!: v. 2.21: 15-MAY-2005 IAEA-NDS-87 Rev. 9, May 2005 DROSG-2000: Neutron Source Reactions Data files with computer codes for 59 accelerator-based two-body neutron source reactions prepared by M. Drosg Institute for Experimental Physics University of Vienna Summary documentation Abstract: This package contains data and three computer codes to calculate: - neutron energies, differential cross-sections and differential yields; - thick-target yields and white neutron spectra from monoenergetic neutron producing reactions; - differential cross sections and energies of (n,p), (n,d), (n,t) and (n,4He) reactions which are time-reversed neutron production reactions (using detailed balance calculations) The package is available on PC diskette from the IAEA Nuclear Data Section or can be downloaded http://www-nds.iaea.org . This package supersedes the package DROSG-96. Citation guideline: This database should be cited as follows: M. Drosg, DROSG-2000, Codes and database for 59 neutron source reactions, documented in the IAEA report IAEA-NDS-87 Rev. 9 (May 2005), received from the IAEA Nuclear Data Section. DROSG-2000 Neutron Source Reactions Data files with the computer codes for 59 accelerator-based two-body neutron source reactions 0. Update history........................................... 1 1. Introduction ............................................ 1 2. Accuracies .............................................. 2 2.1 Kinematics ............................................... 2 2.2 Cross sections ........................................... 2 2.3 Yields ................................................... 3 2.4 Time-reversed data ...................................... 4 3. Description of codes .................................... 4 3.1 NEUYIE .................................................. 4 3.2 WHIYIE ................................................... 6 3.3 TIMREV ................................................... 9 References ..................................................... 10 Appendices ...................................................... 11 1) List of files ........................................ 11 2) List of papers on neutron sources by the same author . 13 3) List of error messages with explanations ............. 16 4) Disclaimer ........................................... 17 0. UPDATE history UPDATES: !: VERSION 2.21: 15-MAY-2005 changed MASS.TAB from 1995 nuclear masses to 2003 nuclear masses removed some mistakes in text files only 1 executable for MS operating systems !: VERSION 2.2: 02-JAN-2003 Database: rearranged SETYIE.TAB to accomodate two new reactions: 18O(p,n)18F and 14N(d,n)15O; and five new targets: 202 d-octane target, 203 LiD target, 702 7LiH target, 902 7LiH target, 313 LiD target. extended differential cross section energy range for p-7Li using ENDF/B-VI MOD 1 Evaluation, July 1999 by M.B. Chadwick,P.G.Young. Code: in file NEUYIE: rearranged input in subr. RDSTUP to match new SETYIE.TAB in files ANGCAL,ANGINP,ENINPO,LEGINT,NEUYIE,NYIOUT,RECOUT and WHIOUT variable HANGSA now in COMMON /masse/ in file ENINPO: in subr. WHISUM: now output of 1st angle in files ANGINP,LEGINT and NEUYIE added BLANK='NULL' in all OPEN statements for files that are read in file ANGCAL: increased number of digits of ENT in FORMAT 100 (display) in file RECOUT: increased number of digits in printout in file WHIOUT: in subroutine PLDTIN: changed FORMAT 100 !: VERSION 2.1: 02-JAN-2002 Minor changes in data files D2HAGS.koe, D3HAGS.koe, D9BEGS.koe, P3HAGS.koe, P7LIGS.koe and P7LIES.koe; changes of the source code in 6 of the 9 *.f90 files as indicated: ANGINP.F90 Added exit on error for angle input by file option CHKANG.F90 changed format of threshold output ENINPO.F90 changed wording of 2 messages NYIOUT.F90 added output of Q-value RECOUT.F90 changed FORMAT # 87 WHIOUT.F90 added output of exit energy of beam in *.spc !: VERSION 2.0: 17-NOV-2000 Code was made compatible with LAHEY-FORTRAN for LINUX and for DEC-UNIX a) Major changes were necessary to maintain "default" capabilities. Subroutine NDEFLT has now 5 arguments so that it can handle an input pair. b) All commas (used for data separation) in data files (*.KOE, *.tab) were removed. As a consequence a few FORMAT changes were necessary. c) To avoid warnings during compilation none of the COMMON blocks (in all the subroutines) is truncated any more and dummy variables were removed. d) Two COMMON blocks were changed to avoid misalignment messages. e) No capital letters for file names (UNIX!) in the calling routines any more. f) A new reaction was added: 9Be(d,n)10B g) A new target type (LiF) was added for the 7Li(p,n) reactions. ! !: VERSION 1.01: 19-MAR-2000 a) Clean-up of COMMON blocks: CHARACTER variables put together b) Several redundancies removed, e.g. in ANGSET: redundancy concerning 'LOW energy group OPTION= 1:' removed c) Several FORMATS changed to allow much smaller values, e.g. in OUTPUT of NYIOUT.F90: FORMAT 185 and 186 d) in BELTHR check for XXC=0. before /XXC e) introduced minimum energy step number for WHIYIE f) new flag LGERR avoids output of negative cross sections g) added subroutine SPCAVG for WHIYIE From DROSG-87 to DROSG-2000: The original package named DROSG-87 [1] provided energy and differential cross section data of p-T, d-D, d-T, p-7Li and their inverse counterparts. The first source code was just about three pages of FORTRAN-IV [1]. Soon it was clear that differential neutron yield data were of much interest so that neutron sources could be compared. After this feature had been included (in the code NEUYIE, "neutron yield") it was straightforward to provide thick-target neutron yield information by way of the code WHIYIE ("white yield"). When a need arose to predict the differential yields and energies of (n, charged particle) reactions in 3He counters, it was easy to introduce the necessary detailed balance calculations into NEUYIE to generate the code TIMREV which gives the energy and cross section data of the time reversed reactions covered by NEUYIE. When heavy ion acceleration became more common, inverse (p,n) and (d,n) reactions had to be considered. In general, inverse reactions have very desirable properties: wider monoenergetic range and, for endothermic reactions, kinematic neutron collimation with enhanced laboratory cross sections. Therefore, a revised package (DROSG-96) took care of this development: it included the three codes and provided data bases for 15 (p,n) reactions and 7 (d,n) reactions, so that together with inverse reactions 33 neutron source reactions were covered. The latest package, DROSG-2000, supersedes DROSG-96 and DROSG-87. It is a major revision. 