LEADER Project – WP5
Giacomino Bandini - ENEA/Bologna
LEADER 4th WP5 MeetingKarlsruhe, 22 November 2012
Task 5.5: “Analyses of representative DEC events of the ETDR”.
Foreseen work schedule. Distribution of work
2
Task 5.5 - Objectives and planning
Nov 2012
3
Task 5.5 Budget
4
Distribution of work (1/2)
Case Number Transient Description
ENEA KIT-G NRG JRC/IE KTH
RELAP5 SIM-LFR SPECTRA SIMMER / TRACE
RELAP5 / CFD
TR-4
Reactivity insertion
(enveloping SGTR, flow
blockage, core compaction)
Reactivity insertion (voiding of part of active region
enveloping voids introduction due SGTR, core compaction, fuel blockage) = 250 pcm
Reactor at hot full power (HFP)
X X X X X X (*) X (**)
TO-3
Reduction of FW
temperature + all pumps stop
Loss of one preheater (feedwater temperature
reduction from 335oC down to 300oC)
All primary pumps are stopped
Reactor is tripped
X X X X X
TO-6Increase of FW
flowrate+ all pumps stop
20 % increase in feedwater flowrate
All primary pumps are stopped
Reactor is tripped
X X X X X
T-DEC1
Complete loss of forced flow +
Reactor trip fails (total
ULOF)
All primary pumps are stopped
Feedwater system available Reactor trip fails
X X X X X X (*) X
T-DEC3Loss of SCS+ Reactor trip
fails (ULOHS)
All primary pumps are operating
DHR system is operatingReactor trip fails
X X X X X X (*)
T-DEC4
Loss of off-site power (LOOP) +
Reactor trip fails (ULOHS +
ULOF)
All primary pumps are stopped
SCS is lostDHR system is operating
Reactor trip fails
X X X X X X
Note (*) JRC/IE possible contribution with TRACE code is subordinated to the correct implementation in the source of the lead properties,
Note (**) KTH plans to look at core voiding due to leak from steam generator by CDF analysis(simulation of bubble transport to the core in Lagrangian framework by turbulent coolant voiding taking into account uncertainties in: bubble size distribution, different correlations for bubble drag in lead, locations of possible leakage from SG, leak rate, etc.)Results from CFD analysis of bubble transport will be used as input for Reactivity insertion transient analysis withn RELAP5
DEC Transients
Transients to be analyzed for Pb-cooled ALFRED Design (LEADER project)
Burnup State
Transients analyzed for Lb-cooled ALFRED Design
BO
C
EO
C
5
Distribution of work (2/2)
Case Number Transient Description
ENEA KIT-G NRG JRC/IE KTH
RELAP5 SIM-LFR SPECTRA SIMMER / TRACE
RELAP5 / CFD
TR-4
Reactivity insertion
(enveloping SGTR, flow
blockage, core compaction)
Reactivity insertion (voiding of part of active region
enveloping voids introduction due SGTR, core compaction, fuel blockage) = 250 pcm
Reactor at hot full power (HFP)
X X X X X X (*) X (**)
Note (*) JRC/IE possible contribution with TRACE code is subordinated to the correct implementation in the source of the lead properties,
Note (**) KTH plans to look at core voiding due to leak from steam generator by CDF analysis(simulation of bubble transport to the core in Lagrangian framework by turbulent coolant voiding taking into account uncertainties in: bubble size distribution, different correlations for bubble drag in lead, locations of possible leakage from SG, leak rate, etc.)Results from CFD analysis of bubble transport will be used as input for Reactivity insertion transient analysis withn RELAP5
DEC Transients
Transients to be analyzed for Pb-cooled ALFRED Design (LEADER project)
Burnup State
Transients analyzed for Lb-cooled ALFRED Design
BO
C
EO
C
T-DEC3Loss of SCS+ Reactor trip
fails (ULOHS)
All primary pumps are operating
DHR system is operatingReactor trip fails
X X X X X X (*)
T-DEC4
Loss of off-site power (LOOP) +
Reactor trip fails (ULOHS +
ULOF)
All primary pumps are stopped
SCS is lostDHR system is operating
Reactor trip fails
X X X X X X
T-DEC5
Partial blockage in the
hottest fuel assembly
Reactor trip failsThe maximum acceptable flow reduction factor has to
be determined
X X X X X X
T-DEC6 SCS failureAll primary pumps are
operatingDHR system totally fails
Reactor is tripped
X X X X X
Note (*) JRC/IE possible contribution with TRACE code is subordinated to the correct implementation in the source of the lead properties, and in any case, restricted by the inability of these system codes to deal with biphasic liquid metal coolants
Note (**) KTH plans to look at core voiding due to leak from steam generator by CDF analysis(simulation of bubble transport to the core in Lagrangian framework by turbulent coolant voiding taking into account uncertainties in: bubble size distribution, different correlations for bubble drag in lead, locations of possible leakage from SG, leak rate, etc.)Results from CFD analysis of bubble transport will be used as input for Reactivity insertion transient analysis withn RELAP5
6
Deliverables
Index Respons. Participants Input Need Date1. Scope ENEA January 2013
2. Introduction ENEA All January 2013
3. Representative DEC scenarios (from the list of transient initiators identified in WP5.3)
ENEA All From Task 5.3(Deliverable D11) May 2012
4. DEC Transient Analysis Results ENEA All Plant and core design (WP2 & 3) December 2012
4.1 Protected Transients ENEA KIT, NRG December 2012
4.2 Unprotected Transients ENEA All December 2012
4.3 Fuel Assembly Blockage ENEA JRC, KIT, NRG December 2012
4.4 Steam Generator Tube Rupture under DEC ENEA KTH December 2012
5. Conclusions ENEA All January 2013
DOCUMENT ORGANIZATION
Responsible ENEAPartners ENEA, KIT-G, JRC-IET, KTH, NRGEstimated MM 20.5