/*
 * DO NOT MANUALLY UPDATE THIS FILE.
 * If needed: make cpp_headers
 *
 * fortran2c.py - automatic conversion
 *       lowneu.inc -> lowneu.h
 */

#ifndef __LOWNEU__
#define __LOWNEU__

#include "types.h"

#ifdef __cplusplus
	extern "C" {
#endif

//
//=== lowneu ===========================================================*
//
//----------------------------------------------------------------------*
//                                                                      *
//     Copyright (C) 2003-2019:  CERN & INFN                            *
//     All Rights Reserved.                                             *
//                                                                      *
//     Created by Alfredo Ferrari on 6 July 1990                        *
//                                                                      *
//     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) = Continuous 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:
//  Maximum number of thermal neutron groups:
const double ENCNMN = 0.00000001E+00;
//  Maximum neutron weight profiles:
const int    MXGTHN = 35;
//  *** Partial kermas position definitions ***
const int    MXSHPP = 5;
//  Position in the kerma table of the correct(ed)   kerma
const int    MPKERM = 19;
//  Position in the kerma table of the elastic       kerma (k302)
const int    KCRKRM = 1;
//  Position in the kerma table of the nonelastic    kerma (k303)
const int    KELKRM = 2;
//  Position in the kerma table of the inelastic     kerma (k304)
const int    KNEKRM = 3;
//  Position in the kerma table of the "all other"   kerma (k305)
const int    KINKRM = 4;
//  Position in the kerma table of the fission       kerma (k318)
const int    KOTKRM = 5;
//  Position in the kerma table of the (n,n alpha)   kerma (k322)
const int    KFSKRM = 6;
//  Position in the kerma table of the (n,2n alpha)  kerma (k324)
const int    KNAKRM = 7;
//  Position in the kerma table of the (n,3n alpha)  kerma (k325)
const int    K2AKRM = 8;
//  Position in the kerma table of the (n,n p)       kerma (k328)
const int    K3AKRM = 9;
//  Position in the kerma table of the disappearence kerma (k401)
//  ((n,gamma) + (n,p) + (n,a) + ....)
const int    KNPKRM = 10;
//  Position in the kerma table of the (n,gamma)     kerma (k402)
const int    KDIKRM = 11;
//  Position in the kerma table of the (n,p)         kerma (k403)
const int    KCPKRM = MPKERM-7;
//  Position in the kerma table of the (n,alpha)     kerma (k407)
const int    KPRKRM = MPKERM-6;
//  Position of kinematic limit (kerma 443)
const int    KALKRM = MPKERM-5;
//  Position in the kerma table of the total         damage energy
const int    K443KR = MPKERM-4;
//  Position in the kerma table of the elastic       damage energy
const int    KNIELS = MPKERM-3;
//  Position in the kerma table of the inelastic     damage energy
const int    KELDMG = MPKERM-2;
//  Position in the kerma table of the disappearance damage energy
//  (MT's 102 through 120)
const int    KINDMG = MPKERM-1;
// *** Fission nu/chi parameters position definitions ***
//  Number of Neutrons per Fission:            <nu>        (MT = 452)
const int    KDIDMG = MPKERM;
//  Number of Delayed neutrons per fission:    <nu_del>    (MT = 455)
const int    KNUTTL = 1;
//  Number of Prompt Neutrons per Fission:     <nu_prompt> (MT = 456)
const int    KNUDLY = 2;
//                                              Chi_total  (MT = 470)
const int    KNUPRM = 3;
//                                              Chi_del    (MT = 471)
const int    KCHITT = 4;
//
const int    KCHIDL = 5;
extern struct {
	double	atolow[MXXMDF];
	double	wshpln[MXSHPP][MXGLWN];
	double	extwwl;
	double	shpimp[MXGLWN];
	double	extetl[MXGLWN];
	double	wwamfl;
	double	vllnth[MXXMDF+1][MXGTHN];
	double	enlnth[MXGTHN];
	double	ablnth[MXXMDF][MXGTHN];
	double	stlnth[MXXMDF][MXGTHN];
	double	tmrtln[MXXMDF];
	double	fnadef;
	double	tmnmln[MXXMDF];
	int	ichcpt[MXXMDF];
	int	igtmrt[MXXMDF];
	int	neumed[MXXMDF];
	int	id1med[MXXMDF];
	int	id2med[MXXMDF];
	int	id3med[MXXMDF];
	int	imd2nr[MXXMDF];
	logical	lcompn[MXXMDF];
	logical	lrecpr[MXXMDF];
	int	icnmed[MXXMDF];
	int	klnrnc[MXXMDF];
	int	ipwsgc[MXXMDF];
	int	kprlow;
	int	nmgp;
	int	nmtg;
	int	igrthn;
	logical	limprn;
	logical	lbiasn;
	logical	ldownn;
	logical	llowww;
	logical	llowet;
	int	iclmed;
	int	ikrbgn;
	int	ikpbgn;
	int	inabgn;
	int	idwbgn;
	int	ietbgn;
	int	i0xsec;
	int	idxsec;
	int	isenav;
	int	isveln;
	int	ispnav;
	int	iwwlwb;
	int	iwwlwt;
	int	ipxbgn;
	int	npxsec;
	int	npkerm;
	int	nnuchi;
	int	ngnaof;
	int	ngctff;
	logical	lpwxsc;
	logical	lnfcrt;
	logical	lexkrp;
	logical	lexnnu;
} lowneu_;
const int lowneu_vllnth_base = 0;

extern struct {
	char	titlow[MXXMDF][10];
} chlwnt_;


#ifdef __cplusplus
}
#endif
#endif