歯174구경회.PDF

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1 000 KALIMER - Creep-Fatigue Damage Evaluation of KALIMER Reactor Internal Structures for Elevated Temperature, 150 KALIMER ASME Code Case N Abstract In this paper, the design limits of the stress, the accumulated inelastic strain, and a creep-fatigue damage are evaluated using the ASME Code Case N-01-4 to check the structural integrity of the baffle annulus structures in KALIMER reactor internal structures, which are subjected the elevated temperatures during normal operations For the loading conditions, the normal operating temperatures and the seismic OBE are considered From the evaluations, the stress limits are satisfied with enough margins and the inelastic strain limits also satisfied when using the simplified inelastic method For the creep-fatigue damage evaluations, the conservative parameters are used if possible From the creepfatigue damage evaluations, all parts of interest satisfy the design rules but the reactor vessel liner part at the elevation of hot pool free surface has large creep damage 1 KALIMER,,, (Baffle annulus structure)

2 (1) KALIMER 50 o C KALIMER 0 - KALIMER () ASME Code Case N-01-4 (), () KALIMER ASME Code Case N KALIMER Fig1,,,,,,,, Fig Fig Fig4,, (Collector cylinder) COMMIX Fig5 Fig6 [4] Fig7 Hot standby(0 o C)

(Heat-up) (Cool-down) Fig8 Hot standby(0 o C) 00 Reactor Head (RH) 00 850 5000 1650 Thermal Insulation Plate (TIP) Baffle

Containment Vessel (CV) Upper Internal Structure (UIS) 1000 1900 140 Inlet Pipe (IPP) Inlet Plenum (IP) Flow Guide (FG)

Elevations and Flow Path in RI 1 : Conduction : Convection : Radiation T gas =40 o C EL 00 Hot Pool Free Surface EL 1 EL 15

3 (Heat-up) (Cool-down) Fig8 Hot standby(0 o C) 00 Reactor Head (RH) Thermal Insulation Plate (TIP) Baffle Plate (BP) Reactor Vessel Liner (RVL) (BP) Reactor Vessel (RV) UIS 6050 Support Barrel (SB) Separation Plate (SP) Containment Vessel (CV) Upper Internal Structure (UIS) Inlet Pipe (IPP) Inlet Plenum (IP) Flow Guide (FG) Radiation Shield (RS) Core Support (CS) Core Fig 1 Conceptually Designed KALIMER RI Fig Elevations and Flow Path in RI 1 : Conduction : Convection : Radiation T gas =40 o C EL 00 Hot Pool Free Surface EL 1 EL 15 EL 44 1 EL 65 EL 105 Cold Pool SB RVL RV CV CC SW EL 15 Fig Axisymmetric Analysis Model of RI Fig4 Heat Transfer Mechanism in Baffle Annulus

Operation (8760 hrs) 50 0 1 Time Fig7 Assumed Normal Operation Cycles in Analysis Stress Intensity or Strain Maximum Value for

4 Section No10 Section No5 Section No Section No9 Section No8 Section No Section No4 Section No7 Section No1 Section No6 Fig 5 Temperature Distributions(Normal Operation) Fig 6 Stresses and Section Points o C Time Block From Hot Standby To Steady State Operation (8760 hrs) Time Fig7 Assumed Normal Operation Cycles in Analysis Stress Intensity or Strain Maximum Value for Steady State Operation Minimum Value for Hot Standby Condition (assumed as zero stress and strain) Fig 8 Assumed Stress Cycles in Analysis Time

5 47 o C ASME Section III Subsection NG (5) 47 o C ASME Code Case N-01-4 (4) ( ) ( 10) - ASME Code Case N-01-4 [4] 4-41 A, B C - p n N + j= 1 d j k= 1 q t T d k D (1) D = total creep-fatigue damage P = number of different cycle types (n) j = number of applied repetitions of cycle type, j (N d ) j = number of design allowable cycles for cycle type, j q = number of time intervals for the creep damage calculation (T d ) k = allowable time duration determined from the stress-to-rupture curves n N d Fig 9 Creep-Fatigue Damage Curve Fig 9 ASME Code Case t Td and 16 Stainless Steels -1/4Cr-1Mo and Ni-Fe-Cr Alloy 800H

6 N ε equiv, i = (1 + ν * [( ε ) ( ε xi zi ε ε yi xi ) ) + ( ε yi + ( γ ε xyi zi ) + γ + yzi + γ i [] () ν * = 0 ν * = 05 Table 1() ε max Table1 Maximum Value of Calculated Equivalent Strain Ranges (Normal Operation) Node No De x x 10 - De y x 10 - De z x 10 - De xy x 10 - De max x 10 - Lower SB/SP Upper SB/SP SB/BP SP/SB BP/SB SP/RVL RVL/SP RVL-Cold Free RVL at BP Elev RVL- Hot Free zxi )] 1/ () () ε mod ε mod S = S * K ε max ()

