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i.e., X 0 j / X j = 1 ( j ∉ R) . (7.3.3-11) Under these assumptions, Eq.(7.3.3-8) can be rewritten as ⎛ ⎞ ϕ ⎜ ⎟ i ( u) → X − → ∞ 0i ∑γ ij X i for X i . (7.3.3-12) ⎝ j∉R ⎠ On the other hand, an equivalent theorem between homogeneous and heterogeneous systems means that the flux in the absorber lump should be expressed by the spectrum in homogeneous medium X 0i + bi ϕ i ( u) = → ( X 0i + bi ) / X i for X i → ∞ . (7.3.3-13) X + b i i where the flux is normalized to be unity at off-resonance energy. For Eqs.(7.3.3-12) and (7.3.3-13) to be held, the following identity must be satisfied: bi = − ∑ j∉R γ ij (7.3.3-14) For a special case where the unit cell under study consists of fuel region (f) and moderator region (m), we can prove the conventional relation 61) b i = − γ = 1 − C , (7.3.3-15) fm where C is the Dancoff correction factor and − γ fm corresponds to the first-flight blackness for neutrons leaving the fuel region 61) . Figure 7.3.3-1 shows the expression of b i for other simple geometries. Consequently, from the above examples, Eq.(7.3.3-14) is considered to be a generalization of the previous works introduced in the previous section. Equation (7.3.3-14) shows that the Dancoff correction factor for complex geometry can be obtained by calculating the generalized blackness γ fm . Here, the blackness γ fm is calculated by using the collision probability package in the SRAC system, that is, by using the value of P ij for a sufficiently large value of Σ ( j ∈ R) , as Σ j =300 cm -1 , based on Eq.(7.3.3-5). j 256
Geometry b i m f b f −( γ + γ ) > 0 = fc fm m 1 2 3 b i ⎧ ⎪ = ⎨ ⎪ ⎩ 0 i = 1 0 i = 2 γ 33 = −γ 3m > 0 i = 3 1 2 m b i ⎧ ⎪ = ⎨ ⎪⎩ 0 γ i = 1 = −∑γ 2m > 0 = 2 22 i m (plate) L i R b i = X ≡ 1 − E3 ( X L ) − E3 ∑ m d m Σ m ( X Meneghetti’s two-sided formula R ) Fig. 7.3.3-1 Dancoff correction factors for simple geometries The symbol (m) means moderator region and the shaded portions show the R-region: The quantities d m stands for the width of moderator plate m. 257
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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
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2.7 TUD ; One-dimensional Diffusion
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= 1 Monitor print at each inner ite
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equation is applied to meshes, the
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Pin Plate D2 D2 D1 D1 In cylindrica
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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
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2.10 Reaction Rate Calculation The
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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
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MACROWRK file. 2 INTSTP Step number
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Block-8-1 Required if IBC6=1 /1/ NM
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e avoided. Because U08W and U080 ar
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2.12 PEACO ; The hyperfine Group Re
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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
Page 217 and 218: Water reflector Extrapolated B.C. B
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: ϕ i ( 0 u ) = ∑ Pij ( u) W j ( u
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 317 and 318: 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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