last modified: 01-APR-1979 | catalog | categories | new | search |

NEA-0520 SARAZE-2/ROBE.

SARAZE-2, Energy Release from Reactivity Transient Fast Reactor Accident

top ]
1. NAME OR DESIGNATION OF PROGRAM:  SARAZE-2/ROBE.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
SARAZE-2/ROBE NEA-0520/01 Tested 01-APR-1979

Machines used:

Package ID Orig. computer Test computer
NEA-0520/01 IBM 360 series IBM 360 series
top ]
3. NATURE OF PHYSICAL PROBLEM SOLVED

SARAZE-2 calculates the energy release in a hypothetical accident to a fast reactor, assuming one-dimensional spherical geometry, following a constant input of reactivity. Reactivity feedback comes from the Doppler effect and the core disassembly. Allowance may be taken for compressible or incompressible sodium in the core breeder. ROBE is a test program for the equation of state used by SARAZE-2.
top ]
4. METHOD OF SOLUTION

Finite difference equations are solved using Lagrangian mesh to calculate the movement of the core and breeder materials. The point kinetics equation is integrated numerically to  find the neutron and energy densities as functions of radius and time.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Maximum 200 Lagrangian meshes.
top ]
6. TYPICAL RUNNING TIME:  A few minutes for 40 meshes.
top ]
7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
top ]
8. RELATED AND AUXILIARY PROGRAMS:  SARAZE-1: A Bethe-Tait program with  similar geometry.
top ]
9. STATUS
Package ID Status date Status
NEA-0520/01 01-APR-1979 Tested at NEADB
top ]
10. REFERENCES

- D.J. Mather:
  'SARAZE-2, A Computer Program to Calculate the Energy Release in Fast Reactor Transients'
  SRD Report 58,UKAEA.
- D. Roberts:
  'A Variable Equation of State for Use in Fast Reactor Safety Problems'
  SRD Report 20,UKAEA.
top ]
11. MACHINE REQUIREMENTS:  150k bytes of core memory, one work file on tape or disc.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0520/01 FORTRAN-IV
top ]
13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  RIOS
and VME/B.
top ]
14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Intended developments: calculation of the effects of structural strength and of heat transfer from the fuel to structure and/or sodium.
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

       D.J. Mather
       SRD, UKAEA
       Warrington, United Kingdom
top ]
16. MATERIAL AVAILABLE
NEA-0520/01
File name File description Records
NEA0520_01.001 INFORMATION 19
NEA0520_01.002 SARAZE -- SOURCE PROGRAM (F4,EBCDIC) 1902
NEA0520_01.003 SARAZE -- SUBROUTINES (F4,EBCDIC) 330
NEA0520_01.004 SARAZE -- SAMPLE PROB. INPUT DATA 17
NEA0520_01.005 SARAZE -- SAMPLE PROB. PRINTED OUTPUT 683
NEA0520_01.006 SARAZE -- JCL 24
NEA0520_01.007 ROBE -- SOURCE PROGRAM (F4,EBCDIC) 678
NEA0520_01.008 ROBE -- SUBROUTINES (F4,EBCDIC) 194
NEA0520_01.009 ROBE -- SAMPLE PROB. PRINTED OUTPUT 2430
top ]
17. CATEGORIES
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics

Keywords: Doppler coefficient, Lagrange equations, energy transfer, fast reactors, one-dimensional, reactor cores, reactor kinetics, sodium, spheres, transients.