Published July 1997 | Version v1
Journal article

Post test calculations to 11% break loca experiments on the integral test facility ISB-VVER using the thermalhydraulic code ATHLET

Creators

  • 1. Forschungszentrum Rossendorf e.V. (FZR), Dresden (Germany)

Description

The considered test was a break on the upper plenum with different modes of emergency core cooling. The reference case was the non-availability of emergency cooling. Injecting the emergency coolant into the cold leg, no increasing of rod cladding temperatures was observed, but natural circulation instabilities occurred. Injecting the cooling into the hot leg, the cooling situation was getting worse. Due to the injected cold emergency coolant, the fluid density in the discharge volume was enhanced and the break mass flow increased. The observed events in the test were reproduced by the code with good agreement. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
170
Journal Issue
1-3
Journal Page Range
p. 3-7.
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
Research and technology - our future.
Original Conference Title
Jahrestagung Kerntechnik (JK '95) - Gemeinsame Veranstaltung des Deutschen Atomforums e.V. (DAtF) und der Kerntechnischen Gesellschaft e.V. (KTG): Forschung und Technik - unsere Zukunft
Acronym
Annual meeting on nuclear technology '95 - joint meeting of Deutsches Atomforum e.V. (DAtF) and Kerntechnische Gesellschaft e.V. (KTG)
Dates
17-18 May 1995.
Place
Nuremberg (Germany).