JAEA-Data/Code 2007-004 - Welcome to Research Group for ...

More documents

Recommendations

Info

5.4 Three-dimensional diffusion calculation (CITATION) Figure 5.4-1 shows a three-dimensional X-Y-Z calculation model of a light water reactor for CITATION three-dimensional diffusion module. Not only multiplication factor but also power distribution and one-point kinetics parameters will be calculated. The following is a sample input organized by three cases. (1) Few group constants for 3.2 wt.% fuel region by PIJ (case name: FUL1) A square lattice cell model for a fuel pin of 3.2 wt.% enriched UO 2 is solved by PIJ with 107-group structure to yield two-group constants for the succeeding whole reactor calculation. The diameter of fuel pellet 9.5mm, thickness of cladding 0.65mm and fuel pin pitch 12.6mm are assumed. The two-group constants for reflector used in the succeeding core calculation are collapsed by using the asymptotic spectrum installed in the library. (2) Few group constants for 2.1wt.% fuel region by PIJ (case name: FUL2) For the fuel pin cell of different enrichment, the same cell calculation is executed. As the geometry is identical with that of the previous case, the input for PIJ is not required by specifying IC11=1. (3) Core calculation by CITATION (case name: CORE) By using the homogenized constants provided by the previous two cases, a whole core calculation of X-Y-Z system is carried out by CITATION. The supposed active core is composed by array of fuel assemblies, each of which has dimension 20cm*20cm*340cm. The outer fuel region is loaded with fuel pins of 3.2 wt.% enriched uranium and the inner with those of 2.1 wt.%. The active core is surrounded by the reflector of the same dimension with fuel assembly. The outer boundary of reflector is assumed as black. In axial direction, the upper and lower reflectors of 20cm thick are installed. Upon calculation, 1/4 core in horizontal direction and 1/2 in axial direction is solved by using reflective boundary condition owing to the symmetry. A mesh size of 5cm is applied in every direction. By specifying the kinetic parameter calculation option, effective delayed neutron fraction, prompt neutron lifetime and decay constants of precursors will be obtained. Note that the two-group structure in this sample does not yield proper effective delayed neutron fraction. Some calculation scheme such that the fission spectrum of delayed neutron can be reflected on the result may be required. 204
Water reflector Extrapolated B.C. Blackness X 20cm Extrapolated B.C. Reflector Reflective B.C. 3.2w/o Fuel 2.1w/o Fuel Extrapolated B.C. 170cm Core Y 20cm20cm Reflective B.C. Z Reflective B.C. Fig.5.4-1 Core geometry of sample input for 3-D diffusion calculation by CITATION [ File name: CitXYZ.sh ]-------------------------------------------------------------------------------------------- FUL1 MACRO FOR INNER FUEL (3.2W/O UO2) BY PIJ 1 1 1 1 2 1 4 3 -2 1 1.0000E-20 / BUCKLING 0 0 0 0 2 0 1 0 0 0 / SRAC CONTROL /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/CitXYZ/UFAST Scratch Core /home/okumura/Mypds/CitXYZ/UTHERMAL /home/okumura/Mypds/CitXYZ/UMCROSS S S C C /home/okumura/Mypds/CitXYZ/MACROWRK S C /home/okumura/Mypds/CitXYZ/MACRO /home/okumura/Mypds/CitXYZ/FLUX S S C C /home/okumura/Mypds/CitXYZ/MICREF S C 61 46 61(1) 1 1 / / 46(1) / 61 46 / / 4 7 7 3 1 1 7 0 0 0 5 0 6 45 0 0 90 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 3(1) 1 2 3 / X-R / M-R 0.0 0.236714 0.334764 0.41 0.475 0.5267 0.5783 0.630 / RX 4 / NMAT FUE1X0AX 0 3 900. 