1) All iteration routines were changed. They are based now on physical properties so that convergence is guaranteed under any input condition. Besides any iteration occurs within about 25 steps increasing the speed in some cases considerably. 2) All calculations are done now with double precision. 3) Some relevant physical properties (thresholds, double valued range and opening angle of kinematically collimated sources) are made available right after the selection of the desired source reaction, and energy, resp.. 4) Some (exotic) monoenergetic (d,n) reactions and (alpha,n) reactions and their inverse reactions were added so that the data base comprises 15 (p,n) reactions 11 (d,n) reactions and 5 (alpha,n) reactions. Including the inverse reactions a total of 57 neutron producing reactions are presently provided. 1. Introduction The package contains 3 codes: 1) NEUYIE: Accelerator-based mononenergetic neutron production This program calculates neutron energies, differential cross sections and (for isotopic pure targets) differential neutron yields for monoenergetic neutron sources using internal tables. The Legendre coefficients of the differential cross sections are stored in the files *.KOE, the energy loss tables needed for the neutron yield calculations in the files *.ELS. The neutron yields are given for an energy loss of the projectile that results in a 10 keV neutron energy spread at 0 degree. 2) WHIYIE: White neutron yields from two-body reactions This program calculates angular differential thick-target neutron yields of white neutron sources that are based on the two-body reactions covered under 1). As an option, a white spectrum at a chosen angle ready for plotting is produced. 3) TIMREV: Differential cross sections and energies of (n,p), (n,d), (n,t) and (n,alpha) reactions This program calculates differential cross sections and energies of some (n,p), (n,d), (n,t) and (n,alpha) reactions by detailed balance from the time reversed reactions covered under 1). As these codes have much in common (a good deal of the source code, data files) they are joined together in this package. The source code is written in FORTRAN which is fully compatible with FORTRAN-95. Executables are provided to run under OPEN- VMS (*.exe for VAXes, *.e90 for ALPHAs) under LINUX (PCs), under DECUNIX and under MS-WINDOWS (*.exe, compiled with a LAHEY F90 compiler, requires at least a 386 processor). For those who want to adjust the source code to their needs or who are using a different computer platform the COMPILATION and LINKING procedures (under OPEN-VMS: xxxLINK.COM and xxxLI90.COM , under MSDOS for the LAHEY compilers: MAKEF77.BAT and MAKEF90.BAT) should be helpful. The regular O U T P U T of all three codes is put in File FOR002.DAT. It will be overwritten for each run. The neutron source reactions in NEUYIE were either chosen because of their practical importance or because of some distinct personal interest of the author in that source. Adding a further reaction is straight-forward: add the corresponding data in the files MASS.TAB and SET*.TAB and add the cross section table (xxx.KOE) and energy loss table (yyy.ELS). Interpolation in the cross section tables is done by SPLINE fitting. If the data show narrow structures a sufficient number of points are needed to give reasonable interpolated data. The interpolation is checked internally for necessary conditions and an error message (see Appendix) is given when this check fails. For the generation of excitation functions the use of the tabulated energies is preferred. Therefore, such a provision is included into NEUYIE (see there). 2. Accuracies 2.1 Kinematics: The kinematic properties are calculated with the 2003 [2] (nuclear) masses using relativistic expressions. In most cases (not near thresholds) the mass uncertainty can be disregarded. It is assumed that the interacting nuclei are completely stripped which need not be true under special circumstances. The mass data (given in MeV) are stored in MASS.TAB. All energies are in MeV unless given otherwise, all angles are in degrees. 2.2 Cross sections: The accuracy of the differential cross sections stored in the 34 *.KOE data files must be dealt with individually. Observe the comments in the comment section at the end of each file. Only p-T, d-D and d-T differential cross sections are based on measurements of this author. The error discussion for these reactions and for p-7Li given in [1] is still valid, even if the recommended cross section values have changed. The evaluated integrated data of d-D above 2.34 MeV and of d-T above 6 MeV which were taken over by the LLNL group in their 1991 evaluation [3](without giving credit!), might be more accurate than given in [1]. For unknown reasons this group assigned errors to these data which are about a factor of two smaller than obtained from the original work. Some more information on the accuracy of the cross sections can be found in the literature given in the Appendix. Three classes of cross section data are used in the code: a) Complete angular distributions of differential cross sections in some energy range for: 3H(p,n)3He, 7Li(p,n0)7Be, 7Li(p,n1)7Be*, 9Be(p,n0)9B, 11B(p,n0)11C, 13C(p,n0)13N, 15N(p,n0)15O, 2H(d,n)3He, 3H(d,n)4He, 3H(4He,n0)6Li b) Differential cross sections at 0 deg AND/OR 180 deg. In several cases just isotropic approximation from integrated cross sections: 6Li(p,n0)6Be, 10Be(p,n0)10B, 10B(p,n0)10C, 14C(p,n0)14N, 36Cl(p,n)36Ar, 39Ar(p,n0)39K, 59Co(p,n)59Ni, 7Li(d,n)8Be, 9Be(d,n)10B, 11B(d,n)12C, 