*$ CREATE LOWNEU.ADD *COPY LOWNEU * *=== lowneu ===========================================================* * *----------------------------------------------------------------------* * * * Copyright (C) 1990-2009 by Alfredo Ferrari * * All Rights Reserved. * * * * * * Created by Alfredo Ferrari on 6 july 1990 * * * * Last change on 18-sep-09 by Alfredo Ferrari, INFN - Milan * * * * Lowneu: contains data for the low energy neutron transport * * * * Included in the following routines: * * * * Bdnopt * * Blnset * * Deflts * * Donimb * * E6lipw * * Ev1hpw * * Eveneu * * Evepwn * * Evpwxs * * Evxtes * * Fiprou * * Flkend * * Flukam * * Grggen * * Grngen * * Kasneu * * Lnfrnc * * Lnrsnc * * Lowres * * Lowset * * Lwmcrd * * Lwncrd * * Stfspr * * Usrbdx * * Usrcll * * Usrtrk * * Usryld * * Xsprnt * * Xsread * * Xtlwnt * * Zeroin * * * * Description of the variables: * * * * Igrthn = number of thermal neutron groups, the groups from * * Nmgp - Igrthn + 1 up to Nmgp are considered to be * * thermal ones. After initialization it is transfor-* * med into the absolute group index of the first * * thermal group, that is, Nmgp - Igrthn + 1 * * Tmrtln (im) = Temperature ratio with respect to the nominal one * * for FLUKA medium im * * Tmnmln (im) = Nominal temperature for FLUKA medium im * * Igtmrt (im) = First (thermal) group where to apply Tmrtln (must * * be such that it is not larger than Nmgp to be * * meaningful) for FLUKA medium im. After initializa-* * tion it is transformed in absolute group number * * Vllnth (ig,im) = Velocity (cm/s) for ig_th thermal group for im_th * * FLUKA medium (im=0 means reference 293 K) * * This is the average over dN_Maxwell/dv which over * * [0,oo) gives v_0 x 2 / sqrt(pi), where v_0 is gi- * * ven by: v_0 = sqrt(2KT/m) x c_light * * Enlnth (ig,im) = Kinetic energy (GeV) for ig_th thermal group for * * the reference 293 K temperature. * * This is the average over dN_Maxwell/dE which over * * [0,oo) gives 3/2 KT, where the average on the flux* * is given by KT * * Ablnth (ig,im) = Absorption (and gamma generation) modifying factor* * for ig_th thermal group for im_th FLUKA medium * * Stlnth (ig,im) = Total cross section modifying factor for ig_th * * thermal group for im_th FLUKA medium * * Neumed(im) = Neutron xsec medium index (mm) corresponding to * * the im_th Fluka material * * Icnmed(mm) = Continuos energy index for the mm_th neut. xsec * * medium (if any, =<0 means no information) * * Klnrnc(mm) = starting location (0 index) in blank common of * * residual nuclei informations for the mm_th neut. * * xsec medium (if any, <0 means no information) * * Ipwsgc(mm) = index of a (possible) pointwise capture gamma data* * set for the mm_th neut. xsec medium (if any, =0 * * means no information) * * Imd2nr(mm) = ordinal index when read of the mm_th neut. xsec * * medium (1=1st read in etc) * * Fnadef = default non-analogue absorption factor to be * * applied to neutron groups from nmgp-ngnaof to nmgp* * Ngnaof = see above * * Ngctff = global neutron group cut-off: neutrons belonging * * to groups >= Ngctff are killed * * Lpwxsc = flag for using pointwise cross sections and/or * * explicit (n,gamma) generation when available * * Lnfcrt = flag for neutron fission criticality problems. It * * simply forces the number of fission neutrons to * * be 1 with a proper weight * * Lexkrp = flag for partial kermas * * Lexnnu = flag for fission nu and chi infos * * Npxsec = number of extra edit infos recorded in the cross * * section file * * 1: Probability of non-elastic scattering fission * * included (gamma production reactions) * * 2: Probability of non-elastic scattering with * * neutron