Title: Coupled Thermal-hydraulic and Neutronic Model for the Asc
1Coupled Thermal-hydraulic and Neutronic Model for
the Ascó NPP using RELAP5-3D/NESTLE
- L. Batet, R. Pericas, E. Morales and F. Reventós
- Technical University of Catalonia (UPC)
- Department of Physics and Nuclear Engineering
2Contents
- Introduction
- Ascó NPP description
- Ascó model description
- Thermal-hydraulic
- Neutronics
- Model testing
- Steady State
- Load Rejection transient
- Main Steam line Break transient
- Sensitivities
- Conclusions
3Introduction
- The Dept. of Physics and Nuclear Engineering of
the (UPC) holds a large background in the use of
TH codes for the Safety Analysis of Nuclear Power
Plants (NPP). The Thermal Hydraulic Studies Group
has been cooperating for 15 years with the
operators of the Catalan nuclear plants, Ascó (2
units) and Vandellós II (all of them 3 loop PWR
Westinghouse design). - Ascó-1 NPP started commercial operation on
December 1984. - RELAP5 model developed by its analysts.
- Extensively qualified and validated.
- The presentation represents a continuation of the
presentation in 2006 seminar L. Batet et al.
Status of the activities related to the use of
RELAP5-3D at the Technical University of
Catalonia
4Introduction
- A 3D vessel component and neutronic data have
been added to the existing model allow full 3D
NKTH coupling. - Neutronic data taken from previous model RELAP5
(NRC)/PARCS. We have faced problems in adapting
the data. - What we are presenting is a set of preliminary
calculations. - The work has been basically done by undergraduate
students (following a previous work presented in
the 2006 seminar). - This is a first step done with the aim of
achieving full neutronic-TH simulation
capabilities in the UPC.
5Ascó NPP description
- Ascó-I is owned by ENDESA (100).
- Ascó-II is owned by ENDESA (85) and IBERDORLA
(15). - Units are located close to Tarragona, in the
north east of Spain, and they use the Ebro River
as a final heat sink.
6Ascó NPP description
- The actual nominal power of each unit is 2952.3
MWt and 1028 MWe. - The reactor vessel is cold head type.
- 3 Siemens (type SG 61 W/D3) steam generators. FW
fed directly to the upper part of the downcomer
via J-tubes. The circulation ratio on the
secondary side of the steam generators is 3.65 at
rated power. - The auxiliary feed water system is impulsed by
one turbo pump and two motor pumps. In the plant
there are, among others, control systems for the
reactivity (rods and boron), primary pressure,
pressurizer level, steam dump and steam generator
level. The reactor protection system includes
safety valves in the pressurizer and the steam
generator.
7Ascó NPP description
- Summary of the plant main features
8Plant thermal-hydraulic model
- The RELAP5 model of Ascó NPP is prepared to
simulate both units of the plant. - Only slight changes are needed, concerning mainly
to the fuel load, to switch from one to another. - The model includes
- Hydrodynamic elements (primary, secondary, safety
systems and auxiliary systems) - Heat structures, and
- Control and protection systems.
- The model has been prepared for RELAP5/MOD3.2 and
has been subjected to a thoroughly validation and
qualification process, which includes the
simulation of transients occurred in the plant
itself.
9Plant thermal-hydraulic model
- Summary of the model degree of detail
10Plant thermal-hydraulic model
11Plant thermal-hydraulic model
AFW
FW modeling
MFW
12Plant thermal-hydraulic model
Logic diagram (partial) of the MFW control system
13Vessel thermal-hydraulic model
- In order to perform 3D NK calculations, in the
Ascó model, the vessel has been converted in a
set of RELAP5-3D multid components. - The 3D vessel model had been previously developed
for Vandellòs-II by an undergraduate student (X.
Sabaté). - A previous R5/Parcs model existed (used in the
MSLB benchmark)
Pseudo 3D Model RELAP5/PARCS
1D Vessel Model Relap5/3.2
3D Vessel Model Relap5-3D
14Vessel thermal-hydraulic model
- One of the nodalization proposals
- RPV consists of 5 multid (cartesian
cylindrical) - 500 hydraulic nodi
- Some of them are disabled (by applying small
volume factors) in the corners
21 core channels
15Vessel thermal-hydraulic model
- Model adopted for the vessel
- Vessel inlets and downcomers.