13C(d,n)14N, 15N(d,n)16O, 18O(d,n)19F, 7Li(4He,n)10B, 11B(4He,n)14N, 13C(4He,n)16O, 22Ne(4He,n)25Mg c) Dummy data: 12C(p,n)12N, 20Ne(d,n)21Na, 24Mg(d,n)25Al, 28Si(d,n)29P, 32S(d,n)33Cl In several cases (n,p), (n,d) and (n,4He) data were taken from the neutron data files (e.g. ENDF) and converted to (p,n), (d,n) and (4He,n) data. The use of such integrated data is indicated in the menu by the REMARK "isotropic approximation". Special care must be taken in cases in which the cross section includes those of reactions to excited states. If only such data are available this is indicated by the omission of "0" [(x,n) instead of (x,n0)]. Mixed data files, i.e. data files that contain data of more than one class, can be recognized in the menu by the slash (/) in the "X-section range". For class a) data ONLY, there will be a warning when there are no complete angular distributions: "ENERGY OUT OF RANGE OF LEGENDRE TABLE, check validity" WARNING: Be aware that the answer you get may be seriously off, because it is only as good as the input cross sections are. If you must rely on the answer for a specific reaction, check first the data file and improve it if necessary. Changing the data base in any *.KOE file is straightforward. All cross sections are in millibarns or millibarns/steradian resp.. 2.3 Yields: Yields are calculated assuming such a target thickness that at 0 deg the neutron energy spread is 10 keV (the corresponding target thickness is given by the energy loss of the projectiles in output file FOR002.DAT). The electronic stopping power needed for this calculation is stored in the *.ELS data files. These are usually based on data of ZIEGLER [4] unless shown otherwise at the end of each file. For energies which are moderately higher than the low energy maximum of the stopping power the solutions of different authors differ by typically 5 to 10%. Using the values of Ziegler [4] appeared to be the best in several cases. Therefore, these data were finally chosen for this code. However, anybody can easily change any *.ELS file to use his/her own favorite energy loss data. The data in these files are in units of MeV/(g/sqcm) vs. MeV. In the DOUBLE-VALUED region (of endothermic reactions) the predicted angular differential thick-target neutron yield (vanishing solid angle) cannot always be taken to be a good approximation of the measured thick-target yield, because of the possibility of a (very) strong nonlinear angular dependence which requires an integration over the opening angle of the detector. In NEUYIE the differential neutron yield is given in units of: neutrons/(sr*pC) for a 10 keV neutron energy spread at 0 degree. In WHIYIE the units in the *.SPC files are: neutrons/MeV/sr/microCoulomb vs. MeV. 2.4 Time reversed data: The spins needed for the detailed balance calculations are stored in MASS.TAB. The degeneracy factor of the d-D reaction [5] is put into SETREC.TAB. Time reversal is done relativistically. The conversion of data at very low energies to those near threshold and vice versa is strongly dependent on the accurate knowledge of the nuclear masses (and the energies) and consequently less accurate. 3. Description of codes 3.1 NEUYIE (Mononenergetic neutron production) This program calculates neutron energies and differential cross sections for monoenergetic neutron sources from internal tables of the Legendre coefficients. For isotopic pure targets (and others) it also can calculate the neutron yield using energy loss tables. The neutron yields are for an energy loss of the projectile that results in a 10 keV neutron energy spread at 0 degree. The main menu is shown below together with a sample input. The interactive program is self-explaining, the main menu more or less, too, except for 'En0 RANGE' which means the monoenergetic neutron energy range at 0 degree available by that reaction, and the slash (/) in the X-SECTION RANGE column which indicates mixed classes of cross sections in the *.KOE table (see 2.2). If there is no truly monoenergetic range like in some exothermic reactions the numbers of neutron lines at 0 MeV incoming energy is indicated by '>=n lv', meaning that n levels are exited at zero incoming energy. If "-2" is chosen as "number of energy steps" (see below) the actual energies from the Legendre tables are selected to avoid interpolation errors (which is essential when generating plot files of excitation functions in cases with a strong structure in the cross sections). 3.1.1 Main menu and sample terminal responses: MONOENERGETIC NEUTRON PRODUCTION (isotopically pure targets) ID REACTION TYPE REMARKS En0 RANGE X-SECTION RANGE [MeV] Traditional Sources 1 3H(p,n)3He gas target 0.064-7.585 1.0191-32.80/318. 101 T2O target 2 2H(d,n)3He gas target 2.449-7.706 0.02 - 39.80/85. 201 D2O target / 202 d-octane target / 203 LiD target 3 1H(t,n)3He gas target 0.574-17.64 3.051 - 98.19 301 water target / 302 octane target 4 3H(d,n)4He gas target 14.03-20.46 0.01 - 40.00/400. 401 T2O target 5 2H(t,n)4He gas target 14.03-23.01 0.015- 59.9/599. 501 D2O target 7 7Li(p,n0)7Be 0.030-0.650 1.8807-23.00/494. 701 7LiF target / 702 7LiH target 8 1H(7Li,n0)7Be 1.441-3.842 13.097- 160.165 9 7Li(p,n1)7Be* (0.429 MeV level) 0.038-1.557 2.40 - 150. 901 7LiF target / 902 7LiH target 10 1H(7Li,n1)7Be* (0.429 MeV level) 1.816-7.231 16.713-1044.56 LESS COMMON (p,n)-SOURCES 11 6Li(p,n0)6Be isotropic approx. 0.122-1.172 6.00 - 7.874/200. 12 9Be(p,n0)9B - 2.20 - 30.0 13 10Be(p,n0)10B isotropic approx. 0.002-0.310 0.251 - 1.040/20.247 14 1H(10Be,n0)10B isotropic approx. .2068-3.012 2.495 - 10.337/201.2 15 10B(p,n0)10C isotropic approx. 0.041-4.055 4.94 - 8.571/17.1 16 11B(p,n0)11C 0.021-2.388 3.020/3.5 - 5.49/26. 17 1H(11B,n0)11C 2.538-11.88 33.-59.989/284.1 18 12C(p,n)12N zero degree only 0.119-1.200 25.8 19 13C(p,n0)13N 0.017-2.278 3.239 - 12.86/30.6 20 1H(13C,n0)13N 2.792-12.18 41.803/112.28-165.97 21 14C(p,n0)14N isotropic approx. 0.003-2.522 0.6714 - 3.151/20.67 22 1H(14C,n0)14N isotropic approx. 0.586-9.782 9.332 - 43.795/287.2 23 15N(p,n0)15O 0.015-5.742 3.94 - 15.62 24 1H(15N,n0)15O 3.319-25.73 58.659 -232.549 59 18O(p,n)18F isotropic approx. 