*---- * TEST CASE TCWW05 * CANDU-6 ANNULAR CELL * WIMS-AECL 69 GROUPS LIBRARY FILE WIMSLIB * POWER (KW) = 615.00000 * BURN POWER (KW/KG) = 31.97130 * URANIUM MASS = 19.23600 * UO2 REAL DENSITY = 10.59300 * UO2 EFF DENSITY = 10.43750 * UO2 TEMPERATURE = 941.28998 * ENRICHMENT = 0.71140 * COOLANT D2 AT % = 99.222 * MODERATOR D2 AT % = 99.911 * NUMBER OF DAYS = 50 * * REF: R. Roy et al. Ann. Nucl. Energy 21, 115 (1994) * *---- * Define variables and initialize * Burnup paremeters * a) Power * = 31.9713 kw/kg for 0.0 to 300.0 days * b) Burnup time interval Delt * = 1 day for 0 to 1 day * = 4 days for 1 to 5 days * = 5 days for 5 to 10 days * = 10 days for 10 to 50 days * = 20 days for 50 to 150 days * = 50 days for 150 to 300 days * c) Days with burnup interval changes * = 1.0, 5.0, 10.0, 50.0, 150.0 and 300.0 days * d) Burnup control time variables Timei, Timef, TotalTime * Timei = initial time * Timef = final time * TotalTime = Final time reached *---- REAL Power Delt Timec Timei Timef TotalTime := 31.9713 1.0 1.0 0.0 0.0 300.0 ; *---- * Define STRUCTURES and MODULES used *---- LINKED_LIST LIBRARY CANDU6S CANDU6F VOLMATS VOLMATF PIJ FLUX BURNUP EDITION DATABASE ISOT ; SEQ_BINARY INTLINS INTLINF ; SEQ_ASCII database ; MODULE GEO: EXCELT: LIB: SHI: ASM: FLU: EVO: EDI: COMPO: DELETE: END: ; PROCEDURE assertS ; *---- * Depletion data from file WIMSLIB format WIMS-AECL * Microscopic cross sections from file WIMSLIB format WIMS-AECL *---- LIBRARY := LIB: :: NMIX 10 CTRA WIMS DEPL LIB: WIMSAECL FIL: WIMSLIB MIXS LIB: WIMSAECL FIL: WIMSLIB MIX 1 560.66 0.81212 O16 = O16 7.99449E-1 D2D2O = D2D2O 1.99768E-1 H1H2O = H1H2O 7.83774E-4 MIX 2 560.66 6.57 Nb93 = NB93 2.50000 BNat = B-NAT 2.10000E-4 Zr91 = ZR91 9.75000E+1 MIX 3 345.66 0.0014 He4 = HE4 1.00000E+2 MIX 4 345.66 6.44 Fe56 = FE56A 1.60000E-1 Ni58 = NI58 6.00000E-2 Cr52 = CR52 1.10000E-1 BNat = B-NAT 3.10000E-4 Zr91 = ZR91 9.97100E+1 MIX 5 345.66 1.082885 O16 = O16 7.98895E-1 D2D2O = D2D2O 2.01016E-1 H1H2O = H1H2O 8.96000E-5 MIX 6 941.29 10.4375010 O16 = O16 1.18473E+1 Xe135 = XE135 0.0 U235 = U235 6.27118E-1 1 U238 = U238 8.75256E+1 1 U236 = U236 0.0 1 Pu239 = PU239 0.0 1 MIX 7 COMB 6 1.0 MIX 8 COMB 6 1.0 MIX 9 COMB 6 1.0 MIX 10 560.66 6.44 Fe56 = FE56A 1.60000E-1 Ni58 = NI58 6.00000E-2 Cr52 = CR52 1.10000E-1 BNat = B-NAT 3.10000E-4 Zr91 = ZR91 9.97100E+1 ; *---- * Geometry CANDU6S : 13 regions annular cluster for self-shielding * CANDU6F : 31 regions annular cluster for transport *---- CANDU6S := GEO: :: TUBE 5 R+ REFL RADIUS 0.00000 5.16890 5.60320 6.44780 6.58750 16.12171 MIX 1 2 3 4 5 CLUSTER ROD1 ROD2 ROD3 ROD4 ::: ROD1 := GEO: TUBE 2 MIX 6 10 NPIN 1 RPIN 0.0000 APIN 0.0000 RADIUS 0.00000 0.6122 0.6540 ; ::: ROD2 := GEO: ROD1 MIX 7 10 NPIN 6 RPIN 1.4885 APIN 0.0000 ; ::: ROD3 := GEO: ROD1 MIX 8 10 NPIN 12 RPIN 2.8755 APIN 0.261799 ; ::: ROD4 := GEO: ROD1 MIX 9 10 NPIN 18 RPIN 4.3305 APIN 0.0 ; ; CANDU6F := GEO: CANDU6S :: SPLITR 6 1 1 1 10 ::: ROD1 := GEO: ROD1 SPLITR 2 1 ; ::: ROD2 := GEO: ROD2 SPLITR 2 1 ; ::: ROD3 := GEO: ROD3 SPLITR 2 1 ; ::: ROD4 := GEO: ROD4 SPLITR 2 1 ; ; *---- * Create the reactor database *---- DATABASE := COMPO: :: EDIT 5 STEP UP 'moderator' COMM 'Multi-parameter reactor database for moderator' ENDC INIT STEP UP 'fuel' COMM 'Multi-parameter reactor database for fuel' ENDC PARA 'BURN' IRRA PARA 'FLUB' FLUB INIT ; *---- * Self-Shielding calculation EXCEL * Transport calculation EXCEL * Flux calculation for keff *---- VOLMATS INTLINS := EXCELT: CANDU6S :: TITLE 'TCWW05: CANDU-6 ANNULAR POWER= 31.971 FUEL TEMP= 941.29' EDIT 0 MAXR 13 TRAK TISO 5 10.0 SYMM 12 ; LIBRARY := SHI: LIBRARY VOLMATS INTLINS :: EDIT 0 NOLJ ; VOLMATF INTLINF := EXCELT: CANDU6F :: TITLE 'TCWW05: CANDU-6 ANNULAR POWER= 31.971 FUEL TEMP= 941.29' EDIT 0 MAXR 31 TRAK TISO 5 10.0 SYMM 12 ; PIJ := ASM: LIBRARY VOLMATF INTLINF ; FLUX := FLU: PIJ LIBRARY VOLMATF :: TYPE K ; assertS FLUX :: 'K-INFINITY' 1 1.117656 ; EDITION := EDI: FLUX LIBRARY VOLMATF :: COND 4.0 MERGE MIX 0 0 0 0 1 0 0 0 0 0 MICR RES SAVE ON 'moderator' ; DATABASE := COMPO: DATABASE EDITION :: EDIT 3 STEP UP * ; EDITION := EDI: EDITION FLUX LIBRARY VOLMATF :: COND 4.0 MERGE COMP MICR 1 Xe135 SAVE ON 'fuel' ; *---- * Burnup loop: for first step BURNUP is created * while for other steps it is modified *---- WHILE Timei TotalTime < DO EVALUATE Timef := Timei Delt + ; IF Timei 0.0 = THEN BURNUP LIBRARY := EVO: LIBRARY FLUX VOLMATF :: DEPL <> <> DAY POWR <> ; ELSE BURNUP LIBRARY := EVO: BURNUP LIBRARY FLUX VOLMATF :: NOEX DEPL <> <> DAY POWR <> ; ENDIF ; LIBRARY := SHI: LIBRARY VOLMATS INTLINS :: EDIT 0 NOLJ ; PIJ := DELETE: PIJ ; PIJ := ASM: LIBRARY VOLMATF INTLINF ; FLUX := FLU: FLUX PIJ LIBRARY VOLMATF :: TYPE K ; EDITION := EDI: EDITION FLUX LIBRARY VOLMATF :: SAVE ON 'fuel' ; BURNUP LIBRARY := EVO: BURNUP LIBRARY FLUX VOLMATF :: SAVE <> DAY POWR <> ; DATABASE := COMPO: DATABASE EDITION BURNUP LIBRARY :: EDIT 3 STEP UP * SET <> DAY ; *---- * change delta t for burnup and final time if required *---- IF Timef Timec = THEN IF Timec 150.0 = THEN EVALUATE Delt Timec := 50.0 300.0 ; ENDIF ; IF Timec 50.0 = THEN EVALUATE Delt Timec := 20.0 150.0 ; ENDIF ; IF Timec 10.0 = THEN EVALUATE Delt Timec := 10.0 50.0 ; ENDIF ; IF Timec 5.0 = THEN EVALUATE Delt Timec := 5.0 10.0 ; ENDIF ; IF Timec 1.0 = THEN EVALUATE Delt Timec := 4.0 5.0 ; ENDIF ; ENDIF ; EVALUATE Timei := Timef ; ENDWHILE ; assertS FLUX :: 'K-INFINITY' 1 0.9566035 ; *---- * Export and access the database *---- database := DATABASE ; ISOT := DATABASE :: STEP UP fuel STEP UP MIXTURES STEP AT 1 STEP UP CALCULATIONS STEP AT 5 STEP UP ISOTOPESLIST STEP AT 1 ; assertS ISOT :: 'NWT0' 1 9.786811E+00 ; assertS ISOT :: 'NWT0' 2 2.550574E+01 ; ISOT := DELETE: ISOT ; ISOT := DATABASE :: STEP UP moderator STEP UP MIXTURES STEP AT 1 STEP UP CALCULATIONS STEP AT 1 STEP UP ISOTOPESLIST STEP AT 1 ; assertS ISOT :: 'NWT0' 1 9.325515E-02 ; assertS ISOT :: 'NWT0' 2 3.124018E-01 ; INTLINF INTLINS := DELETE: INTLINF INTLINS ; ECHO "test TCWW05 completed" ; END: ; QUIT "LIST" .