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5.5 BWR Fuel Assembly Calculation (PIJ) As the last sample, an example to analyze a fuel assembly of BWR loaded with MOX by using a geometry model (IGT=16) of PIJ. The assembly is shown in Fig.5.5-1 at the last of this section. A series of calculations consists of the following 6 cases. (1) A MOX fuel pin cell calculation (case name: UPIN) A pin cell calculation by PIJ (IGT=4) with 107-group structure is solved for the MOX pin cell with the model shown in Fig.5.5-2. The cross-sections are homogenized in the cell and collapsed into 39-group structure. (2) A partial cell containing a UO 2 -Gd 2 O 3 pin (case name: GDPN) A 3 × 3 rod cell calculation by PIJ (IGT=9) with 107-group structure is done by using the model shown in Fig.5.5-3 to obtain the 39-group constants of UO 2 -Gd 2 O 3 rod under the condition that it is surrounded by MOX pins. As the later assembly calculation treat UO 2 -Gd 2 O 3 rod heterogeneously, the cross-sections of meat, cladding and moderator are separately collapsed by assigning different X-Region number. (3) A partial cell of control rod insertion (case name: CRIN) Control blade is heterogeneously treated with the cell model shown in Fig.5.5-4. The homogenized cross-sections of the control blade are obtained in 39-group structure by PIJ (IGT=16). (4) A partial cell of control rod withdrawn (case name: CROT) The same geometry as the previous case is treated while the materials inside control blade are replaced by saturated water used in gap region. (5) An assembly calculation with control rod insertion (case name: ASMI) By using the 39-group constants obtained in (1), (2) and (3) cases, an eigenvalue problem is solved by PIJ with 39-group structure for the assembly with control rod insertion. Fig.5.5-5 shows the R-Region map (identical with T-Region map) used in the calculation where the thick water rod is treated as homogeneous mixture because of the restriction of the model IGT=16. (6) An assembly calculation with control rod withdrawal (case name: ASMO) The same problem as the previous case is solved with the replacement of cross-sections for the control blade obtained in (3) by those in (4). 208
Note: This sample is time consuming and it is necessary to make a load module of enlarged array size by changing defaulted parameters in the include files. - Shell-script to make users own load module: ~SRAC/tool/lmmake/lmmk/lmml.sh - Include files: ~SRAC/tool/lmmake/lmmk/lmml.sh - Suggested parameter values described in include file: ~SRAC/tool/lmmake/lmmk/lmml.sh MAINSINC: PARAMETER (MXSIZE=7000000) PIJPMINC: PARAMETER (MEMPIJ= 2 0000,MXMESH=300,MXNTAB=3000) [ File name: BWR.sh ]----------------------------------------------------------------------------------------------- UPIN Unit MOX Fuel Pin 1 1 1 1 2 1 4 3 -2 1 0 0 0 0 2 0 -1 0 0 0 / SRAC Control 1.000E-20 / Geometrical buckling for P1/B1 calculation /home/okumura/SRACLIB-JDL33/pds/pfast Old File /home/okumura/SRACLIB-JDL33/pds/pthml /home/okumura/SRACLIB-JDL33/pds/pmcrs O O F F /home/okumura/Mypds/BWR/UFAST Scratch Core /home/okumura/Mypds/BWR/UTHERMAL /home/okumura/Mypds/BWR/UMCROSS S S C C /home/okumura/Mypds/BWR/MACROWRK S C /home/okumura/Mypds/BWR/MACRO /home/okumura/Mypds/BWR/FLUX S S C C /home/okumura/Mypds/BWR/MICREF S C 62 45 20 19 62(1) / 107g => 20+19=39g / 45(1) / 10 10 10 7 8 2 2 13(1) / 3 15(2) 4 4 4 / ***** Enter one blank line after input for energy group structure ***** Input for PIJ (Collision Probability Method) 4 7 7 3 1 1 7 0 0 0 5 0 6 23 0 0 45 0 / Pij Control 0 100 50 5 5 5 -1 0.0001 0.00001 0.001 1.0 10. 0.5 1 1 1 2 3 3 3 / R-T 1 1 1 / X-R 1 2 3 / M-R 0.0 0.3054 0.4319 0.529 0.615 0.682 0.748 0.815 / RX ****** Input for material specification 3 / NMAT MOX1X01X 0 8 900.0 1.058 0.0 / MOX Pellet XU050009 2 0 4.40524E-05 XU080009 2 0 2.17045E-02 XPU90009 2 0 6.73856E-04 XPU00009 2 0 3.18053E-04 XPU10009 2 0 1.30771E-04 XPU20009 2 0 7.76602E-05 XAM10009 2 0 5.99868E-06 XO060009 0 0 4.59098E-02 ZR21X02X 0 1 600.0 0.172 0.0 / Cladding for MOXl Pin XZRN0008 0 0 4.32418E-02 H2O1X03X 0 2 600.0 0.0 0.0 / Moderator(42%Void) XH01H008 0 0 2.96967E-02 XO060008 0 0 1.48483E-02 0 / PEACO *************************************************************************** GDPN 3*3 Array with UO2-Gd2O3 Rod in Center (IGT=9) 1 1 1 1 2 1 4 3 -2 1 0 0 0 0 2 0 -1 0 0 0 / SRAC Control 209
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JAEA-Data/Code 2007-004 SRAC2006 :
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Contents 1. General Descriptions ..