0.82 0.0 / 1 : INNER FUEL 3.2W/O XU050009 2 0 7.2270E-4 /1 XU080009 2 0 2.1585E-2 XO060009 0 0 4.4616E-2 /2 /3 CLD1X0BX 0 3 600. 0.13 0.0 / 2 : CLADDING XZRN0008 0 0 3.8032E-2 XCRN0008 0 0 6.7152E-5 /1 /2 XFEN0008 0 0 1.3129E-4 /3 MOD1X0CX 0 2 581. 1.0 0.0 / 3 : MODERATOR 205
Page 3 and 4:
JAEA-Data/Code 2007-004 SRAC2006 :
Page 5 and 6:
Contents 1. General Descriptions ..
Page 7 and 8:
5.5 BWR Fuel Assembly Calculation (
Page 9 and 10:
目次 1. 概要 ................
Page 11 and 12:
5.4 三次元拡散計算 (CI
Page 13 and 14:
1. General Descriptions 1.1 Functio
Page 15 and 16:
essential programs of the integrate
Page 17 and 18:
Sphere (Pebble, HTGR) 1D-Plate (JRR
Page 19 and 20:
ecause the scattering cross-section
Page 21 and 22:
As shown in Fig.1.4-1, one PDS file
Page 23 and 24:
1.5.1 Fast Fission Energy Range (10
Page 25 and 26:
i n m≠n i n i n i n i 1 i i g( C
Page 27 and 28:
mixture(s) having resonant nuclides
Page 29 and 30:
thermal energy range. In the fixed
Page 31 and 32:
1.10 Calculation Scheme In Fig.1.10
Page 33 and 34:
3 2 1 CALL MICREF [20] CALL REACT C
Page 35 and 36:
homogenized P 1 spectrum obtained a
Page 37 and 38:
Consequently next step ’CALL MACR
Page 39 and 40:
1.11 Output Information Major calcu
Page 41 and 42:
(4) A floating number may be entere
Page 43 and 44:
2.2 General Control and Energy Stru
Page 45 and 46:
cell. = 2 The PEACO routine (hyperf
Page 47 and 48:
should be avoided for the core wher
Page 49 and 50:
Note: Usually IC15=1 is used in FBR
Page 51 and 52:
Behrens’ term of the Benoist mode
Page 53 and 54:
Only the first character (capital l
Page 55 and 56:
NET ∑ i= 1 NEGT( i ) =(Total numb
Page 57 and 58:
Block-1 Control integers /18/ 1 IGT
Page 59 and 60:
asymmetric cell is surrounded by en
Page 61 and 62:
= 0 Isotropic (white) reflection =
Page 63 and 64:
degree for the numerical angular in
Page 65 and 66:
3 EPSG Extrapolation criterion 4 R
Page 67 and 68:
Block-10’ Required if IGT=11, or
Page 69 and 70:
= 2 Neutron from moderator = 3 Neut
Page 71 and 72:
Unit Cell Periodic B.C. 4 2 3 1 RX(
Page 73 and 74:
NX=4 NTPIN=6 NAPIN=1 NPIN(1)=6 6 ID
Page 75 and 76:
RDP(1)=0.0 RDP(2) RDP(3) 14 13 12 R
Page 77 and 78:
2.5 ANISN ; One-dimensional S N Tra
Page 79 and 80:
7 IBR Right boundary condition, sam
Page 81 and 82:
22 IPM Angular dependent incident s
Page 83 and 84:
EV = best guess for α or 0.0 when
Page 85 and 86:
Block-04* Positions of interval bou
Page 87 and 88:
2.6 TWOTRAN ; Two-dimensional S N T
Page 89 and 90:
Note: The original TWOTRAN uses two
Page 91 and 92:
= 0 (internally set) 19 IHM Total n
Page 93 and 94:
= 3 R-θ 31 IEDOPT Edit options. =
Page 95 and 96:
= 1 Yes Block-4 Control floating po
Page 97 and 98:
Repeat Block-20 through Block-21, N
Page 99 and 100:
2.7 TUD ; One-dimensional Diffusion
Page 101 and 102:
= 1 Monitor print at each inner ite
Page 103 and 104:
equation is applied to meshes, the
Page 105 and 106:
Pin Plate D2 D2 D1 D1 In cylindrica
Page 107 and 108:
XYZ(1,2) Y-abscissa of the top side
Page 109 and 110:
READ(9) (WORK(J+I),I=1,NDATA) END D
Page 111 and 112:
absorption cross-section, each of w
