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7.8 一点炉動特性パラメータ ................................................................................................. 290 8. 断面積ライブラリに関する表 ................................................................................................. 291 8.1 核種を示す記号 .................................................................................................................. 291 8.2 パブリックライブラリ一覧 ............................................................................................... 294 8.3 エネルギー群構造 .............................................................................................................. 305 参考文献 ............................................................................................................................................. 309 x
1. General Descriptions 1.1 Functions and Features The SRAC system is designed to permit neutronics calculation for various types of thermal reactors. The system covers production of effective microscopic and macroscopic group cross-sections, and static cell and core calculations including burn-up analyses. The key parameters required in reactor design or experimental analysis are also provided. The present system, however, does not cover problems for photon transport, kinetics and coupling with thermal-hydraulics. The features of the system are in the following; • Several neutron cross-section libraries based on the latest JENDL, JEFF(JEF) and ENDF/B files are available for more than 300 nuclides. • The collision probability method code (PIJ) applicable to 16 types of geometries covers cell calculations for most of existing reactors. • User can compose his own calculational scheme by selecting and combining appropriate codes or optional functions in the system. For example, a variety of the transport codes are available for cell calculations (PIJ, 1D and 2D S N codes). For core calculations, 1D, 2D and 3D diffusion codes in addition to the above transport codes are also available. Interfacing of cross-section data between the codes is automatically done. • Three options are available for the resonance absorption calculation in the dominant resonance energy range. The effective cross-sections by the conventional table look-up method based on the narrow resonance (NR) approximation can be replaced by those based on the intermediate resonance (IR) approximation. Moreover a rigorous method is also provided by an optional routine PEACO which solves a multi-region cell problem by the collision probability method using an almost continuous (hyper-fine) energy group structure for the resonance energy range. The interaction of resonances can be accurately treated by the PEACO routine. • Arbitrary temperature of composite materials is allowed by the interpolation of resonance shielding factors and thermal scattering matrices. For the PEACO routine, Doppler broaden cross-sections in hyper-fine energy structure are internally calculated from the point-wise cross-sections at room temperature. • The Dancoff correction factor required in the interpolation of the self-shielding factors of 1
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: 5.4 三次元拡散計算 (CI
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 and 54: Only the first character (capital l
Page 55 and 56: NET ∑ i= 1 NEGT( i ) =(Total numb
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
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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
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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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Page 313 and 314:
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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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