The document deals with the description of results obtained by two Relap5/mod2 code versions in the pre-test blind simulation of an experiment performed in the VVER (water cooled- Water Moderated Energy Reactor) experimental simulator PMK-NVH installed at the Budapest Atomic Energy Research Institute in Hungary. The Relap is the well-known computer code developed at Idaho National Laboratory in US: the code is in use at UNIPI since more than a decade. The PMK-NVH loop is an Integral Test Facility (ITF) simulating with reduced height, full pressure, modulated linear power a Russian (Gidropress) type VVER-440. The concerned test was selected by International Atomic Energy Agency (IAEA) as Standard Problem Exercise 2 (SPE 2). The document describes the results of the pre-test calculation submitted (by UNIPI) to Hungary before the execution of the test. This is called blind pre-test analysis: the comparison of about 40 calculated time trends with measured data (once the experiment is performed: this is part of the SPE documentation issued as IAEA report) allows an objective evaluation of the capabilities of the computer code and of the code user team in predicting the scenario of an accident. This is relevant for demonstrating the capabilities in evaluating safety margins of existing NPP, with main reference to VVER (present case).

"IAEA SPE-2: RELAP5/MOD2 pre-test calculations and comparison with data measured in the Hungarian PMK-NVH experimental facility"

D'Auria F.
Co-primo
Writing – Review & Editing
;
1987-01-01

Abstract

The document deals with the description of results obtained by two Relap5/mod2 code versions in the pre-test blind simulation of an experiment performed in the VVER (water cooled- Water Moderated Energy Reactor) experimental simulator PMK-NVH installed at the Budapest Atomic Energy Research Institute in Hungary. The Relap is the well-known computer code developed at Idaho National Laboratory in US: the code is in use at UNIPI since more than a decade. The PMK-NVH loop is an Integral Test Facility (ITF) simulating with reduced height, full pressure, modulated linear power a Russian (Gidropress) type VVER-440. The concerned test was selected by International Atomic Energy Agency (IAEA) as Standard Problem Exercise 2 (SPE 2). The document describes the results of the pre-test calculation submitted (by UNIPI) to Hungary before the execution of the test. This is called blind pre-test analysis: the comparison of about 40 calculated time trends with measured data (once the experiment is performed: this is part of the SPE documentation issued as IAEA report) allows an objective evaluation of the capabilities of the computer code and of the code user team in predicting the scenario of an accident. This is relevant for demonstrating the capabilities in evaluating safety margins of existing NPP, with main reference to VVER (present case).
1987
DCMN RL
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/11568/895468
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
  • ???jsp.display-item.citation.isi??? ND
social impact