German Standard Problem No. 6: 'Rupture of a steam line within the HDR containment leading to early two-phase flow (V-44)'
Description
Objective of the experiment was the investigation of the containment behaviour after a rupture of the main coolant line under nearly realistic conditions, such as large vent openings between the compartments of the containment, installations and almost full scale dimensions. Particularly the objectives include mechanical and thermal loads upon the containment structures caused by the energy and mass flow through the ruptured steam line into the containment (fig. I). The participants of the standard problem No. 6 were supposed to calculate for three time periods (short time period 0 - 2 seconds, medium time period 0 - 50 seconds, long time period 0 - 1500 seconds) the following variables: Time-dependent pressure and temperature buildup in the various containment compartments; time history of differential pressure between adjacent containment compartments; heat transfer to the containment structures. Except some isolated deficiencies in the physical models the analytical methods used for the calculation of containment behaviour are satisfactory for the accuracy needed for the licensing procedure. (orig./HP)
Availability note (English)
Available from FIZ Karlsruhe.Abstract (German)
Zielsetzung des Experiments war die Untersuchung des Containmentverhaltens nach dem Bruch einer Hauptkuehlmittelleitung unter weitgehend realistischen Bedingungen (grosse Ueberstroemoeffnungen zwischen den Containmentraeumen, Einbauten, realistische Dimensionen). Hierzu gehoeren insbesondere mechanische und thermische Lasten auf die Containmentstrukturen, verursacht durch den Energie- und Massenstrom aus der gebrochenen Leitung in das Containment (s. Bild I). Die Teilnehmer am Standardproblem mussten fuer drei Zeitbereiche (Kurzzeit 0 - 2 s, Mittelzeit 0 - 50 s, Langzeit 0 - 1500 s) u.a. folgende Groessen berechnen: zeitabhaengiger Temperatur- und Absolutdruckaufbau in den einzelnen Containmentraeumen; zeitabhaengiger Differenzdruckverlauf zwischen benachbarten Containmentraeumen; Waermeuebergang an die Containmentstrukturen. Abgesehen von punktuellen Schwachstellen in der Modelltechnik ist die fuer das Containmentverhalten verwendete Analysemethodik im Rahmen der fuer das Genehmigungsverfahren erforderlichen Genauigkeit unter Beachtung konservativer Eingabe-Parameter zufriedenstellend. (orig./HP)Additional details
Additional titles
- Subtitle (English)
- Report of comparisons
- Original title (German)
- Deutsches Standardproblem Nr. 6: 'Dampfleitungsbruch im HDR-Containment mit frueher Zweiphaseneinstroemung (V-44)'
- Original subtitle (German)
- Vergleichsbericht.
Publishing Information
- Imprint Pagination
- 84 p.
- Series
- Schriftenreihe Reaktorsicherheit und Strahlenschutz.;Ergebnisberichte, Untersuchungen, Studien, Gutachten.
- Report number
- BMU--1991-317
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 23049005
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CONTAINMENT; HDR REACTOR; LICENSING PROCEDURES; LOSS OF COOLANT; REACTOR SAFETY EXPERIMENTS; RUPTURES; STEAM LINES; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; ADMINISTRATIVE PROCEDURES; ENRICHED URANIUM REACTORS; EVALUATION; EXPERIMENTAL REACTORS; FAILURES; FLUID FLOW; PIPELINES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract BMU SR 279/1
- Secondary number(s)
- GRS-A--1223.