NEA-0520 SARAZE-2/ROBE.

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

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

[ 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.