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5.5 BWR Fuel Assembly Calculation (
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目次 1. 概要 ................
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5.4 三次元拡散計算 (CI
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1. General Descriptions 1.1 Functio
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essential programs of the integrate
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Sphere (Pebble, HTGR) 1D-Plate (JRR
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ecause the scattering cross-section
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As shown in Fig.1.4-1, one PDS file
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1.5.1 Fast Fission Energy Range (10
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i n m≠n i n i n i n i 1 i i g( C
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mixture(s) having resonant nuclides
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thermal energy range. In the fixed
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1.10 Calculation Scheme In Fig.1.10
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3 2 1 CALL MICREF [20] CALL REACT C
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homogenized P 1 spectrum obtained a
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Consequently next step ’CALL MACR
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1.11 Output Information Major calcu
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(4) A floating number may be entere
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2.2 General Control and Energy Stru
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cell. = 2 The PEACO routine (hyperf
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should be avoided for the core wher
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Note: Usually IC15=1 is used in FBR
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Behrens’ term of the Benoist mode
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Only the first character (capital l
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NET ∑ i= 1 NEGT( i ) =(Total numb
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Block-1 Control integers /18/ 1 IGT
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asymmetric cell is surrounded by en
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= 0 Isotropic (white) reflection =
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degree for the numerical angular in
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3 EPSG Extrapolation criterion 4 R
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Block-10’ Required if IGT=11, or
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= 2 Neutron from moderator = 3 Neut
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Unit Cell Periodic B.C. 4 2 3 1 RX(
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NX=4 NTPIN=6 NAPIN=1 NPIN(1)=6 6 ID
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RDP(1)=0.0 RDP(2) RDP(3) 14 13 12 R
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2.5 ANISN ; One-dimensional S N Tra
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7 IBR Right boundary condition, sam
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22 IPM Angular dependent incident s
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EV = best guess for α or 0.0 when
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Block-04* Positions of interval bou
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2.6 TWOTRAN ; Two-dimensional S N T
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Note: The original TWOTRAN uses two
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= 0 (internally set) 19 IHM Total n
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= 3 R-θ 31 IEDOPT Edit options. =
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= 1 Yes Block-4 Control floating po
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Repeat Block-20 through Block-21, N
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2.7 TUD ; One-dimensional Diffusion
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= 1 Monitor print at each inner ite
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equation is applied to meshes, the
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Pin Plate D2 D2 D1 D1 In cylindrica
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XYZ(1,2) Y-abscissa of the top side
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READ(9) (WORK(J+I),I=1,NDATA) END D
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absorption cross-section, each of w
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ITMX19 The upper limit of CPU time
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corner and there are the same numbe
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NUAC19 Override use of Chebychev po
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NUAC17 > 0 The constant for all gro
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ottom starting with a new card. For
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Card-006-3 Specification of meshes
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4 SIG3 Absorption cross-section (
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2 NFX2 Optional print control = 0 N
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Region 1 Region 2 Left Right X/R/R
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X T 22*11 Meshes 1 Mesh = 1 Region
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2.9 Material Specification ’Mater
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fuel pin: MU08F0U2 and those in MOX
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hydrogen, add character ‘0’ to
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Usually, enter IRES=2 for the heavy
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2.10 Reaction Rate Calculation The