0.008-1.199 2.58 - 20. 25 36Cl(p,n)36Ar isotropic approx. .0001-2.028 0.878 - 2.103 26 1H(36Cl,n)36Ar isotropic approx. 0.074-7.826 31.35 - 75.08 27 39Ar(p,n0)39K isotropic approx. .0002-2.593 1.225 - 1.300/20.224 28 1H(39Ar,n0)39K isotropic approx. 0.214-10.28 47.367 - 50.28/782.1 29 59Co(p,n)59Ni isotropic approx. .0006-0.363 1.8897 - 2.240/11.89 30 1H(59Co,n)59Ni isotropic approx. 1.830-4.198 110.534 - 131./695.5 LESS COMMON (d,n)-SOURCES 31 7Li(d,n)8Be isotropic approx. >=3 lv 0.01 - 10.957 313 LiD target 32 2H(7Li,n)8Be isotropic approx. >=3 lv 0.035 - 38.5 33 9Be(d,n0)10B isotropic approx. >=5 lv 0.05 - 0.121/16.89 34 11B(d,n)12C isotropic approx. >=10 lv 0.411 - 2.513/5.564 35 2H(11B,n)12C isotropic approx. >=10 lv 2.247 - 13.82/30.6 36 13C(d,n)14N isotropic approx. >=5 lv 0.312 - 3.568 37 2H(13C,n)14N isotropic approx. >=5 lv 2.028 - 23.04 60 14N(d,n)15O isotropic approx. 4.765-4.997 1. - 15. 38 15N(d,n)16O isotropic approx. >=8 lv 2.13E-4 - 5.979/10.1 39 2H(15N,n)16O isotropic approx. >=8 lv 0.0016 - 44.53/75.2 40 18O(d,n)19F isotropic approx. >10 lv 0.975 - 2.204/14.696 41 20Ne(d,n)21Na dummy data 0.197-0.344 1.E-5 - 0.140 42 2H(20Ne,n)21Na dummy data 0.197-0.644 1.E-4 - 1.390 43 24Mg(d,n)25Al dummy data 0.044-0.483 1.E-5 - 0.650 44 2H(24Mg,n)25Al dummy data 0.044-1.192 1.2E-4 - 7.740 45 28Si(d,n)29P dummy data 0.505-1.445 1.E-5 - 1.000 46 2H(28Si,n)29P dummy data 0.505-3.208 1.4E-4 - 13.891 47 32S(d,n)33Cl dummy data 0.049-0.855 1.E-5 - 0.900 48 2H(32S,n)33Cl dummy data 0.049-2.207 1.6E-4 - 14.286 (alpha,n)-SOURCES 49 3H(4He,n)6Li 0.913-4.916 11.134-13.128/51.0 50 4He(3H,n)6Li 0.519-3.794 8.3906-9.893/38.4 51 7Li(4He,n)10B isotropic approx. 0.146-1.528 4.3821-5.5106 52 4He(7Li,n)10B isotropic approx. 0.449-2.429 7.6815-9.6596 53 11B(4He,n)14N isotropic approx. 0.148-2.885 0.167-2.9396 54 4He(11B,n)14N isotropic approx. 0.148-4.412 0.460-8.086 55 13C(4He,n)16O isotropic approx. 2.084-7.024 0.0559-5.025 56 4He(13C,n)16O isotropic approx. 2.084-10.54 0.1816-16.325 57 22Ne(4He,n)25Mg isotropic approx. 0.004-0.700 0.5671 - 3.0 58 4He(22Ne,n)25Mg isotropic approx. 0.103-1.504 3.1159 - 16.483 Enter ID, negative for YIELD calculation - blank continues table: -4 Uses 2003 mass table NEUTRONS from the REACTION 3H(d,n)4He PROJECTILE energy or NEGATIVE 0-deg NEUTRON energy in MeV or for END: 1. Energy steps OPTION: + or - step size, nr. of steps; OR using tabulated energy values: MAXIMUM energy, -2; 40.,2 NUMBER of ANGLES, NEGATIVE if C.M., blank for FILE: -3 INPUT of ANGLE values: LINE-BY-LINE or "" for other OPTIONS Constant SPACING options: COSINE= 2, DEF.= degrees: Enter MIN. and MAX. angle of RANGE, DEFAULT= full range: 10.,20. Const. spacing OPTION: RANGE from 10.00 to 20.00 is divided into 2 portions ! Energy out of range of LEGENDRE table, check validity PROJECTILE energy or NEGATIVE 0-deg NEUTRON energy in MeV or for END: Stopped because of BLANK energy INPUT COMMENT: cross section and yield data depend on data base in file: d3hags.koe FORTRAN STOP 3.1.2 Output (FOR002.DAT): NEUTRONS FROM THE REACTION 3H(d,n)4He INCIDENT LAB ENERGY 0.999999 INT. CROSS SECT.= 2.316E+02 mb INTEGRAL YIELD with a 10 keV SPREAD at 0 Deg= 4.337E+00 n/pC Total energy= 4685.1332 MeV,Momentum of projectile= 36.7250,Q= 17.5892470 LABORATORY SYSTEM CENTER-OF-MASS 5.962E+00 keV target thickness ANGLE CROSS ENERGY ANGLE CROSS neutrons/(sr*pC) for a 10 SECTION SECTION keV neutron energy spread DEGREE mb/sr MeV DEGREE mb/sr at 0 D due to energy loss 9.30 21.971 16.72144 10.00 19.036 4.114E-01 13.96 21.908 16.68052 15.00 19.027 4.102E-01 18.62 21.826 16.62368 20.00 19.019 4.087E-01 NEUTRONS FROM THE REACTION 3H(d,n)4He INCIDENT LAB ENERGY 41.000002 INT. CROSS SECT.= 1.441E+01 mb ! Energy out of range of LEGENDRE table, check validity INTEGRAL YIELD with a 10 keV SPREAD at 0 Deg= 9.985E+00 n/pC Total energy= 4709.0537 MeV,Momentum of projectile= 235.2041,Q= 17.5892470 LABORATORY SYSTEM CENTER-OF-MASS 1.033E+01 keV target thickness ANGLE CROSS ENERGY ANGLE CROSS neutrons/(sr*pC) for a 10 SECTION SECTION keV neutron energy spread DEGREE mb/sr MeV DEGREE mb/sr at 0 D due to energy loss 7.55 23.363 57.80428 10.00 13.367 1.619E+01 11.34 22.397 57.40395 15.00 12.893 1.552E+01 15.13 21.091 56.84776 20.00 12.245 1.461E+01 3.2 WHIYIE (White neutron yields from two-body reactions) This program calculates angular differential thick-target yields of white neutron sources that are based on the two-body reactions covered in 3.1.1. (See above warning with regard to yields in the double-valued region!) As an option, a white spectrum ready for plotting is produced. The main menu is shown below together with a sample input. The interactive program is self-explaining, the main menu more or less, too, except, like in NEUYIE, for En0max which means the maximum clean monoenergetic neutron energy available by that reaction, and the slash (/) in the X-SECTION RANGE column indicating mixed classes of cross sections in the *.KOE table (see 2.2). The main difference to NEUYIE is as follows: INPUT: a) energy steps are NEGATIVE only b) energy steps are NEUTRON energy at 0 deg, even if the starting energy is projectile energy! c) angles are lab only OUTPUTs: a) FOR002.DAT: - no c.m. data - Additional summary data (in parallel to display) as follows: ENERGY integr. Yield at 0 deg = xxxx n per sr.picoCoul. abs. TOTAL neutron output = yyyy neutrons per picoCoul. b) FOR001.DAT: This output can be used to generate one's own white neutron spectrum. - 7 data per line for each energy step (and angle): angle, neutron energy, yield per 10 keV at 0 deg, beam energy, 0-deg neutron energy step size, integrated yield/MeV, integrated cross section c) aaaann.SPC: - neutron energy - double differential yield pairs, intended for plotting (intrinsic white neutron spectrum). WARNING: This output file will be overwritten in a following run if the complete filename is equal. 3.2.1 Main Menu and sample terminal responses: WHITE NEUTRON PRODUCTION (isotopically pure targets) ID REACTION TYPE REMARKS En0 RANGE X-SECTION RANGE [MeV] Traditional Sources 1 3H(p,n)3He gas target 0.064-7.585 1.0191-32.80/318. 