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EUROTRANS – DM1
ENEA Activities on EFIT Safety Analysis
ENEA – FIS/NUCBologna - Italy
WP5.1 Progress Meeting Tractebel / Brussels, March 17, 2006
G. Bandini, P. Meloni, M. Polidori
OUTLINE
Planned Activities on EFIT Safety Analysis
Transient Analysis with RELAP5/PARCS
Use of SIMMER-III in MEGAPIE Safety Study and DM4 - DEMETRA
SGTR Analysis with SIMMER-III
Preliminary SIMMER-III Results
ENEA Activities on EFIT Safety Analysis
Analysis of DBC and DEC transients with RELAP5/ PARCS coupled code
Analysis of the SGTR and water-lead interaction with SIMMER-III code
Transient Analysis with RELAP5/PARCS Planned Approach
Capability to treat global system behavior coupled with dynamic core response in transient conditions
Investigation of whole spectrum of accidental DBC scenarios and DEC conditions (no severe accidents)
Main differences respect to PDS-XADS to address code upgrading and activity planning:
Lead instead of LBE as coolant
Large positive reactivity potentials without prompt Doppler
Preliminary investigation of safety issues to support core design
Transient Analysis with RELAP5/PARCS Completed and in Progress Activity
Inplementation of Lead thermodynamics and physics properties in the last RELAP version MOD3.3 (capable to be coupled with most recent PARCS versions)
Modification of v2.4 PARCS version to treat external source (hexagonal geometry, multi-group energy description)
First coupled calculations and modelling of EFIT core (preliminary design) in progress
Use of SIMMER-III in MEGAPIE Safety Study
Calculations of LBE-Water Interaction Accident for MEGAPIE
Comparison with FZK calculation with MATTINA code
SIMMER-III MATTINA
Validation of SIMMER-IIIon JAERI Experiments
LBE-Water Interaction Test
SIMMER-III and Test resultcomparison(vapor volume)
Use of SIMMER-III in DM4-DEMETRA
Lead-Water interaction experiments will be performed in the Facilities (LIFUS and/or CIRCE) of ENEA/Brasimone site
SIMMER-III code will be used in pre- and post-test analysis of these experiments
Qualification of SIMMER-III models in connection with these experiments is proposed by ENEA in close cooperation with the University of Pise
Based on the results of this work and eventual code model limits some model development work could be envisaged and proposed
ENEA asks for the agreement by the SIMMER-III development team (JNC, FZK and CEA) to perform this task in close cooperation with the University of Pise (under responsibility of ENEA)
Analysis SGTR Accident in EFITPreliminary SIMMER-III Calculations
Use of a simplified 2-D cylindrical geometry
Boundary conditions according to EFIT ANSALDO design
Stagnant lead inside the vessel
Lead liquid fuel, Water coolant in SIMMER-III lead-water interaction simulation
1 to 5 steam generator tube rupture
EFIT DesignSIMMER-III ModellingSimplified R-Z Geometry (29 x 41)
R
Z
SGTR Accident in EFITSimplified Assumptions in SIMMER-III Calculations
Reactor Vessel
Lead mass = 1850 tons (LBE properties with Tmelting = 328 °C)
Lead temperature = 400 °C
Cover gas volume = 41 m3 (T = 400 °C, P = 1 Bar)
Steam Generator
Tube inside diameter = 14.2 mm
Liquid mass = 31.1 kg; steam mass = 25.3 kg
Volume = 0.32 m3; void fraction = 84.7%
Pressure = 140 Bar; Temperature = 335 °C
Tube Rupture (1 and 5 SG tubes)
Downwards flow at the heat hexchanger bottom
Mass flowrate (1 tube) = 1.2 – 1.6 kg/s (steam and liquid mixture)
SG Break Mass Flowrate
Break Mass Flowrate (5 Tubes)
0
1
2
3
4
5
6
7
8
0 5 10 15 20Time (s)
Mas
s F
low
rate
(kg
/s)
liquid
steam
total
Break Mass Flowrate (1 Tube)
0.0
0.3
0.6
0.9
1.2
1.5
1.8
2.1
2.4
0 5 10 15 20 25 30Time (s)
Mas
s F
low
rate
(kg
/s)
liquid
steam
1 Tube
MaterialFractions
1 Tube RuptureTime = 0 – 30 s
0.1 s 1 s
3 s 10 s 30 s
MaterialFractions
5 Tubes RuptureTime = 0 – 30 s
0.1 s 1 s
3 s 10 s 30 s
System Pressure
1 Tube Rupture
t = 30 s
System Pressure
5 Tubes Rupture
t = 30 s
1 to 5 SGTube Rupture Comparison
Break Mass Flowrate
0
1
2
3
4
5
6
7
8
0 5 10 15 20 25 30Time (s)
Ma
ss
Flo
wra
te (
kg
/s) 1 Tube
5 Tubes
Vessel Cover Gas Pressure
0
100000
200000
300000
400000
500000
600000
0 5 10 15 20 25 30Time (s)
Pre
ss
ure
(P
a)
1 Tube
5 Tubes
SG Secondary Side Pressure
0.0E+00
2.0E+06
4.0E+06
6.0E+06
8.0E+06
1.0E+07
1.2E+07
1.4E+07
1.6E+07
0 5 10 15 20 25 30Time (s)
Pre
ss
ure
(P
a)
1 Tube
5 Tubes
Main Conclusions from SGTR Analysis
More suitable geometry must be chosen to model the SGTR in EFIT reactor with the SIMMER code (2-D or 3-D ?)
Boundary conditions are still uncertain
Preliminary calculations show that steam explosion effects are not of concern in the SIMMER-III evaluation
Fast vapour expansion outside the break causes a significant movement of lead mass that impacts onto the vessel upper structures
An almost linear increase of the cover gas pressure is computed by SIMMER-III in the time frame of tens of seconds