NEA-0446 DELIGHT-7.
DELIGHT-7, Point Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, AUXILIARIES, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| DELIGHT-7 | NEA-0446/03 | Tested | 01-JUL-2003 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0446/03 | IBM PC | PC Pentium III,PC Windows,Linux-based PC,DEC ALPHA W.S. |
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4. METHOD OF SOLUTION
The fast neutron energy range is from 10 MeV down to 2.38 eV with 61 fine groups. P1 and B1 approximations are available. The thermal spectrum from 2.38 to 0 eV is evaluated by P1 or P0 approximation in 50 fine groups. For the resonance calculation the IR method is used, taking into account the double heterogeneity in the fuel lattice. For the fuel lattice geometry zero and one dimensional models are available, which are used for criticality and burnup calculations. In the one dimensional model, the collision probability method is employed. The burnup chains of Th-U and U-Pu systems are included.
The fast neutron energy range is from 10 MeV down to 2.38 eV with 61 fine groups. P1 and B1 approximations are available. The thermal spectrum from 2.38 to 0 eV is evaluated by P1 or P0 approximation in 50 fine groups. For the resonance calculation the IR method is used, taking into account the double heterogeneity in the fuel lattice. For the fuel lattice geometry zero and one dimensional models are available, which are used for criticality and burnup calculations. In the one dimensional model, the collision probability method is employed. The burnup chains of Th-U and U-Pu systems are included.
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7. UNUSUAL FEATURES OF THE PROGRAM
- Shielding factor of burnable poison is evaluated by the collision probability method which enables to treat the double heterogeneity in the poison rod containing many poison grains.
- The cross section library is compiled from ENDF/B-4 except burn-up data of Xm, Sm and pseudo FPs, which are from ENDF/B-3. The chemical binding effect of graphite is taken into account in the thermal scattering cross section.
- The code provides the macroscopic group constants of fuel lattice with burn-up in CITATION input format.
- The spherical fuel cell can be handled as well, for the core design of pebble bed type high temperature gas-cooled reactors.
- Shielding factor of burnable poison is evaluated by the collision probability method which enables to treat the double heterogeneity in the poison rod containing many poison grains.
- The cross section library is compiled from ENDF/B-4 except burn-up data of Xm, Sm and pseudo FPs, which are from ENDF/B-3. The chemical binding effect of graphite is taken into account in the thermal scattering cross section.
- The code provides the macroscopic group constants of fuel lattice with burn-up in CITATION input format.
- The spherical fuel cell can be handled as well, for the core design of pebble bed type high temperature gas-cooled reactors.
NEA-0446/03
The temperature of scattering kernel of graphites can be designated every 20K between 300K and 1800K.[ top ]
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10. REFERENCES
- R. Shindo, M. Hirano, K. Minami:
"Point Reactivity Burnup Code DELIGHT-4 for High Temperature, Gas-Cooled Reactor Cells"
JAERI-M 8097 (1979) (in Japanese).
- R. Shindo, M. Hirano:
"DELIGHT-2, The Point Reactivity Burnup Code for High Temperature, Gas-Cooled Reactor Cells"
JAERI-M 5661 (1974) (in Japanese).
- R. Shindo, M. Hirano, T. Aruga:
"DELIGHT, The Point Reactivity Burnup Code for HTGR Lattices"
JAERI-M 4449 (1971) (in Japanese).
- T. Kurashige, M. Hirano, R. Shindo:
"JIMCOF, A Multigroup Constants File from ENDF.B-IV"
JAERI-M 6972 (1977) (in Japanese).
- R. Shindo, M. Hirano, K. Minami:
"Point Reactivity Burnup Code DELIGHT-4 for High Temperature, Gas-Cooled Reactor Cells"
JAERI-M 8097 (1979) (in Japanese).
- R. Shindo, M. Hirano:
"DELIGHT-2, The Point Reactivity Burnup Code for High Temperature, Gas-Cooled Reactor Cells"
JAERI-M 5661 (1974) (in Japanese).
- R. Shindo, M. Hirano, T. Aruga:
"DELIGHT, The Point Reactivity Burnup Code for HTGR Lattices"
JAERI-M 4449 (1971) (in Japanese).
- T. Kurashige, M. Hirano, R. Shindo:
"JIMCOF, A Multigroup Constants File from ENDF.B-IV"
JAERI-M 6972 (1977) (in Japanese).
NEA-0446/03, included references:
- R. Shindo, K. Yamashita and I. Murata:DELIGHT-7: One Dimensional Fuel Cell Burnup Analysis Code for High
Temperature Gas-cooled Reactors (HGTR)
JAERI-M 90-048 (February 1990) (In Japanese) (input description in English)
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NEA-0446/03
burn1.dat burn-up data libraryreact.dat reaction rate data library
trml51.dat thermal neutron range library
graphk.dat graphite kernel, incoherent library
fast51.dat fast neutron range library
gratobin.f To make graphk library --- FORTRAN source
graphk.sh To make graphk library --- Shell script
graphkebc.dat To make graphk library --- Input data
gamtolib.f To make fast51 library --- FORTRAN source
gamtolib.sh To make fast51 library --- Shell script
gam.dat To make fast51 library --- Input data
delight7v2002.f DELIGHT-7 ... FORTRAN source-1
PARAM DELIGHT-7 ... FORTRAN source-2
delight7.bat DELIGHT-7 ... batch file
f6325f030m030.inp DELIGHT-7 ... Sample input
f6325f030m030.out DELIGHT-7 ... Print-out of sample case
JW256_DELIGHT-7.pdf JAERI-M 90-048 Electronic Documentation
abstract(delight-7)2.doc Abstract
Keywords: HTGR reactors, burnup, criticality, few-group, neutron spectra, reactivity, reactor lattices.