SCWR Research in Korea. Yoon Y. Bae KAERI
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1 SCWR Research in Korea Yoon Y. ae KAERI
2 Organization President Dr. In-Soon Chnag Advanced Reactor Development Dr. Jong-Kyun Park Nuclear Engineering & Research Dr. M. H. Chang Mechanical Engineering & Research Dr. K.. Park Fluid Engineering & Research Dr. Y. Y. ae Thermal HYdraulic & Safety Research Dr. H. D. Kim PSA Dr. J. J. Ha Advanced Fuel Development Dr. D. S. Son PWR Fuel Development Dr. Y. H. Chung GEN IV KALIMER, Dr. D. H. Han SMART. Dr. S. K. Zee Nuclear Data Evaluation lab. 2002/11/19 2
3 Activities Feasibility study sponsored by KISTEP Provide information for decision making of MOST State of art Identify research items Lay foundation of SCWR research Draw attention of research community into SCWR 2002/11/19 3
4 Activities Feasibility study of SCWR concept Design Limits Core Primary and Safety Systems System performance and efficiency (KAERI Internal project) 2002/11/19 4
5 Activities I-NERI Radiolysis and Heat Transfer Studies for Supercritical-Water-Cooled Reactors (SCWRs) Mid to Long Term Nuclear R&D? 2002/11/19 5
6 Preliminary calculation 2002/11/19 6
7 S/G Sizing - Assumptions Use Griem s correlation Nu = Re Pr ρw ρ Assume U-tube length 10m ω Assume 12% of tube length is economizer Overall HTC for economizer and evaporater are 3,355 and 7,565 W/m 2 K /11/19 7
8 S/G Sizing Procedures h i = Nu d 1 = U k tube 1 h i + t k tube + 1 h o ( ) Q = UA T T sat Repeat until Q reaches 4000 MWt ( A = 2πd x) T w = T Q h A i T = T, i+ 1, i + Q m C SG P 2002/11/19 8
9 S/G Sizing - Results 2002/11/19 9
10 S/G Sizing - Results 2002/11/19 10
11 Core Sizing - Assumptions Use ishop s correlation Pitch/Diameter = 1.15 Nu Pr = Re C µ P =, k C P 2/3 Hydraulic diameter 3.26 mm Fuel diameter = 9.16 mm 0.9 Pr h = T W W ρ W ρ h T Tight lattice hexagonal fuel assembly 160 ass y 397 rods(324 fuel)/ass y D L 2002/11/19 11
12 Core Sizing - Procedures T b, i T = b, i 1 + q A m C c p Repeat until T reaches T hot = 565C T w = T b, i + q h i [ h i = f ( Tw,...)] 2002/11/19 12
13 Core Sizing - Results 2002/11/19 13
14 Inputs and Outputs Technical Data System pressure = MPa Steam Generator T COLD = ºC Core power = MWt Heat transfer per S/G = MWt Mass flow rate per S/G = kg/s Total flow area = m 2 Number of tubes = Tube length = m Total heat transfer area = m 2 Mass flux = kg/m 2.s Average heat flux = MW/m /11/19 14
15 Inputs and Outputs Core Fuel diameter = mm Pitch of fuel rod = mm Pitch to fuel diameter = mm Gap between fuel rods = mm Pitch of fuel assembly = mm Hydraulic diameter = mm Number of rod per fuel ass y = 397 Number of fuel rod per fuel ass y = 324 Number of fuel ass y = 160 Cross sect. area of all fuel ass y = m 2 Cross sect. area of all fuel rod = m 2 Net fuel channel area = m 2 Core mass flow rate = kg/s Core mass flux = kg/m 2 s Core heat flux = MW/m 2 Core length = m Average specific power = kw/m RCP power = kw T HOT = ºC 2002/11/19 15
16 Thermal Efficiency From SG MS Reheater Reheater HP TN A C LP TN CON C A To SG FWP COP 2002/11/19 16
17 Thermal Efficiency A: Primary loop, SC condition + secondary of APR1400 (6.895 MPa saturated steam) : Option A + secondary of 20 MPa saturated steam C: Option A + secondary of 20 MPa superheated steam ( T = 100 ) D: Option A + secondary of SC condition, 24 MPa, 500 ) E: High pressure turbine at primary + secondary of APR /11/19 17
18 Thermal Efficiency A C D E Core Power (MWt) Flow rate(kg/s) Primary SG Inlet Pres. (MPa) SG Outlet Pres. (MPa) SG Inlet Temp. (C) SG Outlet Temp. (C) Steam Pres. (MPa) Secondary Steam Temp. (C) Steam Flow rate (kg/s)) Feedwater Temp. (C) Feedwater Pres. (MPa) Results Elec. Power (MWe) Pump Power (MW) ( ) 66 (39+27) Efficiency (%) /11/19 18
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