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home/okumura/SRACLIB-JDL33/pds/pmcrs O F /home/okumura/MyPDS/Test/UFAST Scratch Core /home/okumura/MyPDS/Test/UTHERMAL /home/okumura/MyPDS/Test/UMCROSS S S C C /home/okumura/MyPDS/Test/MACROWRK S C /home/okumura/MyPDS/Test/MACRO /home/okumura/MyPDS/Test/FLUX New New C C /home/okumura/MyPDS/Test/MICREF S C Block-6 Specification for energy group structures /4/ 1 NEF Number of the fast neutron groups of the User Fast Library (NEF ≤ 74) 2 NET Number of the thermal neutron groups of the User Thermal Library; (NET ≤ 48, and NEF+NET ≤ 107). Enter 0, if IC4 = 0 (no thermal group calculation) in Block-3 3 NERF Number of the fast few-groups If no collapsing is required (IC10=0 and IC13=0), enter NERF=0. 4 NERT Number of the thermal few-groups If no collapsing is required (IC10=0 and IC13=0) or no thermal group calculation (IC4=0), enter NERT=0. Block-7 Collapsing from PFAST into UFAST /NEF/ NEGF(i) Number of the public fast groups in each user fast group (i) See the table of energy group structure in Sect. 8.3. NEF ∑ i= 1 NEGF( i ) =(Total number of public fast groups included between 10 MeV and the thermal-cut-off energy). By this item, the thermal-cut-off energy is decided. As the thermal-cut-off energy has to be any of lower energy boundaries of Public energy group structure between 3.9278 eV and 0.41399 eV, set NEGFs so as NEF to satisfy 59 ≤ NEGF( i) ≤ 74. ∑ i= 1 The recommended cut-off-energy in the SRAC code is about 2.0 eV (cf. Sect.1.3) Block-8 Collapsing from PTHERMAL into UTHERMAL, Required if NET ≠ 0 /NET/ NEGT(i) Number of the public thermal groups in each user thermal group (i) See the table of energy group structure in Sect. 8.3. 42
NET ∑ i= 1 NEGT( i ) =(Total number of public thermal groups below the thermal-cut-off energy). NEF ∑ The relation NEGF(i) + NEGT(i) = 107 must be satisfied. i= 1 NET ∑ i= 1 Block-9 Required if NERF ≠ 0 is specified /NERF/ NECF(i) Number of the user fast groups in each condensed fast group (i) NERF The relation ∑ NECF(i) = NEF must be satisfied. i= 1 Block10 Required if NERT ≠ 0 is specified /NERT/ NECT(i) Number of the user thermal groups in each condensed thermal group (i) NERT The relation ∑ NECT(i) = NET must be satisfied. i= 1 An example of the Block-6 through Block-10 ---------------------------------------------------------------------------------------------------------------- 62 45 2 1 / 107(=62+45) fine-group => 3(=2+1) few-group 62(1) 45(1) / No collapsing from PFAST to UFAST (cut-off=1.85eV) / No collapsing from PTHERM to UTHERM 28 34 / Block-9 45 / Block-10 ---------------------------------------------------------------------------------------------------------------- 2.3 User’s Library Specification Formally all of the nuclides used in the succeeding calculations had to be specified in this section to transfer the necessary cross section data from the Public Library to User’s Library. In the current version, the requirements are automatically judged from the material specifications in Sect.2.9 and the burn-up chain library in Sect.3.3. Thus, the user completes the section by feeding one blank line. message: A special option is provided for the case where a job was terminated with the following error ----------------------------------------------------------------------------------------------------- NUCLIDE(xxxxxxxx) HAS DOUBLE TEMPERATURE DEFINITION. ONE TEMPERATURE IS xxx.xx KELVIN AND ANOTHER IS yyy.yy KELVIN. PLEASE RESET STATNDARD TEMPERATURE ARRAY BY YOUR INPUT DATA -------------------------------------------------------------- 43
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: Only the first character (capital l
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
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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
Page 141 and 142:
2.10 Reaction Rate Calculation The
Page 143 and 144:
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
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
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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
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INT(2) = 0 K-member only without sc
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Member name Contents **************
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(WEIGHT(g),g=1,NGF) Lethargy widths
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3.1.5 Fine Group Macroscopic Cross-
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Member mmmmebfM or caseebxM /10*ng+
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Member caseBNUP Material-wise burn-
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Initial inventory in the restart ca
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(YDIOX(j),j=1,NOWSTP) Fission yield
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(n/cm 2 /sec*cm 3 ), NRR is number
Page 187 and 188:
3.2.1 Common PS Files The following
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3.2.5 PS files for TUD The PS files
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at the first column. Block-1-1 Numb
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= ‘DAYS’ days = ‘YEARS’ yea
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GD156 XGD60001 641560 154.660 0 0 0
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: ZZ050 1.50080E+00 *FP-Yield-Data
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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
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~SRAC/tool/lmmake/lmmk/lmmk.sh, whi
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5. Sample Input Several typical exa
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613.0 650.0 760.0 769.0 & cooling 7
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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
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1 1 1 1 1 1 1 2 3 008 -2 1 1 999 /
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Note: This sample is time consuming
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XCRN0008 0 0 1.55546E-02 XNIN0008 0
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****** Input for material specifica
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T-Region R-Region X-Region Reflecti
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6. Utility for PDS File Management
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To read in the microscopic cross-se
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7. Mathematical Formulations 7.1 Fo
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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
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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
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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
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