production (all non-elastic reactions * * (n,xn), x >= 1, but not (n,fission)) * * 3: Probability of fission * * 4: Probability of (n,gamma) * * 5: Probability of (n,p) * * 6: Probability of (n,a) * * Npkerm = number of partial kermas * * Nnuchi = number of fission nu/chi values * * * *----------------------------------------------------------------------* * Minimum energy for (possible) point-wise treatments: PARAMETER ( ENCNMN = 0.00000001 D+00 ) * Maximum number of thermal neutron groups: PARAMETER ( MXGTHN = 35 ) * Maximum neutron weight profiles: PARAMETER ( MXSHPP = 5 ) * *** Partial kermas position definitions *** PARAMETER ( MPKERM = 19 ) * Position in the kerma table of the correct(ed) kerma PARAMETER ( KCRKRM = 1 ) * Position in the kerma table of the elastic kerma (k302) PARAMETER ( KELKRM = 2 ) * Position in the kerma table of the nonelastic kerma (k303) PARAMETER ( KNEKRM = 3 ) * Position in the kerma table of the inelastic kerma (k304) PARAMETER ( KINKRM = 4 ) * Position in the kerma table of the "all other" kerma (k305) PARAMETER ( KOTKRM = 5 ) * Position in the kerma table of the fission kerma (k318) PARAMETER ( KFSKRM = 6 ) * Position in the kerma table of the (n,n alpha) kerma (k322) PARAMETER ( KNAKRM = 7 ) * Position in the kerma table of the (n,2n alpha) kerma (k324) PARAMETER ( K2AKRM = 8 ) * Position in the kerma table of the (n,3n alpha) kerma (k325) PARAMETER ( K3AKRM = 9 ) * Position in the kerma table of the (n,n p) kerma (k328) PARAMETER ( KNPKRM = 10 ) * Position in the kerma table of the disappearence kerma (k401) * ((n,gamma) + (n,p) + (n,a) + ....) PARAMETER ( KDIKRM = 11 ) * Position in the kerma table of the (n,gamma) kerma (k402) PARAMETER ( KCPKRM = MPKERM-7 ) * Position in the kerma table of the (n,p) kerma (k403) PARAMETER ( KPRKRM = MPKERM-6 ) * Position in the kerma table of the (n,alpha) kerma (k407) PARAMETER ( KALKRM = MPKERM-5 ) * Position of kinematic limit (kerma 443) PARAMETER ( K443KR = MPKERM-4 ) * Position in the kerma table of the total damage energy PARAMETER ( KNIELS = MPKERM-3 ) * Position in the kerma table of the elastic damage energy PARAMETER ( KELDMG = MPKERM-2 ) * Position in the kerma table of the inelastic damage energy PARAMETER ( KINDMG = MPKERM-1 ) * Position in the kerma table of the disappearance damage energy * (MT's 102 through 120) PARAMETER ( KDIDMG = MPKERM ) * *** Fission nu/chi parameters position definitions *** * Number of Neutrons per Fission: (MT = 452) PARAMETER ( KNUTTL = 1 ) * Number of Delayed neutrons per fission: (MT = 455) PARAMETER ( KNUDLY = 2 ) * Number of Prompt Neutrons per Fission: (MT = 456) PARAMETER ( KNUPRM = 3 ) * Chi_total (MT = 470) PARAMETER ( KCHITT = 4 ) * Chi_del (MT = 471) PARAMETER ( KCHIDL = 5 ) * LOGICAL LCOMPN, LIMPRN, LBIASN, LDOWNN, LRECPR, LLOWWW, LLOWET, & LPWXSC, LNFCRT, LEXKRP, LEXNNU CHARACTER*10 TITLOW COMMON / LOWNEU / ATOLOW (MXXMDF), WSHPLN (MXGLWN,MXSHPP), EXTWWL, & SHPIMP (MXGLWN), EXTETL (MXGLWN), WWAMFL, & VLLNTH (MXGTHN,0:MXXMDF), ENLNTH (MXGTHN), & ABLNTH (MXGTHN,MXXMDF), STLNTH (MXGTHN,MXXMDF), & TMRTLN (MXXMDF), FNADEF, & TMNMLN (MXXMDF), ICHCPT (MXXMDF), & IGTMRT (MXXMDF), NEUMED (MXXMDF), & ID1MED (MXXMDF), ID2MED (MXXMDF), & ID3MED (MXXMDF), IMD2NR (MXXMDF), & LCOMPN (MXXMDF), LRECPR (MXXMDF), & ICNMED (MXXMDF), KLNRNC (MXXMDF), & IPWSGC (MXXMDF), KPRLOW, NMGP, NMTG , IGRTHN, & LIMPRN, LBIASN, LDOWNN, LLOWWW, LLOWET, ICLMED, & IKRBGN, IKPBGN, INABGN, IDWBGN, IETBGN, I0XSEC, & IDXSEC, ISENAV, ISVELN, ISPNAV, IWWLWB, IWWLWT, & IPXBGN, NPXSEC, NPKERM, NNUCHI, NGNAOF, NGCTFF, & LPWXSC, LNFCRT, LEXKRP, LEXNNU COMMON / CHLWNT / TITLOW (MXXMDF) SAVE / LOWNEU / SAVE / CHLWNT /