You need JavaScript to view this

Thermohydraulic analysis of the IAEA standard problem test on the PMK-NHV facility; Termohidraulicna analiza standardnega problem MAAE na poskusni napravi PMK-NHV

Abstract

International Atomic Energy Agency (IAEA) has supported a standard test problem simulating small break loss of coolant accident on the test facility PMH-NHV in Budapest. The present pretest analysis of that transient was done using the computer code RELAP4/MOD6. The results were compared to the measurements data and to data of 19 other laboratories around the world that have performed the same analysis. The correspondence of the results to the measured data is reasonable. There are bigger discrepancies, which in turn influence other variables. (author)
Authors:
Stritar, A [1] 
  1. Institut Jozef Stefan, Ljubljana (Yugoslavia)
Publication Date:
Jul 01, 1987
Product Type:
Conference
Report Number:
INIS-RS-0630
Resource Relation:
Conference: 31. Conference - ETAN'87: Society for Electronics, Telecommunications, Automation, and Nuclear Engineering, ETAN'87: 31. Konferencija za elektroniku, telekomunikacije, automatiku i nuklearnu tehniku, Bled (Yugoslavia), 1-5 Jun 1987; Other Information: 2 refs., 7 figs
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; COMPARATIVE EVALUATIONS; EXPERIMENTAL DATA; IAEA; LOSS OF COOLANT; R CODES; SIMULATION; THERMAL HYDRAULICS
OSTI ID:
20843063
Country of Origin:
Serbia
Language:
Slovenian
Other Identifying Numbers:
TRN: RS07RA199015833
Availability:
Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCA
Submitting Site:
INIS
Size:
7 pages
Announcement Date:
Mar 26, 2007

Citation Formats

Stritar, A. Thermohydraulic analysis of the IAEA standard problem test on the PMK-NHV facility; Termohidraulicna analiza standardnega problem MAAE na poskusni napravi PMK-NHV. Serbia: N. p., 1987. Web.
Stritar, A. Thermohydraulic analysis of the IAEA standard problem test on the PMK-NHV facility; Termohidraulicna analiza standardnega problem MAAE na poskusni napravi PMK-NHV. Serbia.
Stritar, A. 1987. "Thermohydraulic analysis of the IAEA standard problem test on the PMK-NHV facility; Termohidraulicna analiza standardnega problem MAAE na poskusni napravi PMK-NHV." Serbia.
@misc{etde_20843063,
title = {Thermohydraulic analysis of the IAEA standard problem test on the PMK-NHV facility; Termohidraulicna analiza standardnega problem MAAE na poskusni napravi PMK-NHV}
author = {Stritar, A}
abstractNote = {International Atomic Energy Agency (IAEA) has supported a standard test problem simulating small break loss of coolant accident on the test facility PMH-NHV in Budapest. The present pretest analysis of that transient was done using the computer code RELAP4/MOD6. The results were compared to the measurements data and to data of 19 other laboratories around the world that have performed the same analysis. The correspondence of the results to the measured data is reasonable. There are bigger discrepancies, which in turn influence other variables. (author)}
place = {Serbia}
year = {1987}
month = {Jul}
}