101 T2O target 2 2H(d,n)3He gas target 2.449-7.706 0.02 - 39.80/85. 201 D2O target / 202 d-octane target / 203 LiD target 3 1H(t,n)3He gas target 0.574-17.64 3.051 - 98.19 301 water target / 302 octane target 4 3H(d,n)4He gas target 14.03-20.46 0.01 - 40.00/400. 401 T2O target 5 2H(t,n)4He gas target 14.03-23.01 0.015- 59.9/599. 501 D2O target 7 7Li(p,n0)7Be 0.030-0.650 1.8807-23.00/494. 701 7LiF target / 702 7LiH target 8 1H(7Li,n0)7Be 1.441-3.842 13.097- 160.165 9 7Li(p,n1)7Be* (0.429 MeV level) 0.038-1.557 2.40 - 150. 901 7LiF target / 902 7LiH target 10 1H(7Li,n1)7Be* (0.429 MeV level) 1.816-7.231 16.713-1044.56 LESS COMMON (p,n)-SOURCES 11 6Li(p,n0)6Be isotropic approx. 0.122-1.172 6.00 - 7.874/200. 12 9Be(p,n0)9B - 2.20 - 30.0 13 10Be(p,n0)10B isotropic approx. 0.002-0.310 0.251 - 1.040/20.247 14 1H(10Be,n0)10B isotropic approx. .2068-3.012 2.495 - 10.337/201.2 15 10B(p,n0)10C isotropic approx. 0.041-4.055 4.94 - 8.571/17.1 16 11B(p,n0)11C 0.021-2.388 3.020/3.5 - 5.49/26. 17 1H(11B,n0)11C 2.538-11.88 33.-59.989/284.1 18 12C(p,n)12N zero degree only 0.119-1.200 25.8 19 13C(p,n0)13N 0.017-2.278 3.239 - 12.86/30.6 20 1H(13C,n0)13N 2.792-12.18 41.803/112.28-165.97 21 14C(p,n0)14N isotropic approx. 0.003-2.522 0.6714 - 3.151/20.67 22 1H(14C,n0)14N isotropic approx. 0.586-9.782 9.332 - 43.795/287.2 23 15N(p,n0)15O 0.015-5.742 3.94 - 15.62 24 1H(15N,n0)15O 3.319-25.73 58.659 -232.549 59 18O(p,n)18F isotropic approx. 0.008-1.199 2.58 - 20. 25 36Cl(p,n)36Ar isotropic approx. .0001-2.028 0.878 - 2.103 26 1H(36Cl,n)36Ar isotropic approx. 0.074-7.826 31.35 - 75.08 27 39Ar(p,n0)39K isotropic approx. .0002-2.593 1.225 - 1.300/20.224 28 1H(39Ar,n0)39K isotropic approx. 0.214-10.28 47.367 - 50.28/782.1 29 59Co(p,n)59Ni isotropic approx. .0006-0.363 1.8897 - 2.240/11.89 30 1H(59Co,n)59Ni isotropic approx. 1.830-4.198 110.534 - 131./695.5 LESS COMMON (d,n)-SOURCES 31 7Li(d,n)8Be isotropic approx. >=3 lv 0.01 - 10.957 313 LiD target 32 2H(7Li,n)8Be isotropic approx. >=3 lv 0.035 - 38.5 33 9Be(d,n0)10B isotropic approx. >=5 lv 0.05 - 0.121/16.89 34 11B(d,n)12C isotropic approx. >=10 lv 0.411 - 2.513/5.564 35 2H(11B,n)12C isotropic approx. >=10 lv 2.247 - 13.82/30.6 36 13C(d,n)14N isotropic approx. >=5 lv 0.312 - 3.568 37 2H(13C,n)14N isotropic approx. >=5 lv 2.028 - 23.04 60 14N(d,n)15O isotropic approx. 4.765-4.997 1. - 15. 38 15N(d,n)16O isotropic approx. >=8 lv 2.13E-4 - 5.979/10.1 39 2H(15N,n)16O isotropic approx. >=8 lv 0.0016 - 44.53/75.2 40 18O(d,n)19F isotropic approx. >10 lv 0.975 - 2.204/14.696 41 20Ne(d,n)21Na dummy data 0.197-0.344 1.E-5 - 0.140 42 2H(20Ne,n)21Na dummy data 0.197-0.644 1.E-4 - 1.390 43 24Mg(d,n)25Al dummy data 0.044-0.483 1.E-5 - 0.650 44 2H(24Mg,n)25Al dummy data 0.044-1.192 1.2E-4 - 7.740 45 28Si(d,n)29P dummy data 0.505-1.445 1.E-5 - 1.000 46 2H(28Si,n)29P dummy data 0.505-3.208 1.4E-4 - 13.891 47 32S(d,n)33Cl dummy data 0.049-0.855 1.E-5 - 0.900 48 2H(32S,n)33Cl dummy data 0.049-2.207 1.6E-4 - 14.286 (alpha,n)-SOURCES 49 3H(4He,n)6Li 0.913-4.916 11.134-13.128/51.0 50 4He(3H,n)6Li 0.519-3.794 8.3906-9.893/38.4 51 7Li(4He,n)10B isotropic approx. 0.146-1.528 4.3821-5.5106 52 4He(7Li,n)10B isotropic approx. 0.449-2.429 7.6815-9.6596 53 11B(4He,n)14N isotropic approx. 0.148-2.885 0.167-2.9396 54 4He(11B,n)14N isotropic approx. 0.148-4.412 0.460-8.086 55 13C(4He,n)16O isotropic approx. 2.084-7.024 0.0559-5.025 56 4He(13C,n)16O isotropic approx. 2.084-10.54 0.1816-16.325 57 22Ne(4He,n)25Mg isotropic approx. 0.004-0.700 0.5671 - 3.0 58 4He(22Ne,n)25Mg isotropic approx. 0.103-1.504 3.1159 - 16.483 Enter ID - blank continues the table: 7 Uses 2003 mass table NEUTRONS from the REACTION 7Li(p,n0)7Be Between 1.880769 and 1.920461 MeV LAB cross sections are double valued If starting energy is in the double valued range, the LOW-energy branch is automatically included. BEAM energy or NEGATIVE maximum 0-deg NEUTRON energy in MeV or for END: -3. Neutron energy SPACING at 0 deg, Nr. of energy STEPS: 0.1,4 NUMBER of ANGLES (lab.); if 1, a yield vs. energy file *.SPC is generated 1 INPUT of ONE angle: 15. abs. TOTAL neutron output= 6.645E+02 neutrons per pC BEAM energy or NEGATIVE maximum 0-deg NEUTRON energy in MeV or for END: Stopped because of BLANK energy INPUT Opens INPUT file: for001.dat Number of projectiles lost by two-body nuclear reactions per pC 664.52 Opens OUTPUT file: p7li04.spc : p7li 4.670880 MeV 15.00 deg, beam exits w/ 4.373260 MeV AVERAGE neutron energy at 15.0 deg 2.824 MeV, using 3. scans COMMENT: cross section and yield data depend on data base in file: p7ligs.koe 3.2.2 Sample outputs: a) FOR002.DAT: INCIDENT LAB ENERGY 4.670881 INT. CROSS SECT.= 3.211E+02 mb LABORATORY SYSTEM 9.928E+00 keV target thickness ANGLE CROSS ENERGY neutrons/(sr*pC) for a 10 SECTION keV neutron energy spread DEGREE mb/sr MeV at 0 D due to energy loss 15.000 5.456E+01 2.9621E+00 4.121E+00 INCIDENT LAB ENERGY 4.571630 INT. CROSS SECT.= 3.071E+02 mb LABORATORY SYSTEM 9.923E+00 keV target thickness ANGLE CROSS ENERGY neutrons/(sr*pC) for a 10 SECTION keV neutron energy spread DEGREE mb/sr MeV at 0 D due to energy loss 15.000 5.048E+01 2.8631E+00 3.746E+00 INCIDENT LAB ENERGY 4.472423 INT. CROSS SECT.= 2.945E+02 mb LABORATORY SYSTEM 9.918E+00 keV target thickness ANGLE CROSS ENERGY neutrons/(sr*pC) for a 10 SECTION keV neutron energy spread DEGREE mb/sr MeV at 0 D due to energy loss 15.000 4.717E+01 2.7641E+00 3.438E+00 INCIDENT LAB ENERGY 4.373264 INT. CROSS SECT.