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IEDG10 Print point flux values by group IEDG11 = 0 (not used) IEDG12 Print zone average power densities IEDG13 Print relative power density traverses through peak IEDG14 Print mesh-wise power densities IEDG15 = 0 (suppressed) IEDG16 Print mesh-wise neutron densities summed over energy IEDG17 = 0 (suppressed) IEDG18 though IEDG23 = 0 (ineffective) IEDG24 Option added on SRAC-CITATION = 0 Print zone placement on fine mesh = 1 Suppress printing of zone placement on fine mesh. This is effective for saving too many pages printing for 3D case. Card-001-4 General iteration count and machine time limits (24I3) Problems are terminated when the iteration count reaches the limit and the calculation proceeds as specified by NGC15 in Card-001-2. As SRAC treats a static problem (no depletion or dynamics) only ITMX1, ITMX19, and ITMX24 are applied. Built-in numbers are shown in < >; zero input data are replaced by these. ITMX1 The limit of the iteration count ITMX2 through ITMX18 = 0.0 (ineffective) 100
ITMX19 The upper limit of CPU time (min) for an eigenvalue calculation ITMX20 through ITMX23 = 0.0 (ineffective) ITMX24 The upper limit of total CPU time (min) for CITATION calculation This time does not include CPU time elapsed before and after CITATION calculation. Card-001-5 General restraints (6E12.5) Any calculation will be terminated if the restraints of GLIM1 and GLIM2 are not met. Built-in numbers are shown in < >; zero input data are replaced by these. GLIM1 Maximum multiplication factor GLIM2 Minimum multiplication factor GLIM3 = 0.0 (suppressed) GLIM4 = 0.0 (not used) GLIM5 Factor applied to neutron productions for generating a fixed source file, see NGC8 GLIM6 = 0.0 (suppressed) ============= Section 003 : Description of the neutron flux problem ============= Card-003-1 Input section name (I3) Enter ’003’. Card-003-2 General description (24I3) NUAC1 = 0 (not used) NUAC2 Initialization of the flux for a restart calculation (effective if NGC2= -1) = 0 Use available flux, multiplication factor and acceleration parameters from 101
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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
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: absorption cross-section, each of w
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
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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
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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
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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
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Ge73 Ge74 As75 Ge76 fission β + de
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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
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5.3 S N Transport Calculation (PIJ,
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XFEN0001 2 0 5.78720E-02 XNIN0001 2
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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
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The integration by R between R j- a
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G j Pij ( lattice) = Pij ( isolated
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We, however, should take care of th
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2 = ρ 2 + x r sin β = ρ R = x
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1 i ∑ − 1 k = j+ 1 λ ij = λ k
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where λ λ 1 is 2 is = = N ∑ k k
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2π ri −1 Pij = − Σ ∫ ρdρ
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In Fig.7.1-5, the line PQ’ define
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pin rod are divided into four regio
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the arrays T and II, respectively.
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Note that among four terms appearin
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If a group-dependent form of Fick
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7.3 Optional Processes for Resonanc
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7.3.2 Table-look-up Method of f-tab
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has been introduced for the correct
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ϕ i ( 0 u ) = ∑ Pij ( u) W j ( u
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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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