application of comsol pipe flow module to develop a high ... · develop a high flux isotope reactor...
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Application of COMSOL
Pipe Flow Module To
Develop a High Flux
Isotope Reactor (HFIR)
System Loop Model
Dean Wang
Prashant K. Jain
James D. Freels
COMSOL Conference 2013
October 10, 2013
2 Managed by UT-Battelle for the U.S. Department of Energy
HFIR is a Multi-Purpose High-Performance
Research Reactor
• Operated since 1966 with one of the world’s highest thermal neutron fluxes ~2.5x1015 neutrons/(cm2-s )
• Involute-shaped fuel plates, beryllium reflected, light water-cooled and –moderated, pressurized, flux-trap type research reactor
• Highly enriched uranium (~93% 235U/U) fuel embedded in aluminum-6061 clad
• Cold and thermal neutron scattering, materials irradiation, isotope production, neutron activation analysis
3 Managed by UT-Battelle for the U.S. Department of Energy
Sixties’ Historical Photos of HFIR
HFIR pressure vessel as being lowered into the pool cavity
4 Managed by UT-Battelle for the U.S. Department of Energy
HFIR Primary Coolant System
HFIR Primary Coolant System
5 Managed by UT-Battelle for the U.S. Department of Energy
Schematics of HFIR System Components
Heat Exchanger Cells and Pool Structure
Heat Exchanger Flow Path
Vessel/Core Cross-section
6 Managed by UT-Battelle for the U.S. Department of Energy
HFIR COMSOL System Model Based
on the RELAP5 Model • Three primary loops modeled
• Reactor pressure vessel
– Inner fuel region
– Outer fuel regions
– Target region
– Reflector
• Primary coolant pumps
– Modeled with COMSOL Pump component
– Limited modeling capability: fixed flow, pressure increase, downstream pressure
– Pump curves needed for flow transient
• Heat Exchanger
– Modeled with COMSOL heat transfer component
– Currently, the component cannot define effective heat transfer area
TDJ
92-1
90
91-1
8180-4 80-1 79 77
50-2
52-1 75-4
175-1
173
170
152-4
157
Heat
Exchanger
C
51 53 54 55
64
65687271
TDV
TDJ 84
Reactor
Vessel
Main
Pressurizer
Pump
66
69
551
561
Standby
Pressurizer
Pump
Flow control
valve
Flow control
valve
550
560
Auxiliary
Pressurizer
Pump
TDV
Primary Coolant
Head Tank
TDV
20 Inch Cold Leg in Pipe Tunnel
18 Inch Hot Leg in Pipe Tunnel
check
valve174
Primary
Coolant Pump
75-1
73
70
52-4
57
Heat
Exchanger
D
60-3
60-2
60-1
62-1
74check
valve
Primary
Coolant Pump
Letdown
Valve 63
Letdown
Valve 163
275-1
273
270
260-3
260-2
260-1
252-4
257
Heat
Exchanger
A
274check
valve
Primary
Coolant Pump
Letdown
Valve 263
160-3
160-2
160-1
47
67-5
67-4
67-3
67-2
67-1
92-2
92-3
91-2
91-3
50-1
80-280-3
89
88
50-3
52-2
52-3
75-3
75-2
62-2
152-1
152-2
152-3
175-4
175-3
175-2
162-1
162-2
352-1
352-2
352-3
252-1 252-2
252-3
262-1
262-2
375-3
375-2
375-1
275-5 275-4
275-2
275-3
512
Break 6
513
508
Break 4
509
506
Break 3
507
504
Break 2
505
502
Break 1
503
510
Break 5
511
48
check valve
49
59
check valve
56
571
574
577
PU-1D (70)
Suction
PU-1C (170)
Suction
PU-1A (270)
Suction
83 leakage
76
801
relief valve
802
276 176
803-1 805804
check valve
Cell 110 Cell 111 Cell 113
578
575
572
Reactor Pool
803-2
venturi
HX
Vessel/Core
Pump HL
CL Check Valve
7 Managed by UT-Battelle for the U.S. Department of Energy
Vessel/Core Modeling
• Vessel/Core Components
– Fuel element
– Target
– Control cylinders,
– Reflector
– Core bypass
– Upper and lower plenum
– Outlet
• Inner and outer hot fuel elements
• Core heat loads: 86MW
– Distributed in fuel, target, cylinders, reflectors
– Axial power shape
• Core heat structures needed for transients
8 Managed by UT-Battelle for the U.S. Department of Energy
Heat Exchanger Modeling
• HX bundle consists of 1200 SS tubes
– Average tube length: 710.52 in.
– Tube ID/OD: 0.555/0.625 in.
• The secondary side flow pattern is much more complicated.
– HTC has to be estimated
• COMSOL lumped all tubes into one hydraulic pipe
– User defined primary side Nu = f(Re, Pr)
9 Managed by UT-Battelle for the U.S. Department of Energy
Extra-Vessel Piping
• Lengths and elevations of the piping throughout the primary side were obtained from the RELAP5 deck/document
• Values of Hydraulic Diameter and K-loss were obtained from the RELAP5 model. Modifications were made when necessary.
HL
CL
10 Managed by UT-Battelle for the U.S. Department of Energy
COMSOL vs. RELAP5 – Steady State Run
COMSOL RELAP5
Reactor power (MW) 86.6
Total Loop flow rate (kg/s) 327.4x3
RPV Inlet cold leg temperature (K) 325.56 325.48
RPV Exit Hot leg temperature (K) 346.8 347.2
RPV Inlet coolant pressure (MPa) 2.92 2.91
RPV exit coolant pressure (MPa) 2.31 2.20
Outer core hot fuel outlet coolant temperature (K)
385.08 386.2
Inner core hot fuel outlet coolant temperature (K)
380.1 381.1
11 Managed by UT-Battelle for the U.S. Department of Energy
Temperature Pressure
COMSOL Results – Steady State Run
1D-3D CFD Coupling (under investigation)
12 Managed by UT-Battelle for the U.S. Department of Energy
Advantages of COMSOL-based System
Model of HFIR
• Coupling with same, higher or lower order physics, as needed
– 1D-1D, 1D-2D, 1D-3D, 2D-3D…
– “system-CFD-multiphysics” coupling
• Independent capability for reviewing calculations within the limited scope
• Enhanced interaction between transient and steady state analyses for different applications
• Easily tractable and portable (ease of user management)
• Modern user-interface (ease of model input management)
• More solver options/features (convergence, stability)
• Ease of handling for nonlinear (T,P)-dependent material properties
• Parametric and functional inputs (mathematical dependencies) could be easily implemented
13 Managed by UT-Battelle for the U.S. Department of Energy
Thank you
for your attention.
This presentation has been authored by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the US Department of Energy. The US government retains and the publisher, by accepting the presentation for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this presentation, or allow others to do so, for US government purposes.
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