7 ε mod ε = K S * σ ε max max mod ε max (4) = K e K (5) S * S (Stress indicators) K K ( P + Q + F) eff = (6) ( P + Q) eff Ds mod S Fig10 Composite Stress-Strain Curve Fig S rh - (Isochronous stress-strain curve) (, 6) S rh [4] Table 100Cm 5Cm ε t ε = Kν ε mod + K ε (7) t (7) K ν S * s s / S rh O / O c K 10+ f ( K 10) (8) ν = ν f (Triaxiality Factor, TF) ASME Code Case N-01-4 FIG Y-140- TF 1 = (9) 1 From Isochronous Curve with Zero Time [( σ σ ) + ( σ σ ) + ( σ σ ) ] 1/ 1 e / De max KDe max De mod e σ + σ + σ 1

8 K ν ASME Code Case N-01-4 FIG Y-140- K ek ε max E / S m K ek ε max E / S m 10 K ν=1 (8) K ν=1 (7) ε c (Test No B-1) 15σ c ε c -, 15σ c, (P) (n) x P) Table 1, 4, 6, 7 47 o C Table 4 OBE ASME 10 6 Table Calculated Parameters for Modified Equivalent Strain Range(Normal Operation) Node No ε max x 10 - S rh S * S K K e

9 Table Calculated Parameters for Total Strain Range (Normal Operation) K Node No TF f ek ε max E / S m K ν K ν ε mod x10 - ε c x Node No Table 4 Calculated Fatigue Damages for Normal Operation ν ε mod K x10 - Thermal Load (0 Cycles) K ε x10 - c Total Stain Range ε x10 - t Seismic OBE (50 Cycles) ε x10 - t Fatigue Damage P n = j= N 1 d Lower SB/SP Upper SB/SP SB/BP SP/SB BP/SB SP/RVL RVL/SP RVL-Cold Free RVL at BP Elevation RVL- Hot Free j

10 4 - (1) ASME Code Case N-01-4 t H = 6800 hours(0 ) T HT Fig 7 0 t = t / n = 6800/0 = 8760 hours ASME Code Case N (S) k - Table 4 T HT S j S j t S r j H j S r = S 8G ( S S ) (10) j 0 j r S j j S t (10) G [ σ [ σ ( σ 0( σ + σ )] + σ )] σ 1, σ, σ σ 1 σ σ (10) G 10 G=10 Fig 11 r (11) Stress, s S j ASME Code Case N σ c S r S LB S LB 15 s c, - 15σ c Constant Temperature = T HT Time t Fig11 Stress-Relaxation Limits for Creep Damage j Table 5 S LB S j ( ) S j

11 Fig1 16 ASME Code Case N S j ( t ) k, 8760 hours Node Nos Table 5 Calculated Parameters for Creep Damages (Normal Operation) t H, hrs T HT, o C t j, hrs Relaxed stress level at time t S j S r G S r S LB Upper SB/SP SB/BP BP/SB RVL-Cold Free RVL at BP Elevation RVL- Hot Free S j 10 Adjusted Uniaxial Relaxation 15s c Stress, MPa S r Constant Temperature = 50 o C t j Time, hours Fig 1 Stress-Relaxation Limits for Creep Damages at Node 16 (T d ) k ASME Code Case N (S) k K / =09 Table 6

12 0876 Table 4 Fig9 - - Node Nos Table 6 Calculated Creep Damage for Normal Operation (T) k, o C (S) k, MPa ( t ) k, hrs (S) k /K /, MPa q (T d ) k, hrs Creep Damage q t = k = T 1 d Upper x SB/SP x SB/BP x x BP/SB x x RVL-Cold Over Free Over RVL at BP x Elevation x RVL- Hot x Free x k 5 KALIMER 0 ASME Code Case N KALIMER - -

13 ,, [1] Gyeong-Hoi, Koo, Design Description of KALIMER Reactor Internal Structures, KALIMER/MS40-DD-01/1998, RevA, KAERI, 1999 [],,, KALIMER,, 1999 [] Cases of ASME Boiler and Pressure Vessel Code N-01-4, ASME, 1994 [4] Gyeong-Hoi, Koo, Evaluation of Structural Integrity of KALIMER Reactor Internal Structures for Elevated Temperature, KALIMER/MS40-AR-04/000, RevA, KAERI, 000 [5] ASME B&P Code Section III Subsection NG, ASME, 199 [6] LK Severud, Creep-Fatigue Assessment Methods Using Elastic Analysis Results and Adjustments, Transactions of the ASME, Vol11, pp4-40, 1991

12(4) 10.fm

12(4) 10.fm KIGAS Vol. 12, No. 4, December, 2008 (Journal of the Korean Institute of Gas) l x CNG» v m s w ½ Á y w» œw (2008 9 30, 2008 12 10, 2008 12 10 k) Numerical Analysis for Temperature Distribution and Thermal

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歯174구경회.PDF