- 3 azimuthal sectors .
- 1 radial sector.
- 5 axial levels.
- Primary circuit to vessel inlets (120º).
- Bypass.
- 8 azimuthal sectors .
- 1 radial sector.
- 1 axial level.
- Core.
- 21 thermal-hydraulic nodes
- 9 axial levels including Core entrance, Core
exit, Core auxiliary exit and Core. - 5x5 Cartesian matrix.
- Lower plenum.
- 8 azimuthal sectors.
- 2 radial sectors.
- 1 axial level.
- Upper head.
- 8 azimuthal sectors .
- 2 radial sectors.
- 2 axial levels.
16Vessel thermal-hydraulic model
Core bypass
Core
Downcomer
Core
Upper plenum and Upper head
Lower plenum
17Vessel neutronic model
- Neutronic data taken from previous model
R5/PARCS. - At that time (2001) Cross Section libraries were
taken from SEANAP (Univ. Polit. Madrid) - Additional work has been done to transfer from
PARCS format values to NESTLE format values. - We have faced problems in adapting the data
18Vessel neutronic model
- 17x17 Matrix 157 elements/level.
- 13 axial levels.
- 2 reflector levels.
- 11 power levels.
- 190 different compositions (XS).
- Mapping from 13 levels (NK) ? 8 levels (TH).
Dont ask me why
19Vessel neutronic model
157 neutronic nodes
20Control Rod core distribution
Control Rod group A
Control Rod group B
Control Rod group C
Control Rod group D
21Model Testing
- Steady state
- Load rejection transient.
- Load rejection (50) corresponding to the testing
after fuel reload (Ascó I, 1999, cycle 13) - MSLB
- UPC participated in the OECD-CSNI PWR MSLB
benchmark with RELAP5/PARCS. As a culmination, a
MSLB was calculated for the Ascó NPP (A. Cuadra,
JL Gago, F. Reventós, Analysis of a
Main-Steam-Line Break in Ascó NPP, ANS Technical
Paper - Thermal Hydraulics, Volume 146, Number
1, April 2004, Pages 41-48)
22Steady State
- Steady state calculation at Beginning Of Life
conditions, for the Ascó-1 NPP cycle 13.
23Steady State
Something to be improved in the kinetics data or
in mapping
24Steady State
25Load rejection
- Transient from 100 to 50 steady state power in
12 seconds. - Control Rod group D insertion.
- Intervention of kinetics, TH, control systems
the actuation of one system affecting the others - We usually perform this test whenever we make an
improvement to the model. - We performed this test with the 1D TH (point
kinetics) model using R5-3D in 2006
26Load rejection
27Load rejection
Control Rod group D
28Load Rejection
Power axial profiles
29Load rejection
Axial top level temperature evolution
Power evolution
30Main Steam Line Break
- Objective
- Try to get the good results obtained after the
MSLB benchmark using R5/PARCS - Loop 2 pipe break at 10,060 seconds (loop 2)
inside containment (double-guillotine between
nodes 750-752). - Stop AFW Turbopumps, 3 min after the break.
- Flow control to 15 of AFW motorpumps, 4 min
after the break. - Base case 1 sensitivity no safety injection
(no credit for boron injection)
31MSLB Base Case
32MSLB Base Case
Isnt the primary a closed system?
33MSLB Base Case
Axial top level temperature evolution
Power evolution
34MSLB Sens. No safety injection
35MSLB Sens. No safety injection
36Ongoing work and conclusions
- The well validated Ascó model for R5 has been
converted into a 3D model by substituting the
vessel volumes by multid components. - 3D NK using Nestle
- XS library adapted from previous Parcs model
(facing problems) - On going try to refine the conversion process
and use the gt600 compositions in the original
model - At present we depend on borrowed XS
- On going initiating a research line in
neutronics (try to use SCALE to produce 2 group
XS)
37Ongoing work and conclusions
- The goal is to have fully 3D NKTH computational
capabilities at the THSG. - Plant data available to (partially) validate the
future model (e.g. temperature and power maps for
the 50 load rejection transient) - Comments and suggestions are welcome.