= 2.815E+02 mb LABORATORY SYSTEM 9.914E+00 keV target thickness ANGLE CROSS ENERGY neutrons/(sr*pC) for a 10 SECTION keV neutron energy spread DEGREE mb/sr MeV at 0 D due to energy loss 15.000 4.427E+01 2.6651E+00 3.167E+00 abs. TOTAL neutron output= 6.645E+02 neutrons per pC b) FOR001.DAT: 0.0000E+002.962128E+00 0.00000E+00 4.67088E+00 0.00E+00 0.00000E+00 0.00000E+00 1.5000E+012.962128E+00 4.12134E+00 4.67088E+00 1.00E-01 2.42554E+02 3.21119E+02 1.5000E+012.863123E+00 3.74616E+00 4.57163E+00 1.00E-01 2.27926E+02 3.07136E+02 1.5000E+012.764119E+00 3.43759E+00 4.47242E+00 1.00E-01 2.14614E+02 2.94481E+02 1.5000E+012.665116E+00 3.16743E+00 4.37326E+00 1.00E-01 2.01400E+02 2.81484E+02 c) P7LI04.SPC: @@@@ 2.6651E+00,3.1991E+08 2.7641E+00,3.4719E+08 2.8631E+00,3.7837E+08 2.9621E+00,4.1627E+08 !: p7li 4.670810 MeV 15.00 deg, beam exits w/ 4.373260 MeV !: Units are: neutrons/MeV/sr/microCoulomb vs. MeV !: High energy group: av. energy= 2.821576, av. dbl. diff. yield= 3.645E+08 !: Average energy of all neutrons= 2.821576, angular diff. yield= 1.083E+08 3.3 TIMREV (Differential cross sections and energies of (n,p), (n,d), (n,t) and (n,4He) reactions) These are calculated by detailed balance from the time reversed reactions. The main menu is shown below together with a sample input. The interactive program is self-explaining, the main menu more or less, too, except for the slash (/) in the X-SECTION RANGE column, which indicates mixed classes of cross sections in the *.KOE table (see 2.2). The output FOR002.DAT contains kinematic information on both the ingoing and the outgoing particles and on the differential LABORATORY cross section of both outgoing particles together with the solid angle factors needed for a conversion into c.m.. 3.3.1 Main Menu and sample terminal responses: Cross sections of (n,p), (n,d), (n,t) and (n,alpha) REACTIONS ID REACTION TYPE REMARKS X-SECTION RANGE [MeV] 1 3He(n,p)3H 0.001 - 31.786 2 3He(n,d)2H REACTION CROSS SECTIONS! 4.38 - 30.945 3 3He(n,t)1H 0.001 - 31.786 4 4He(n,d)3H 22.08 - 52.2 5 4He(n,t)2H 22.08 - 52.2 7 7Be(n,p)7Li 1.07e-5 -21.118 13 10B(n,p0)10Be isotropic approximation 0.001 - 20. 15 10C(n,p)10B isotropic approximation .0626 - 3.692/12.22 16 11C(n,p)11B 0.678 - 2.471 19 13N(n,p)13C 5.462 - 9.622 21 14N(n,p0)14C isotropic approximation 1.44e-6 - 20. 23 15O(n,p0)15N 0.165 - 1.85/11.843 25 36Ar(n,p0)36Cl isotropic approximation 0.7 - 0.733/20. 27 39K(n,p0)39Ar isotropic approximation 1. - 1.075/20. 29 59Ni(n,p)59Co isotropic approximation 3.71e-5 - 20. 33 10B(n,d)9Be isotropic approximation 4.846 - 4.910/20. 34 12C(n,d0)11B isotropic approximation 15.272 - 17.201/20. 36 14N(n,d0)13C isotropic approximation 6. - 20. 38 16O(n,d0)15N isotropic approximation 10.53 - 16.137/20. 40 19F(n,d0)18O isotropic approximation 7. - 8.165/20. 49 6Li(n,t)4He 0.0001- 1.000/20. 51 10B(n,4He0)7Li isotropic approximation 0.0001 - 0.79 53 14N(n,4He0)11B isotropic approximation 0.30 - 2.48 55 16O(n,4He0)13C isotropic approximation 2.40 - 6.44 57 25Mg(n,4He)22Ne isotropic approximation 3.e-5 - 2.141 Enter ID: 1 Uses 2003 mass table REACTION 3He(n,p)3H Incoming NEUTRON energy in MeV or for END: 30. NUMBER of ANGLES, NEGATIVE if C.M., blank for FILE: 3 INPUT of ANGLE values: LINE-BY-LINE or "" for other OPTIONS 0. 90. 180. The CROSS SECTIONS were calculated by using 31.0133866 MeV proj. energy Incoming NEUTRON energy in MeV or for END: Stopped because of BLANK energy INPUT COMMENT: cross section and yield data depend on data base in file: p3hags.koe FORTRAN STOP 3.3.2 Sample output (FOR002.DAT): REACTION 3He(n,p)3H REST MASSES: INCIDENT 939.5653261 CALCULATED Q= 0.7638032 TARGET 2808.3913232 C 938.2719963 D 2808.9208498 INCIDENT LAB ENERGY 30.0000000 INCIDENT LAB MOMENTUM 239.3197 PROJ. ENERGY FOR RECIPR. REACTION: 31.0133866 INTEGR. CROSS SECTION: 50.570351 Center of Mass Parameters: TOTAL ENERGY 3770.3690 BETA(C.M.)0.0633 GAMMA(C.M.) 1.0020 S= 1.421568E+07 PART A:TOT EN 956.3260 MOM 178.2593 PART B:TOT EN 2814.0430 MOM 178.2593 PART C:TOT EN 955.6094 MOM 181.2045 BETA 0.1896 GAM 1.0185 MQ 0.193 PART D:TOT EN 2814.7596 MOM 181.2045 BETA 0.0644 GAM 1.0021 MQ 0.065 PARTICLE C: PARTICLE D: CM LAB KINETIC SOLID labCROSS LAB KINETIC SOLID labCROSS ANGLE ANGLE ENERGY ANGLE SECTION ANGLE ENERGY ANGLE SECTION 0.00 0.00 30.762 0.5596 63.0585 180.00 0.0023889.0769 0.0091 109.52 90.00 15.418 1.0631 1.7629 35.51 15.346 0.3117 6.0131 180.00 180.00 7.759 2.2459 2.1924 0.00 23.005 0.2530 19.4597 References: [1] M. Drosg, O. Schwerer: "Production of Monoenergetic Neutrons Between 0.1 and 23 MeV: Neutron Energies and Cross Sections", in Handbook on Nuclear Activation Data, K. Okamoto, Ed., IAEA Tech. Rep. Ser. 273, Vienna 1987 [2] G. Audi, A.H. Wapstra, and C. Thibault. "The AME2003 atomic mass evaluation (II). Tables, graphs, and references", Nuclear Physics A729, 337 (2003). [3] Fusion Evaluated Data File, FENDL, MAY91, R. M. WHITE & D. A. RESLER, JULICH 91 CONFERENCE [4] J. F. ZIEGLER, ed., "The Stopping and Ranges of Ions in Matter", Vol.3 "HYDROGEN, Stopping Powers and Ranges in All Elements", Vol.5, "Heavy Ions, Stopping Powers and Ranges", Pergamon, 1977, 1980. [5] M. Drosg: "Unified Absolute Cross Sections for the Neutron Production by the Hydrogen Isotopes for Charged Particle Energies Between 6 and 17 MeV", Nucl.Sci.Eng. 67, 190 (1978) Appendices: Appendix 1: List of files: a) Introductory information (4 files): 0-README.TXT IAEANDS.TXT README.TXT b) 6 OPEN-VMS-compatible compiling and linking commands: for VAXes (FORTRAN77) for ALPHAs (FORTRAN90) RECLINK.COM RECLI90.COM WHILINK.COM WHILI90.COM YIELINK.COM YIELI90.COM c) 9 source files: ANGCAL.F90 ANGINP.F90 CHKANG.F90 ENINPO.F90 LEGINT.F90 NEUYIE.F90 The output subroutines for the 3 codes are in one of the following files: NYIOUT.F90 (monoenergetic neutron production) WHIOUT.F90 (white source, i.e. thick target application) RECOUT.F90 (reciprocal reactions) d) 3 parameter files (for INCLUDE statement): PARAM.MON PARAM.REC PARAM.WHI (PARAM.NEU is not included, it is a temporary file only!) e) 3 executables (compiled with either Fortran-90 or Fortran-95) NEUYIE.xxx TIMREV.xxx WHIYIE.xxx f) 3 general data files: SETYIE.TAB General menu for NEUYIE and WHIYIE SETREC.TAB General menu for TIMREV !!!!! ATTENTION: In case that there is no complete display of the main menu remove all " + " symbols from the SET*.TAB files. MASS.TAB Table of nuclear masses and spins g) Cross sections and Legendre coefficients (34 files): A11BGS.KOE A13CGS.KOE A22NEX.KOE A7LIGS.KOE D9BEGS.KOE D11BGS.KOE D13CGS.KOE D14NGS.KOE D15NGS.KOE D18OGS.KOE D20NEX.KOE D24MGX.KOE D28SIX.KOE D2HAGS.KOE D32SGS.KOE D3HAGS.KOE D7LIGS.KOE P10BEX.KOE P10BGS.KOE P11BGS.KOE