The document deals with the description of results obtained by two Relap code versions (Relap4/mod6 and Relap5 Mod1) in the pre-test open simulation of a LOCA 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 1 (SPE 1). 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 ISP documentation issued as OECD 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-1: pre-test calculation of a SBLOCA in the Hungarian PMK-NVH experimental facility performed at Pisa University by RELAP4/MOD6 and RELAP5/MOD1-EUR computer codes
D'Auria F.
Primo
Writing – Review & Editing
;
1986-01-01
Abstract
The document deals with the description of results obtained by two Relap code versions (Relap4/mod6 and Relap5 Mod1) in the pre-test open simulation of a LOCA 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 1 (SPE 1). 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 ISP documentation issued as OECD 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).I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
