歯154배영직.PDF

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1 2002 (DBADOSE) Development of Doe alculation Program(DBADOSE) Incorporating Alternative Source Term Due to Deign Bai Accident * *, **, **, ** **, * ( ) 167 ** ( ) (PWR) TID [1] Reg Guide 14[2], TID NR NUREG-1465[3], (IRP) IRP-9[4], IRP-26[5], IRP-60[6], IRP-26, NUREG-1465 IRP-60 (DBADOSE ) DBADOSE POSTDBA[7] STARDOSE[8], Abtract Source term preented in TID and Regulatory Guide 14 have been ued for radiological analyi of deign bai accident for licening exiting preurized water reactor (PWR) However, more realitic and phyically-baed ource term baed on reult of tudy and experiment for about 30 year after the publication of TID wa developed and preented in NUREG-1465 publihed by NR in 1995 In addition, IRP ha been reviing doe concept and criteria through the publication of IRP-9, 26, 60 and recommended effective doe concept rather than critical organ concept ince the publication of IRP-26 Accordingly, multipurpoe computer program called DBADOSE incorporating alternative ource term in NUREG-1465 and effective doe concept in IRP-60 wa developed omparion of reult of DBADOSE with thoe of POSTDBA and STARDOSE wa performed and verified and no ignificant difference and inaccuracy were found DBADOSE will be ued for evaluation of licening according to the dometic law that are expected to be revied in the near future 1 (PWR) 1

2 TID Reg Guide 14, NR 1962 TID NUREG-1465, (IRP) IRP-2, IRP-9, IRP-26 IRP-60, IRP-26 NR NR NUREG-1465 TID Reg Guide 14, NUREG-1465 IRP-26 (10FR20, 10FR50, 10FR100 ), (Reg Guide 1183[9] SRP1501) [10] 2003 [11] NUREG-1465 IRP-60, IRP (LOA) (Non-LOA) - (Steam Line Break, SLB) - (Feedwater Line Break, FWLB) - (RP Locked Rotor, RP LR) - (ontrol Rod Ejection Accident, EA) - (Letdown Line Break, LDLB) - (S/G Tube Rupture, SGTR) - (Fuel Handling Accident, FHA) 211 (LOA) 5 (Annulu) (, ) 2

3 1 1 core = (i) = (i/ft 3 ) V = (ft 3 ) u = (i/ ft 3 ) Vu = (ft 3 ) = (ft 3 /hr) Rc = (1/hr) R = (1/hr) λ S = (1/hr) Ep = (%) 1 = (Anulu area) (i/ ft 3 ) V1 = (ft 3 ) 2 = (Anulu area) (i/ ft 3 ) V2 = (ft 3 ) Rf = (cfm) Rv = (cfm),, 8,, ) - (t=0) 0, 1 (1) 2,V 2 λ S S,V S R R Bypa F R ore R U,V U I,V I / 1 LOA 3

4 - 1 (2) - 1 (3) - 1 (4) ) SRP 652[12] NUREG/R-5966[14], DBADOSE - 1 (5) (6) - 1 (7) - 1 (8) (9), (10), (11) ),, 4

5 F1 F1+ F2 ( ) F2 F3 F2+F3 2 1 LOA, (1) V d / dt = R λ V ( Rl + Pg) c core dcy (2) V a da / dt = (10 fb) Rl λdcy Va a Rv a (3) dq / dt = fb ( Rl + Pg) + Rv a (4) d R / dt = ( R i + f 1 + f 2 ) Q ( λ dcy + R t ) R V (5) d / dt = f R c core ( λ + λ dcy ) V f ( Rl + Pg) ( u ) V d / dt = (1 f ) R λ V (1 f )( Rl + Pg) (6) u u c core dcy u u u ( ) u V d / dt = Rl (1 f ) { f (1 f ) } { λ V + a a b u dcy a (7) E R + R } f f v a (8) dq / dt = ( f b Rl + ( Pg (1 E pg )) ( f + (1 f ) u ) + (1 E f ) Rv a (9) d R / dt = ( Ri (1 Et ) + R f ) Q ( λ dcy + Rt ) R (10) E = 0 (10 E ) (10 E ) t 1 i c t = f1 + Ec f3 + f (11) R 2 V: (ft 3 ), d/dt : (i/ft 3 -ec ), Rc : (1/hr), core : (Bq), λ : (1/hr), : (i/ft 3 ), Rl: (ft 3 /hr ), Pg: (ft 3 /hr ), fb: (bypa), Rv : (cfm ), dq/dt : (Bq/ec), E f :, R f : (cfm) E c : (%), R f : (1/ec), F : /, : (cfm), f : /, E pg :, E f : R f : (cfm), E I : (%), E c : (%), f1 : (cfm), f2 : (cfm), f3 : (cfm) a :, i : intake, Q :, : pray, u : unpray, R : control room dcy 5

6 212 (Non-LOA) Non-LOA 3 4 3, 4 Q p Q & = Q & p ( 12) p, p Fuel ( / ) RS ( ) TT( ) Envir( ) Fuel RS ASG(Affected S/G) Envir Fuel RS ISG(Intact S/G) Envir Fuel RS DNSR( ) Envir Fuel SFP( ) FB( ) Envir ( ), Non-LOA Fuel ( / ) RS (, SFP ) SS(,,, ) Envir( ) ompartment fuel,, c, env, fuel p, d dt d dt d dt = r ( + λ) r = ( + λ) c = + R r e ( 1 f r ) ( + λ c DFe c Q & 1 f r r + DF d dt d dt e e c gi 1 ( Pre-accident Iodine Spike) ( 13-a) (Generated Iodine Spike) ) c ( 13-b) ( 14) = ( 15) c + = ( ) ( 16) r r + SI afw = ( ) ( 17) e 6

