This pa per pres ents an over view of the “scal ing strat egy”, in par tic u lar the role played by the coun ter part test meth od ol ogy. The re cent stud ies deal ing with a scal ing anal y sis in light wa ter reactor with spe cial re gard to the VVER 1000 Rus sian re ac tor type are pre sented to dem on strate the phe nom ena im por tant for scal ing. The adopted scal ing ap proach is based on the se lec tion of a few char ac ter is tic pa ram e ters cho sen by tak ing into ac count their rel e vance in the be hav ior of the tran sient. The adopted com puter code used is RELAP5/Mod3.3 and its ac cu racy has been dem on strated by qual i ta tive and quantitative evaluation. Comparing experimen tal data, it was found that the investigated facilities showed sim i lar be hav ior con cern ing the time trends, and that the same ther mal hy drau lic phe - nom ena on a qual i ta tive level could be pre dicted. The main re sults are: PSB and LOBI main pa ram e ters have sim i lar trends. This fact is the con fir ma tion of the va lid ity of the adopted scal ing ap proach and it shows that PWR and VVER reactor type behavior is very sim i lar. No new phe nom ena oc curred dur ing the coun ter part test, de spite the fact that the two fa cil i ties had a dif fer ent lay out, and the al ready known phe nom ena were pre dicted cor rectly by the code. The code ca pa bil ity and ac cu racy are scale-in de pend - ent. Both char ac ter is tics are nec es sary to per mit the full scale calculation with the aim of nu clear power plant behavior prediction.

Analysis of measured and calculated counter part test data in PWR and VVER1000 simulators

D'AURIA, FRANCESCO SAVERIO;
2005-01-01

Abstract

This pa per pres ents an over view of the “scal ing strat egy”, in par tic u lar the role played by the coun ter part test meth od ol ogy. The re cent stud ies deal ing with a scal ing anal y sis in light wa ter reactor with spe cial re gard to the VVER 1000 Rus sian re ac tor type are pre sented to dem on strate the phe nom ena im por tant for scal ing. The adopted scal ing ap proach is based on the se lec tion of a few char ac ter is tic pa ram e ters cho sen by tak ing into ac count their rel e vance in the be hav ior of the tran sient. The adopted com puter code used is RELAP5/Mod3.3 and its ac cu racy has been dem on strated by qual i ta tive and quantitative evaluation. Comparing experimen tal data, it was found that the investigated facilities showed sim i lar be hav ior con cern ing the time trends, and that the same ther mal hy drau lic phe - nom ena on a qual i ta tive level could be pre dicted. The main re sults are: PSB and LOBI main pa ram e ters have sim i lar trends. This fact is the con fir ma tion of the va lid ity of the adopted scal ing ap proach and it shows that PWR and VVER reactor type behavior is very sim i lar. No new phe nom ena oc curred dur ing the coun ter part test, de spite the fact that the two fa cil i ties had a dif fer ent lay out, and the al ready known phe nom ena were pre dicted cor rectly by the code. The code ca pa bil ity and ac cu racy are scale-in de pend - ent. Both char ac ter is tics are nec es sary to per mit the full scale calculation with the aim of nu clear power plant behavior prediction.
2005
D'Auria, FRANCESCO SAVERIO; Cherubini, M; Galassi, G. M.; Muellner, N.
File in questo prodotto:
Non ci sono file associati a questo prodotto.

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/97631
 Attenzione

Attenzione! I dati visualizzati non sono stati sottoposti a validazione da parte dell'ateneo

Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
  • ???jsp.display-item.citation.isi??? ND
social impact