NEA-0446: DELIGHT-7, Point Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation

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NEA-0446 DELIGHT-7. (Abstract last modified 01-JUL-2003)

DELIGHT-7, Point Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION OF PROGRAM - DELIGHT-7.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name Package-ID Status DELIGHT-2 NEA-0446/01 Obsolete DELIGHT-6 NEA-0446/02 Obsolete DELIGHT-7 NEA-0446/03 Tested

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.

3. NATURE OF PHYSICAL PROBLEM SOLVED - The program performs multi-group neutron spectrum calculations and provides the few-group constants for burnup calculations of a high-temperature gas-cooled reactor core, where the coated particle fuel elements cause double heterogeneity.

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.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -
Maximum number of:
- nuclides - 50
- fast and thermal groups for criticality/burnup calculations - 25
- neutron spectrum recalculations, burnup steps - 50.

6. TYPICAL RUNNING TIME - The sample problem takes a few tens of seconds to execute.

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.

NEA-0446/03:

UNUSUAL FEATURES - The temperature of scattering kernel of graphites can be designated every 20K between 300K and 1800K.

8. RELATED AND AUXILIARY PROGRAMS -

9. STATUS
NEA-0446/01: 07-DEC-1983 Obsolete
NEA-0446/02: 22-OCT-2002 Obsolete
NEA-0446/03: 01-JUL-2003 Tested at NEADB

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).
NEA-0446/03:
- 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)

11. MACHINE REQUIREMENTS -

12. PROGRAMMING LANGUAGE(S) USED -
NEA-0446/03: FORTRAN-77

13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED -

14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHOR -
          Japan Atomic Energy Research Institute
          Tokai-mura, Naka-gun, Ibaraki-ken
          JAPAN

16. MATERIAL AVAILABLE -
NEA-0446/03:
burn1.dat  burn-up data library
react.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

17. CATEGORIES -

- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: BURNUP, CRITICALITY, FEW-GROUP, HTGR REACTORS, NEUTRON SPECTRA, REACTIVITY, REACTOR LATTICES

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