7 m r f r m e RS Steam Env m SI Liquid m afw 1/DF e SG 3 Non-LOA ( ) RS m SI m rb Air Liquid f rb F bdg F 1/DF rb BDG Env 4 Non-LOA ( ),, m, ompartment,,, f, DF, R, Q r, e, i, afw,,, 4 (13)~ (17) (13)~ (17) dx dt = ax + by + cz + d ( 18) X n+ 1 = (1 + a dt) X n + b dt Y n + c dt Z n + d dt ( 19), (13)~ (17)(18) (19) 2 2 ompartment 7

8 2 Non-LOA a) X a b Y c Z d r ( + λ) 1 e c ( + λ) DF e c r ( 1 f r ) c Q - f r r m & e DF e c - m & r SI c r afw e m & b) X a b Y d rb ( + λ) Fbdg bdg ( + λ) V bdg Q - ( f f rb rb rb + ) DFrb Vbdg F bdg DF - bdg - F m & rb + SI 22 (total effective doe, TED) D = X Q ( DF Q ) ( 20) ED / EDi i i D = X Q Br ( DF Q ) ( 21) ID / IDi i i (20) (21) D ED, D ID, X/Q, Br, DF Edi DF IDi i, Q I i 8

9 3 DBADOSE 5 (LOA) LOA NONLOA DBADOSE icrooft Viual Baic 60 GUI(Graphic Uer Interface), FORTRAN Digital Viual FORTRAN FORTRAN GUI 2 (Baic+FORTRAN) (External Shell), (Dynamic Link Library, DLL), Window 95, 98 Window NT DOS Viual Baic (DBADOSE) LOA NONLOA : VB GUI : FORTRAN DLL : : 4 41 LOA 5 (DBADOSE) LOA POSTDBA STARDOSE, POSTDBA, STARDOSE, X/Q, LOA TID NUREG-1465, 9

10 42 LOA LOA POSTDBA STARDOSE, POSTDBA joint frequency STARDOSE, POSTDBA STARDOSE TID IRP-30 POSTDBA 5, STARDOSE 6 POSTDBA STARDOSE, POSTDBA STARDOSE 43 NONLOA NONLOA Non-LOA NONLOA LOA STARDOSE, 44 NONLOA NONLOA 7, 7 STARDOSE NONLOA 10% (Xe-135m : 152min, Xe-138 : 142min) 10% NONLOA STARDOSE Holdup Time % (EAB LPZ ) 10% 5 DBADOSE Reg Guide 14, NUREG-1465, SRP 64 SRP 652, NUREG/R-5966 TID IRP-30 IRP-60, DBADOSE,,, DLL 10

11 DBADOSE,,, 1) TID-14844, alculation of Ditance Factor for Power and Tet Reactor Site, US AE, ) Regulatory Guide 14, Aumption Ued for Evaluating the Potential Radiological onequence of a Lo of oolant Accident for Preurized Water Reactor, Rev2, US NR, ) NUREG-1465, Accident Source Term for Light Water Nuclear Power Plant, US NR, ) IRP, Publication 9, Recommendation of the International ommiion on Radiological Protection, ) IRP, Publication 26, Recommendation of International ommiion on Radiological Protection, ) IRP Publication 60, 1990 Recommendation of the International ommiion on Radiological Protection, IRP, ) Uer anual for POSTDBA, S&L Program No ,1978 8) STARDOSE Uer anual, Rev0, Poletar Applied Technology, Inc, ) Regulatory Guide 1183, Alternative Radiological Source Term for Evaluating Deign Bai Accident at Nuclear Power Reactor, US NR, ) ,,, ) , ( ),, ) SRP 652, ontainment Spray a a Fiion Product leanup Sytem, USNR, ) NUREG/R-5966, A Simplified odel of Aerool Removal by ontainment Spray, SAND , US NR, June

12 3 2 2 (i) LOAPOSTDBA ( 1) 2 (i) LOA STARDOSE ( 2) Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E ) 1 = (LOA )/(POSTDBA ) 2 = (LOA )/(STARDOSE ) (i) LOA POSTDBA ( 1) LOASTARDOSE ( 2) Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E ) 1 = (LOA )/(POSTDBA ) 2 = (LOA )/(STARDOSE ) 12

13 5 POSTDBA LOA POSTDBA ( ) (rem) (rem) (EAB) TID E E E E IRP E E E E TID E-01 (LPZ) 109E E E IRP E E ) = (LOA )/(POSTDBA ) 162E E STARDOSE LOA STARDOSE (rem) (rem) (EAB) TID E E E E IRP E E E E TID E-01 (LPZ) 146E E E IRP E E E E TID E E E E E E IRP E E ) = (LOA )/(STARDOSE ) 102E E E E

14 7 2 (i) 1) NONLOA STARDOSE 2) Kr 85m Kr 85 Kr 87 Kr 88 Xe131m Xe133m Xe133 Xe135m Xe135 Xe138 I 131E I 132E I 133E I 134E I 135E I 131O I 132O I 133O I 134O I 135O E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E-03 E E E E E E E E E E E E E ) E =, O=, 2) = (NONLOA )/(STARDOSE ) 8 ( ) (rem) NONLOA STARDOSE ) 383E E E E E E E E E E E E ) = (NONLOA )/(STARDOSE ) 14

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歯154배영직.PDF

歯154배영직.PDF