Pressure 7 MPa

Inlet Flow

Temperature

Max Flow

Temperature

Maximum AC

Pressure Envelop (PE)

Temperature

210 ºC

900 ºC

450 ºC

Mass flow 40 kg/h

Inlet into the interpiping space of the reheater

Output from the interpiping space of the reheater

Entry into the test chamber

Inlet to the reheater piping space

Output from the reheater piping space

Output from the primary side of the heat exchanger

Maximum helium temperature

| | Tab. 4.

Thermocouples position and description.

T1

T2

T3

T4

T5

T6

Tmax

OPERATION AND NEW BUILD 225

| | Tab. 3.

HTHL main parameters calculated during

steady state.

The steady state simulation was

run in null transient mode for 5,000 s

and the stabilized conditions were

reached after 3,500 s. The LOFA

transients was characterized by an

immediate safety shutdown of the

reactor due to the loss of power. As a

result of the SCRAM, the temperature

went immediately down following the

heat generated by decay gamma flux.

Figure 9 shows the calculated

temperature for various thermocouples

positions (according to

Table 4), while Figure 10 represents

the maximum temperatures in the

HTHL PE.

| | Fig. 9.

HTHL Helium temperatures during LOFA.

5 Conclusions

The article provides a brief introduction

about the SUSEN project and the

experimental facilities built in CVŘ in

the Czech Republic for research and

development in support of the safe,

reliable and long‐term sustainable

operation of existing energy facilities

and in development of GIF IV and

fusion technologies. The SUSEN

R&D activities include four complementary

programmes, mentioned in

the introduction, which are focused

on material science, thermal hydraulics,

neutronics, radiation protection,

nuclear chemistry, waste management

and environmental studies. A

significant part of the research programme

is devoted to HTH and SCW

experimental loops, which are going

to be installed into the active core of

the research reactor LVR-15. Both of

| | Fig. 10.

HTHL PE temperature during LOFA.

these unique facilities are challenging

to model and the selection of appropriate

codes was a demanding process.

A special methodology was used for

assessing the abilities of the codes to

simulate these advanced coolants and

to obtain regulatory certificate/ permit

for their use in operational and accident

conditions and for preparation of

the amendment of the LVR-15 FSAR.

These presented activities represent

only starting steps for the further

codes validation which will be based

on benchmarking of the codes with

experimental data provided by the

SCWL and HTHL loops in their

experimental campaigns.

Aknoledgment

The authors would like to thank

Mr. Miroslav Hrehor and Dr. Vincenzo

Romanello for their kind revisions and

suggestions.

The presented work was financially

supported by the Project CZ.02.1.01/

0.0/0.0/15_008/0000293: Sustainable

energy (SUSEN) – 2 nd phase,

realized in the framework of the

Operation and New Build

Experimental and Analytical Tools for Safety Research of GEN IV Reactors ı G. Mazzini, M. Kyncl, Alis Musa and M. Ruscak

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