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Block-1 Control integers for reacti
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3 U238 The position of the second n
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2.11 Cell Burn-up Calculation The i
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= 2 Information for debugging = 3 D
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chains under consideration is enlar
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MACROWRK file. 2 INTSTP Step number
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Block-8-1 Required if IBC6=1 /1/ NM
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e avoided. Because U08W and U080 ar
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2.12 PEACO ; The hyperfine Group Re
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3. I/O FILES We shall describe the
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(E(g),g=1,NGF+1) structure. Boundar
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LTH(1) = (LD(1)+1)*LA(1), ordered a
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Background cross-sections Member Yz
Page 169 and 170: INT(2) = 0 K-member only without sc
Page 171 and 172: Member name Contents **************
Page 173 and 174: (WEIGHT(g),g=1,NGF) Lethargy widths
Page 175 and 176: 3.1.5 Fine Group Macroscopic Cross-
Page 177 and 178: Member mmmmebfM or caseebxM /10*ng+
Page 179 and 180: Member caseBNUP Material-wise burn-
Page 181 and 182: Initial inventory in the restart ca
Page 183 and 184: (YDIOX(j),j=1,NOWSTP) Fission yield
Page 185 and 186: (n/cm 2 /sec*cm 3 ), NRR is number
Page 187 and 188: 3.2.1 Common PS Files The following
Page 189 and 190: 3.2.5 PS files for TUD The PS files
Page 191 and 192: at the first column. Block-1-1 Numb
Page 193 and 194: = ‘DAYS’ days = ‘YEARS’ yea
Page 195 and 196: GD156 XGD60001 641560 154.660 0 0 0
Page 197 and 198: : ZZ050 1.50080E+00 *FP-Yield-Data
Page 199 and 200: Kr83 Zr95 fission β + decay, EC (n
Page 201 and 202: Ge73 Ge74 As75 Ge76 fission β + de
Page 203 and 204: 4. Job Control Statements In this c
Page 205 and 206: ~SRAC/tool/lmmake/lmmk/lmmk.sh, whi
Page 207 and 208: 5. Sample Input Several typical exa
Page 209 and 210: 613.0 650.0 760.0 769.0 & cooling 7
Page 211 and 212: 5 5 5 5 5 5 & 5 5 5 5 5 5 & 1 2 3 4
Page 213 and 214: 5.3 S N Transport Calculation (PIJ,
Page 215 and 216: XFEN0001 2 0 5.78720E-02 XNIN0001 2
Page 217 and 218: Water reflector Extrapolated B.C. B
Page 219: 1 1 1 1 1 1 1 2 3 008 -2 1 1 999 /
Page 223 and 224: XCRN0008 0 0 1.55546E-02 XNIN0008 0
Page 225 and 226: ****** Input for material specifica
Page 227 and 228: T-Region R-Region X-Region Reflecti
Page 229 and 230: 6. Utility for PDS File Management
Page 231 and 232: To read in the microscopic cross-se
Page 233 and 234: 7. Mathematical Formulations 7.1 Fo
Page 235 and 236: scattering kernel at point r’ fro
Page 237 and 238: The integration by R between R j- a
Page 239 and 240: G j Pij ( lattice) = Pij ( isolated
Page 241 and 242: We, however, should take care of th
Page 243 and 244: 2 = ρ 2 + x r sin β = ρ R = x
Page 245 and 246: 1 i ∑ − 1 k = j+ 1 λ ij = λ k
Page 247 and 248: where λ λ 1 is 2 is = = N ∑ k k
Page 249 and 250: 2π ri −1 Pij = − Σ ∫ ρdρ
Page 251 and 252: In Fig.7.1-5, the line PQ’ define
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Page 255 and 256: the arrays T and II, respectively.
Page 257 and 258: Note that among four terms appearin
Page 259 and 260: If a group-dependent form of Fick
Page 261 and 262: 7.3 Optional Processes for Resonanc
Page 263 and 264: 7.3.2 Table-look-up Method of f-tab
Page 265 and 266: has been introduced for the correct
Page 267 and 268: ϕ i ( 0 u ) = ∑ Pij ( u) W j ( u
Page 269 and 270: Geometry b i m f b f −( γ + γ )
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will be seen in the reference 65) .
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The lattice cell under study may co
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(2) Two resonance-absorbing composi
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One of the physical problems associ
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and V = V + V , F f m where Σ m ,
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We shall discuss the following two
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where X = 2R p ( Σ C = 2R πρ R p
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• the reduced collision probabili
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The root mean square (RMS) residual
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group flux and for the fast group f
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Table 7.5-1 (1/2) Nomenclature Symb
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7.5.1 Smearing Smearing or spatial
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7.5.2 Spectrum for Collapsing The f
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Here, an equivalent relation holds
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1 F = K ∑∫ g * χ g ( r) ϕ g (
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M dN i ( t) M = ∑ f j→iλ j N i
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8. Tables on Cross-Section Library
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Table 8.1-2 (2/2) Element index (zz
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JEFF-3.0 are based on other nuclear
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Table 8.2-1 (1/8) List of SRAC publ
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8.3 Energy Group Structure The ener
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(4) Upper Boundary of PEACO Routine
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References 1) K. Tsuchihashi, H. Ta
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Experiment,” J. Nucl. Sci. Techno
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75) K. Tasaka : “DCHAIN: Code for
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