P12CGS.KOE P13CGS.KOE P14CGS.KOE P15NGS.KOE P18OGS.KOE P36CLX.KOE P39ARX.KOE P3HAGS.KOE P59COX.KOE P6LIGS.KOE P7LIES.KOE P7LIGS.KOE P9BEGS.KOE T4HEGS.KOE h) Energy loss data (50 files): AONH.ELS AONLI.ELS AONB.ELS AONC.ELS AONNE.ELS TONHE.ELS LI7HE.ELS B11HE.ELS C13HE.ELS NE22HE.ELS DONLI.ELS DONLIH.ELS DONB.ELS DONBE.ELS DONC.ELS DONN.ELS DONO.ELS DONNE.ELS DONMG.ELS DONSI.ELS DONS.ELS LI7ONH.ELS B11ONH.ELS C13ONH.ELS N15ONH.ELS NE0ONH.ELS MG4ONH.ELS SI8ONH.ELS S32ONH.ELS PONLI.ELS PONLIF.ELS PONLIH.ELS PONBE.ELS Be0ONH.ELS PONB.ELS PONC.ELS C12ONH.ELS C14ONH.ELS PONN.ELS PONO.ELS PONCL.ELS Cl6ONH.ELS PONAR.ELS AR9ONH.ELS PONCO.ELS CO9ONH.ELS TONH.ELS TONH2O.ELS TONLIH.ELS TOCTAN.ELS Appendix 2: List of papers on neutron sources by the same author: M. DROSG: "Monoenergetic neutron production by two-body reactions in the energy range from 0.0001 to 500 MeV. An overview." TCM-Meeting of IAEA, Debrecen, Hungary, October 1999 M. DROSG: "Monoenergetic neutrons in the energy range from 100 eV to 200 MeV from two-body reactions with the hydrogen nuclei." Proc. 5th International Conf. on Applications of Nucl. Techniques "Neutrons in Research and Industry", Sissi, Crete, June 1996 M. DROSG: "Sources of fast monoenergetic neutrons. More recent developments." Proc. 4th International Conf. on Applications of Nucl. Techniques "Neutrons and their Applications", Sissi, Crete, June 1994. M. DROSG, D.M. DRAKE, J. Mazarik: "Calibration of a Li-glass detector for neutron energies above 50 keV by the 1H(t,n)3He reaction." Nucl. Instr. Meth. Phys. Res. B (1994) M. DROSG, D.M. DRAKE: "Fast neutron yield from 20-MeV tritons on water. Part I. Triton interaction with light water." Nucl. Instr. Meth. Phys. Res. B73, 387(1993) M. DROSG, D.M. DRAKE, R.C. HAIGHT, R.O. NELSON: "Fast neutron yield from 20-MeV tritons on water. Part II. Triton interaction with heavy water." Nucl. Instr. Meth. Phys. Res.B73, 392(1993) M.DROSG, D.M.DRAKE, R.C.HAIGHT, Ron NELSON: "A 'one-step' Method for Measuring Neutron Detector Efficiencies up to 40 MeV", p.135, Report NEANDC-305 "U", NEA, OECD, Paris 1991 M.DROSG: "Some Accurate Neutron Cross Sections in the 4He and 5He Systems above 20 MeV", p.196, Report NEANDC-305 "U", NEA, OECD, Paris 1991 M.DROSG: " On Shibata-san's "Evaluation of Neutron Nuclear Data for 3He and 4He" published in Journal of NUCLEAR SCIENCE and TECHNOLOGY, 27,81(1990)", Nucl. Sci. Techn., 28(4), 70(1991). S. CIERJACKS, Y. HINO, M. DROSG: "Proposal of a High Intensity 14MeV-Cut-Off Neutron Source Based on the 1H(t,n)3He Source Reaction", Nucl. Sci. Eng. 106, 183 (1990) M. Drosg:" Sources of Variable Energy Monoenergetic Neutrons for Fusion Related Applications", Nucl. Sci. Eng. 106, 279 (1990) S. CHIBA, M. MIZUMOTO, K. HASEGAWA, Y. YAMANOUTI, M. SUGIMOTO, Y. WATANABE, and M. DROSG:"The 1H(11B,n)11C Reaction as a Practical Low Background Monoenergetic Neutron Source in the 10 MeV Region", Nucl. Instr. Meth. Phys. Res. A281,581 (1989) M. DROSG: "Angular Dependences of Neutron Energies and Cross Sections for 11 Monoenergetic Neutron Source Reactions", Computer-Code DROSG-87: Neutron Source Reactions (O. Schwerer, ed.) Documentation series, IAEA, Nuclear Data Section, October 1987 M. Drosg, O. Schwerer: "Production of Monoenergetic Neutrons Between 0.1 and 23 MeV: Neutron Energies and Cross Sections", in Handbook on Nuclear Activation Data, K. Okamoto, Ed., IAEA Tech. Rep. Ser. 273, Vienna 1987 M. Drosg: "Novel Monoenergetic Neutron Sources for Energies Between 2.5 and 25.7 MeV", Nucl. Inst. Meth. Phys. Res. A254, 466 (1987) M. Drosg: "Production of Fast Neutrons with Targets of the Hydrogen Isotopes. Source Properties and Evaluation Status of the Cross Sections", p. 239, Report IAEA-TECDOC-410 (1987) (Proc. IAEA Adv. Group Meeting on Neutron Source Properties, Leningrad, June 1986) M. Drosg: "Updating Survey of Some Less Common Fast Neutron Sources: 9Be(p,n)9B, 11B(p,n)11C, 51V(p,n)51Cr and 9Be(4He,n)12C", p. 285, Report IAEA-TECDOC-410 (1987) (Proc. IAEA Adv. Group Meeting on Neutron Source Properties, Leningrad, June 1986) M. Drosg, G. Haouat, W. Stoeffel, D.M. Drake: "Differential Cross Sections of 3H(p,n)3He and of 6Li(n,t)4He by Using Triton Beams Between 5.95 and 19.15 MeV and a Reevaluation of the p-T Neutron Production Cross Sections up to 12 MeV", Report LA10444- MS, LANL (May 1985) M. Drosg: "Proposal for Measuring the Ratio of the Neutron Standards 6Li(n,alpha)3H and 10B(n,alpha)7Li by the Quasiabsolute Method using the Time-Reversed Reactions and the Ratios of these Standards to the 3He(n,p)3H Reaction in the 0.25 to 9 MeV Neutron Energy Range", Report IAEA-TECDOC-335, p.130 (June 1985) (Proc. IAEA Adv. Group Meeting on Nuclear Standard Reference Data, Geel, Nov. 1984) M. Drosg: "Candidates for Fast Neutron Standards Among Neutron Producing Reactions", Report IAEA-TECDOC-335, p.456 (June 1985) (Proc. IAEA Adv. Group Meeting on Nuclear Standard Reference Data, Geel, Nov. 1984) M. Drosg: "Neutron Sources", Proceedings XIth International Symposium on the Interaction of Fast Neutrons with Nuclei, 30. Nov.-4.Dec.1981, Rathen bei Dresden, ZfK-476, p.80, July 1982 M. Drosg: "The 1H(7Li,n)7Be Reaction as a Neutron Source in the MeV Range", Report LA-8842-MS, Los Alamos Scientific Laboratory (LASL) (1981) M. Drosg: "The 2H(d,n)3He Differential Cross Sections for Deuteron Energies between 20 and 40 MeV", Report LA-8538-MS, Los Alamos Scientific Lab. (LASL) (1980) M. Drosg: "Proposal of a Novel High Intense Neutron Source for Radiation Therapy", Z.Physik A 298, 297 (1980) M. Drosg: "Improved Evaluation of the Differential Cross Sections of the 3H(d,n)4He Reaction for Deuteron Energies Between 3 and 7 MeV", LA-8532-MS, LASL (1980) and Z.Physik A 300, 315 (1981) M. Drosg: "Properties of Monoenergetic Neutron Sources from Proton Reaction with Nuclei other than Tritons", p.241 Proc. IAEA Consultants' Meeting on Neutron Source Properties, Debrecen 1980, K. Okamoto, Ed.,Report INDC (NDS)-114/GT (1980) M. Drosg: "Production of Fast Monoenergetic Neutrons by Charged Particle Reactions Among the Hydrogen Isotopes. Source properties, experimental