NEA-0321 ANDROMEDA.
ANDROMEDA, 1-D Burnup for Fuel Cycle Analysis of FBR
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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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.
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.
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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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).
- 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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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 |
Keywords: buckling, burnup, cross sections, cylinders, diffusion, fast reactors, fuel cycle, iterative methods, kinetics, multigroup, neutron flux, one-dimensional, reaction kinetics, slabs, spheres.