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NEA-0321 ANDROMEDA.

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

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1. NAME OR DESIGNATION OF PROGRAM:  ANDROMEDA.
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2. COMPUTERS
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Program name Package id Status Status date
ANDROMEDA NEA-0321/01 Tested 01-DEC-1971

Machines used:

Package ID Orig. computer Test computer
NEA-0321/01 IBM 360 series IBM 360 series
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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.
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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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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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.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS

LTANDRO, for ANDROMEDA. Cross sections must be input via tape which is prepared by LTANDRO.
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9. STATUS
Package ID Status date Status
NEA-0321/01 01-DEC-1971 Tested at NEADB
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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, included references:
- K. Ikawa:
  ANDROMEDA, A One-Dimensional Diffusion-Burnup Code
  JAERI-M 4808 (May 1972).
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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.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0321/01 FORTRAN-IV
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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.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

             Koji Ikawa
             JAERI
             Tokai-mura, Naka-gun
             Ibaraki-ken,mJapan.
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16. MATERIAL AVAILABLE
NEA-0321/01
File name File description Records
NEA0321_01.001 INFORMATION 11
NEA0321_01.002 LTANDRO SOURCE+DD CARDS+INPUT DATA 202
NEA0321_01.003 ANDROMEDA SOURCE PROGRAMME 3277
NEA0321_01.004 ANDROMEDA OVERLAY,DD CARDS+INPUT DATA 53
NEA0321_01.005 ANDROMEDA PUNCHED OUTPUT 144
NEA0321_01.006 AUXILIARY DATA LIBRARY(U236,PU242) 364
NEA0321_01.007 ANDROMEDA PRINTED OUTPUT 5149
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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.