anchor.diff:  	        WRITE(ounit,1015)g, (xsigs(i,g,h), h=1,ng)
   	    END DO
       END DO
  -END IF	
  +END IF
  +
  +IF (ccnuf .AND. mode /= 'FIXEDSRC') THEN
  +    WRITE(ounit, *) "ERROR: The Problem has no fission material (nu*fission for all materials are zero)" 
  +	STOP
  +END IF
  +IF (ccsigf .AND. mode /= 'FIXEDSRC') THEN
  +    WRITE(ounit, *) "ERROR: The Problem has no fission material (fission xsec for all materials are zero)"
  +	STOP
  +END IF
   
   WRITE(ounit,*)
  -WRITE(ounit,*) ' ...Macroscopic CXs are sucessfully read...'
  +WRITE(ounit,*) ' ...Macroscopic CX Card is sucessfully read...'
   
   1009 FORMAT(5X, 'MATERIAL', I3)
   1011 FORMAT(2X, A7, A12, A13, A12, A11, 2A13, A15)
   1010 FORMAT(2X, I6, F13.6, 3F12.6, 3F13.6)
   1015 FORMAT(4X, I3, F16.6, 20F12.6)
  -1020 FORMAT(2X, 'ERROR: Transport cross section (sigtr)is zero or less in material: ', I3, ' ;group: ', I3)
  +1020 FORMAT(2X, 'ERROR: Transport cross section (sigtr)is zero or negative in material: ', I3, ' ;group: ', I3)
   
   DEALLOCATE(group)
   
  
positive.code: WRITE(ounit,*)
  WRITE(ounit,*) ' ...Core geometry is sucessfully read...'
  
  END SUBROUTINE inp_geom2
  
  
  
  SUBROUTINE misc ()
  !
  ! Purpose:
  !    To assign material xsec to nodes
  !    To arranges the nodes into 1-D array instead of 3-D array
  !
  !   Date                Programmer           History
  !  ========================================================
  !  6 FEB 2017         Muhammad Imron       Original code
  
  USE sdata, ONLY: nxx, nyy, nzz, ix, iy, iz, xyz, &
  				 nnod, sigtr, siga, nuf, sigf, zdel, &
                   chi, sigs, D, sigr, ng, ystag
  
  IMPLICIT NONE
  
  INTEGER :: i, j, k, n
  INTEGER, DIMENSION(:), ALLOCATABLE :: mat
  
  ! set nnod
  nnod = 0
  DO k = 1, nzz
      DO j = 1, nyy
  
negative.code: INTEGER :: i, j, k, n, ztot
  INTEGER :: ly, lx, ys, xs, yf, xf, lz
  REAL :: summ, vsumm
  REAL, DIMENSION(nz) :: faxi
  REAL :: totp
  INTEGER :: nfuel
  REAL :: fmax
  