techniques and limitations of the data", p.201, Proceedings IAEA Consultants' Meeting on Neutron Source Properties, Debrecen 1980, K. Okamoto, Ed., Report INDC(NDS)- 114/GT (1980) M. Drosg: "The 3H(p,n)3He Differential Cross Sections Below 5 MeV and the n-3He Cross Sections", LA-8215-MS, LASL (1980) M. Drosg: "Unified Absolute Cross Sections for the Neutron Production by the Hydrogen Isotopes for Charged Particle Energies Between 6 and 17 MeV", Nucl.Sci.Eng. 67, 190 (1978) M. Drosg: "Interaction of Fast Neutrons with 4He, 3He and 1H: Additional and Improved Data", Report LA-7269-MS of Los Alamos Scientific Laboratory, Univ. Calif. (1978) M. Drosg: "On the Energy Dependence of the Total Cross Section of the Reaction 2H(d,n)3He", Nucl.Sci.Eng. 65, 553 (1978) M. Drosg and G.F. Auchampaugh: "Signal-to-Background Ratio for Neutron Production Between 10 and 14 MeV by the Reactions 3H(p,n)3He, 1H(t,n)3He, and 2H(d,n)3He", Nucl.Instr.Meth. 140, 515 (1977) M. Drosg: "Absolute Differential Cross Sections for the Reactions 2H(t,n)4He and 3H(d,n)4He Between 7 and 17 MeV", in Proc. Internat. Conf. on the Interactions of Neutrons with Nuclei, Lowell 1976, p.1384 (CONF-760715-P2) M. Drosg, R.K. Smith and R. Woods: "Absolute Differential Cross Sections over the Entire Angular Range for the Reaction 3H(d,n)4He at 7.0 and 10.0 MeV",-Report LA-6262-MS of LASL (1976) M. Drosg, G.F. Auchampaugh and F. Gurule: "Neutron Background Spectra and Signal-to-Background Ratio for Neutron Production Between 10 MeV and 14 MeV by the Reactions 3H(p,n)3He, 1H(t,n)3He and 2H(d,n)3He", Report LA-6459-MS of LASL (1976) M. Drosg, D.M. Drake: "Absolute Differential Cross Sections for Neutron Production by the 2H(d,n)3He Reaction with Ed from 6 to 17 MeV and by the 3H(p,n)3He Reaction with Ep from 6 to 16 MeV", Report LA-5732-MS of Los Alamos Scientific Laboratory, Univ. Calif., (1974) D.K. McDaniels, M. Drosg, J.C. Hopkins, J.D. Seagrave: "Angular Distributions and Absolute Cross Sections for the T(d,n)4He Neutron Source Reaction", Phys. Rev. C7, 882 (1973) D.K. McDaniels, M. Drosg, J.C. Hopkins, J.D. Seagrave: "Angular Distributions and Absolute Cross Sections for the T(p,n)3He Neutron Source Reaction", Phys. Rev. C6, 1593 (1972) Appendix 3: List of ERROR messages with /explanations/: WARNINGS: ' Input ERROR, repeat input'/ Formal input error/. ' ATTENTION: sqrt of negative value avoided'/ / ' ATTENTION: negative value might be serious'/ / ' PROJ. ENERGY TO GET nnn.nnnn MeV NEUTRONS IS NOT ACCESSIBLE, Below THRESHOLD of: nnn.nnnnn MeV'// ' BELOW THRESHOLD of nnnn.nnnnn MeV'/ Projectile energy is below threshold./ ' Neutron energy below ',engnmin,' MeV encountered'// ' Minimum allowed neutron energy spacing is 0.001 MeV'/Lower limit for WHIYIE is 1 keV./ ' At E= nnn.nnnnn MeV ALL nnn ANGLES OUTSIDE OF THE CONE'/ For endothermic reactions in the double-valued regime./ ' ENERGY OUT OF RANGE OF LEGENDRE TABLE, check validity'/ Definitely NO information on angular distributions at this energy in file *.KOE./ ' INTERPOLATION ERROR: sum of coeff. deviates >=0.1%'/ It is necessary, that the sum of the coefficients deviates not more than 0.001 from 1.0000/. ' SPLINE Interpolation failed!! Neg. cross section of -nnn.nnn at Eproj nnnn.nnnn set to zero!'/Uses zero cross section instead of calculated negative one./ ' ATTENTION: step size was 0., replaced by 0.1 MeV'/ In WHIYIE only; provision to overcome problem when generating differential yield spectra (should never happen!)/ ' Possibility of a GAP! after nn'/In WHIYIE only; detects an energy gap in differential yield spectra. Unavoidable in double-valued data./ ' Possible offset in Ethr of: ',df,' MeV'/ Calculation of threshold energy incomplete. (Should never happen!)/ ' Conversion into projectile energy failed. Possible offset of: ' ,df,' MeV'/ (Should never happen!)/ FATAL ERRORS: ' ERROR in connection with SETUP table'/ ID chosen does not occur in the main menu/. ' STOPPED BECAUSE OF BLANK energy INPUT'/ is the preferred regular exit from the program/. ' STOP: Zero neutron energy (end of data) encountered!'/ No *.SPC output for plotting because only one data point is available./ ' ERROR IN PROJECTILE ENERGY'/' NEUTRON ENERGY LIMITS CANNOT BE CONVERTED INTO PROJECTILE ENERGY VALUES'/. ' ITERATION of reciprocal energy was NOT successful'/ TIMREV cannot find the charged particle energy that matches the neutron energy/. ' No cross section data'/ / ' DESIRED ENERGIES OUTSIDE OF LEGENDRE TABLES'/ Only in option "-2" of NEUYIE, i.e. if a *.KOE table is scanned/. ' EMINL - EMAXL mess up'/ Indicates an error in the first line of the *.KOE table/. ' >=5% Interpolation ERROR of Legendre coefficients!'/ If the sum of the coefficients deviates more than 0.05 from 1.0000. NEUYIE and TIMREV stop conditionally. WHIYIE gives the ERROR message and terminates the energy chain. ' Yield and cross section values are meaningless!!'/ If sum of Legendre coefficients deviates by more than 5 %; see above./ ' STOP in subroutine LEGINT, file LEGINT.F90'/ Error in SPLINE interpolation vector/. ' NOT ENOUGH DATA FOR SPLINE'/ / ' STOP: bad cross section input for ',en,' MeV'/ Error in SPLINE: two data points are equal/ ' RETURN: ANGLE mismatch!!'/In WHIYIE only; error in FOR001.DAT from which the white spectrum *.SPC for plotting is prepared/. ' Consecutive neutron energies are equal!!!'/ In WHIYIE only; error in FOR001.DAT from which the white spectrum *.SPC for plotting is prepared/. Appendix 4: Disclaimer: Previous versions of these programs have been distributed under the acronyms DROSG-87 and DROSG-96 by the IAEA since 1987. The codes DROSG-2000 were written by M. DROSG INST. F. EXP. PHYSICS UNIVERSITY OF VIENNA Boltzmanngasse 5 A-1090 WIEN AUSTRIA / Europe for his personal use. Neither the author nor anybody else makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of this program and of results obtained by it, or represents that its use would not infringe privately owned rights. The author will appreciate any comment that will allow to improve this program: E-mail "Manfred.Drosg@UNIVIE.AC.AT" Vienna, 2005-05-11