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data is identical with that of this input section. The CVMACT routine in SRAC converts the data before calling CITATION by reading the data from PDS (MACRO or MACROWRK) file and writes them into logical unit 31. For the latter, Card-008-1 is required and then Card-008-2 containing a negative integer in columns 1-3 (KMAX0), input data after Card-008-3 are required. We shall describe this section to explain the contents of the I/O unit 31. Card-008-1 Input section name (I3) Enter ’008’. Card-008-2 Number of groups and scattering range (3I3) 1 KMAX Number of energy groups < 0 Use the cross section provided by SRAC: Cross-sections are read from logical unit 31. As KMAX is automatically supplied on logical unit 31, absolute value of KMAX may be arbitrary. > 0 User’s own cross-sections are read in this section, the KMAX value must be proper. 2 IX28 Number of groups for down-scatter As the code finds the correct value from the scattering vector, this value may be different from the actual value. 3 IX29 Number of groups for up-scatter As the code finds the correct value from the scattering vector, this value may be different from the actual value. If KMAX
4 SIG3 Absorption cross-section ( Σ a, g ) 5 SIG4 Production cross-section ( ν Σ f , g ) 6 SIG5 Constant ( Σ υ , g ≡1/ Eg ) related on neutron velocity for the calculation of point kinetics parameters (cf. Sect. 3.1.5). 7 SIG6 Power per unit flux, (joule/fission)* Σ f , g for normalization of the flux level and power density maps. If all entries here are zero, then SIG4 is used. If KMAX
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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(
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: Card-006-3 Specification of meshes
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
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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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