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*----
* TEST CASE TCDR13
* CANDU-6 ANNULAR CELL
* 172-GROUP JEF2.2 DRAGLIB
* 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
*
*----
* Select burnup options
*----
REAL Power BExit := 31.9713 9609.42 ;
INTEGER NbSteps := 16 ;
*----
* Define STRUCTURES and MODULES used
*----
LINKED_LIST
LIBRARY CANDU6S CANDU6F VOLMATS VOLMATF PIJ FLUX EDITION ISOT ;
XSM_FILE BURNUP DATABASE ;
SEQ_BINARY
INTLINS INTLINF ;
SEQ_ASCII
database.txt ;
MODULE
GEO: EXCELT: SHI: ASM: FLU: EDI: COMPO: DELETE: END: ;
PROCEDURE EvolRef ;
PROCEDURE assertS ;
*----
* Depletion data from Jef 2.2 Draglib
* Microscopic cross sections from Jef 2.2 Draglib
*----
PROCEDURE TCDR05Lib ;
INTEGER iedit := 1 ;
LIBRARY := TCDR05Lib :: <<iedit>> ;
*----
* 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
*----
VOLMATS INTLINS := EXCELT: CANDU6S ::
TITLE 'TCDR05: CANDU-6 ANNULAR POWER= 31.971 FUEL TEMP= 941.29'
EDIT 0 MAXR 13 TRAK TISO 5 10.0 SYMM 12 ;
VOLMATF INTLINF := EXCELT: CANDU6F ::
TITLE 'TCDR05: CANDU-6 ANNULAR POWER= 31.971 FUEL TEMP= 941.29'
EDIT 0 MAXR 31 TRAK TISO 5 10.0 SYMM 12 ;
*----
* Reflector calculation
*----
LIBRARY := SHI: LIBRARY VOLMATS INTLINS :: EDIT 0 NOLJ ;
PIJ := ASM: LIBRARY VOLMATF INTLINF ;
FLUX := FLU: PIJ LIBRARY VOLMATF ::
TYPE K ;
assertS FLUX :: 'K-INFINITY' 1 1.117541 ;
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' ;
PIJ FLUX EDITION := DELETE: PIJ FLUX EDITION ;
*----
* Burnup calculation using procedure EvolRef
*----
DATABASE BURNUP FLUX LIBRARY := EvolRef LIBRARY VOLMATS
VOLMATF INTLINS INTLINF ::
<<BExit>> <<Power>> <<NbSteps>> ;
*----
* Export and access the database
*----
database.txt := 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 1.149079E1 ;
assertS ISOT :: 'NWT0' 2 2.586806E1 ;
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 9.095950E-2 ;
assertS ISOT :: 'NWT0' 2 3.246065E-1 ;
INTLINF INTLINS := DELETE: INTLINF INTLINS ;
ECHO "test TCDR13 completed" ;
END: ;
QUIT "LIST" .
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