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Integrated CR( t) = ∫ t 0 ∫ FISSProduction( τ ) dτ . (2.11-4) t FISSDepletion( τ ) dτ 0 Thus the user can calculate his own microscopic or macroscopic reaction rates and their ratio by the option IBC5=1. The defaulted definition of conversion ratio follows the description in the burn-up chain library. As the initial setting, it is defined as the ratio of the summation of capture reaction rates of Th-232 (if any in chain), U-234 (if any), U-238 and Pu-240 to the summation of absorption reaction rates of U-233 (if any), U-235, Pu-239 and Pu-241. (no decay effect) IBC6 Option to write effective microscopic cross-sections into MICREF file = 0 No cross-sections are written unless IXMICR (Sect.2.9) is not specified to certain nuclides. This option is suggested if MICREF file is not preserved. = 1 Write cross-sections of the nuclides specified by Block-8 = 2 Write cross-sections of the whole depleting nuclides = 3 Write cross-sections of the whole burnable resonant nuclides Note: In such a case that numbers of depleting materials, burn-up steps or depleting nuclides are large as to cause shortage of core memory for virtual PDS file, keep the requirement to write cross-sections to a minimum. [cf.] Sect.1.4, Block-5 in Sect.2.2, Block-3 in Sect.2.9 IBC7 Option to make up collision probability table for PEACO calculation (effective if IC5=±2 is specified in Sect.2.2) = 0 Update at each burn-up step (suggested) = 1 Make up tables at first two steps and use the second one after that Note: Option IBC7=1 is used to reduce large CPU time. IBC8 Maximum length (LCHA) of decay chain in linear analysis = 0 Defaulted value (LCHA=6) is used > 0 Input value is used for LCHA. If large LCHA is used, as number of 138
chains under consideration is enlarged, long CPU time and large core memory are required. IBC9 Option to fix atomic number densities of specified nuclides = 0 Calculate atomic number densities of all nuclides = N Replace atomic number densities of N nuclides by the values specified by Block-11. Note: This option is used, for example, to prepare Xenon free cross-sections for a branch-off calculation, or to assume on-line decontamination in the normal burn-up calculation. N ≤ 5 must be satisfied. IBC10 Option to specify depleting material = 0 Any material containing at least one nuclide appearing in burn-up chains is automatically assumed as depleting material. = 1 The user specifies depleting materials by Block-9 Some burn-up chain model assumes such a material as cladding, boric water or control rod to be depleting although the user does not want to treat as depleting. This option is used to avoid it. Note: Especially pay attention to boric water, because B-10 is treated as a burnable nuclide in any burn-up chain model. IBC11 through IBC20 = 0 (not used) Block-2 Thermal power (MWt/cm) /IBC1/ (POWERL(i), i=1,IBC1) Thermal power (MWt) in the whole cell per unit length (1cm) at each burn-up step interval. For example, to the cell containing 4 pin rods with average linear power of 170 W/cm, enter 170*4*1.0E-6=6.60E-4 as POWERL. To a one-dimensional plane geometry, assume unit length for two transverse directions, and enter average thermal power of the system (cell thickness)*1cm* 1cm. 139
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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
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: = 2 Information for debugging = 3 D
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
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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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