Page 113 and 114:
ITMX19 The upper limit of CPU time
Page 115 and 116:
corner and there are the same numbe
Page 117 and 118:
NUAC19 Override use of Chebychev po
Page 119 and 120:
NUAC17 > 0 The constant for all gro
Page 121 and 122:
ottom starting with a new card. For
Page 123 and 124:
Card-006-3 Specification of meshes
Page 125 and 126:
4 SIG3 Absorption cross-section (
Page 127 and 128:
2 NFX2 Optional print control = 0 N
Page 129 and 130:
Region 1 Region 2 Left Right X/R/R
Page 131 and 132:
X T 22*11 Meshes 1 Mesh = 1 Region
Page 133 and 134:
2.9 Material Specification ’Mater
Page 135 and 136:
fuel pin: MU08F0U2 and those in MOX
Page 137 and 138:
hydrogen, add character ‘0’ to
Page 139 and 140:
Usually, enter IRES=2 for the heavy
Page 141 and 142:
2.10 Reaction Rate Calculation The
Page 143 and 144:
Block-1 Control integers for reacti
Page 145 and 146:
3 U238 The position of the second n
Page 147 and 148:
2.11 Cell Burn-up Calculation The i
Page 149 and 150:
= 2 Information for debugging = 3 D
Page 151 and 152:
chains under consideration is enlar
Page 153 and 154:
MACROWRK file. 2 INTSTP Step number
Page 155 and 156:
Block-8-1 Required if IBC6=1 /1/ NM
Page 157 and 158:
e avoided. Because U08W and U080 ar
Page 159 and 160:
2.12 PEACO ; The hyperfine Group Re
Page 161 and 162:
3. I/O FILES We shall describe the
Page 163 and 164:
(E(g),g=1,NGF+1) structure. Boundar
Page 165 and 166: LTH(1) = (LD(1)+1)*LA(1), ordered a
Page 167 and 168: 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: XFEN0001 2 0 5.78720E-02 XNIN0001 2
Page 219 and 220: 1 1 1 1 1 1 1 2 3 008 -2 1 1 999 /
Page 221 and 222: Note: This sample is time consuming
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
Page 253 and 254: pin rod are divided into four regio
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 )
Page 271 and 272:
will be seen in the reference 65) .
Page 273 and 274:
The lattice cell under study may co
Page 275 and 276:
(2) Two resonance-absorbing composi
Page 277 and 278:
One of the physical problems associ
Page 279 and 280:
and V = V + V , F f m where Σ m ,
Page 281 and 282:
We shall discuss the following two
Page 283 and 284:
where X = 2R p ( Σ C = 2R πρ R p
Page 285 and 286:
• the reduced collision probabili
Page 287 and 288:
The root mean square (RMS) residual
Page 289 and 290:
group flux and for the fast group f
Page 291 and 292:
Table 7.5-1 (1/2) Nomenclature Symb
Page 293 and 294:
7.5.1 Smearing Smearing or spatial
Page 295 and 296:
7.5.2 Spectrum for Collapsing The f
Page 297 and 298:
Here, an equivalent relation holds
Page 299 and 300:
1 F = K ∑∫ g * χ g ( r) ϕ g (
Page 301 and 302:
M dN i ( t) M = ∑ f j→iλ j N i
Page 303 and 304:
8. Tables on Cross-Section Library
Page 305 and 306:
Table 8.1-2 (2/2) Element index (zz
Page 307 and 308:
JEFF-3.0 are based on other nuclear
Page 309 and 310:
Table 8.2-1 (1/8) List of SRAC publ
Page 311 and 312:
Page 313 and 314:
Page 315 and 316:
Page 317 and 318:
8.3 Energy Group Structure The ener
Page 319 and 320:
(4) Upper Boundary of PEACO Routine
Page 321 and 322:
References 1) K. Tsuchihashi, H. Ta
Page 323 and 324:
Experiment,” J. Nucl. Sci. Techno
Page 325:
75) K. Tasaka : “DCHAIN: Code for
show all

JAEA-Data/Code 2007-004 - Welcome to Research Group for ...

Create successful ePaper yourself

Delete template?

Save as template?