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[Program Service | Recent programs]

NEA-0321 ANDROMEDA. (Abstract last modified 01-DEC-1971)


ANDROMEDA, 1-D Burnup for Fuel Cycle Analysis of FBR

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Abstract Table of Contents:

NAME | COMPUTER | PROBLEM | SOLUTION | RESTRICTIONS | CPU | FEATURES | AUXILIARIES | STATUS | REFERENCES | REQUIREMENTS | LANGUAGE | OPERATING SYSTEM | OTHER RESTRICTIONS | AUTHOR | MATERIAL | CATEGORIES |

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1. NAME OR DESIGNATION OF PROGRAM - ANDROMEDA.


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
ANDROMEDA            NEA-0321/01 Tested

Machines used:
Package-ID     Orig.Computer                       Test Computer
NEA-0321/01    IBM 360 series                      IBM 360 series

3. NATURE OF PHYSICAL PROBLEM SOLVED - ANDROMEDA is a one-dimensional multigroup diffusion-burnup code for use with fast reactors. The code is designed primarily for preliminary fuel-cycle analysis of fast breeder reactors by performing the following items:
a) Regular flux calculation.
b) Adjoint flux calculation.
c) Material buckling calculation.
d) Kinetic parameter calculation.
e) Searches on material (fuel or poison) concentration or region    dimensions.
f) Collapsing the multigroup cross sections into several group cross sections, and punching them on cards, if desired.
All of the items above mentioned except A can be performed at any time during burnup history according to input options. Geometries to deal with are cylinder, slab and sphere. The time interval for burnup calculation is given by input, and for each time interval, reaction rate and mass changes of each isotope, and breeding ratio, burnups in atom percent and power peaking factors in each region are computed. The multigroup cross section library for ANDROMEDA is prepared by LTANDRO, which is able to compose three cross section sets, i.e., JAERI-Fast-Set, ABBN-Set and RCBN Set, on one magnetic tape. It depends on user's choice which cross section set will be used.


4. METHOD OF SOLUTION - Eigenvalues are computed by ordinary source- iteration techniques with ordinary acceleration methods for convergence. But when burnup calculation is required, the flux obtained at the previous burnup step is used for the next burnup step as its initial flux guess in order to accelerate convergence.
Burnup calculation is performed using region-integrated multigroup flux and region-averaged multigroup cross sections, which is renewed every time step taking account of changes in self-shielding factors of each region.


5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -


6. TYPICAL RUNNING TIME - A burnup calculation in cylindrical geometry with 25 groups, 13 regions, 78 mesh points and 6 burnup steps requires about 190 sec running time on the CDC 6600.


7. UNUSUAL FEATURES OF THE PROGRAM -


8. RELATED AND AUXILIARY PROGRAMS - LTANDRO, for ANDROMEDA. Cross sections must be input via tape which is prepared by LTANDRO.


9. STATUS
NEA-0321/01: 01-DEC-1971 Tested at NEADB


10. REFERENCES  - 
- T. Suzuki:
  EXPANDA-4, The One-Dimensional Diffusion Equation Code for Fast
  Reactors Using the JAERI-Fast-Set
  JAERI-Memo 3660 (1969).
- H. Nishimura:
  Reactor Constants for JFER (RCBN Set), Evaluation of the Nuclear
  Characteristics of Japan Experimental Fast Reactor (JFER)
  JAERI-Memo 4214, Japan Atomic Energy Research Institute (1970).
NEA-0321/01:
- K. Ikawa:
  ANDROMEDA, A One-Dimensional Diffusion-Burnup Code
  JAERI-M 4808 (May 1972).


11. MACHINE REQUIREMENTS - A 75 k memory, two storage devices (disks), and two magnetic-tape units, one of which is for the cross section library and the other for the programme.


12. PROGRAMMING LANGUAGE(S) USED -
NEA-0321/01: FORTRAN-IV 


13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED - The programme is constructed, either within the SCOPE 3.3 operating system of the CDC 6600 or within the monitor system of the FACOM 230.


14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -


15. NAME AND ESTABLISHMENT OF AUTHOR -
             Koji Ikawa
             JAERI
             Tokai-mura, Naka-gun
             Ibaraki-ken,mJapan.


16. MATERIAL AVAILABLE -
NEA-0321/01:
NEA0321_01.001    INFORMATION                                        11 records
NEA0321_01.002    LTANDRO SOURCE+DD CARDS+INPUT DATA                202 records
NEA0321_01.003    ANDROMEDA SOURCE PROGRAMME                       3277 records
NEA0321_01.004    ANDROMEDA OVERLAY,DD CARDS+INPUT DATA              53 records
NEA0321_01.005    ANDROMEDA PUNCHED OUTPUT                          144 records
NEA0321_01.006    AUXILIARY DATA LIBRARY(U236,PU242)                364 records
NEA0321_01.007    ANDROMEDA PRINTED OUTPUT                         5149 records


17. CATEGORIES  - 

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


Keywords: BUCKLING, BURNUP, CROSS SECTIONS, CYLINDERS, DIFFUSION, FAST REACTORS, FUEL CYCLE, ITERATIVE METHODS, KINETICS, MULTIGROUP, NEUTRON FLUX, ONE-DIMENSIONAL, REACTION KINETICS, SLABS, SPHERES

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