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