last modified: 01-SEP-1980 | catalog | categories | new | search |

NEA-0624 JOSHUA.

JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR

top ]
1. NAME OR DESIGNATION OF PROGRAM:  JOSHUA.
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
JOSHUA NEA-0624/01 Tested 01-SEP-1980

Machines used:

Package ID Orig. computer Test computer
NEA-0624/01 IBM 3033 IBM 3033
top ]
3. DESCRIPTION OF PROBLEM OR FUNCTION

JOSHUA simulates the neutronics, hydraulics, burnup and refuelling of water-cooled reactors in two or three dimensions. It is a whole-reactor code which uses cell-averaged data calculated in a lattice cell calculation such as used by WIMS. JOSHUA evaluates the overall power distribution through the reactor, and integral properties such as reactivity.
top ]
4. METHOD OF SOLUTION

The neutronics calculation, based on the program BASHAN, uses diffusion theory with an in-channel mesh point  respresentation in Cartesian x-y-z geometry. The hydraulics calculation for void feedback is general enough to deal with pressure tube and pressure vessel reactors. An iterative procedure between the flux solution and the hydraulics calculation ensures consistency between the rating and density distributions. Optional features include soluble poison and the reactivity feedback effects  of xenon poisoning and fuel temperature as well as control rod or interlattice tube representation.

The approach followed in modelling the burnup process is to integrate the equations describing isotopic change within the framework of the lattice cell calculation.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  JOSHUA is limited to two energy groups.
top ]
6. TYPICAL RUNNING TIME:
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS

WIMS supplies the data such as the  macroscopic cross sections. The FACADE system may be used to transfer data from WIMS to JOSHUA. The flux solution is based on that used in the code BASHAN.
top ]
9. STATUS
Package ID Status date Status
NEA-0624/01 01-SEP-1980 Tested at NEADB
top ]
10. REFERENCES

- D.F. Pearce:
  JOSHUA III - A Three-Dimensional Diffusion Code with Thermal
  Hydraulic Feedback for Fuel Management Studies in Water Cooled
  Reactors
  AEEW-R788 (1973).
NEA-0624/01, included references:
- M. J. Roth:
  A Review of the Equations Solved by the Computer Program JOSHUA
  AEEW-R 1165 (April 1978)
- M. J. Roth, Mrs. M. A. Thompson:
  The FACADE Version of JOSHUA
  AEEW-R 1186 (July 1978)
top ]
11. MACHINE REQUIREMENTS:
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0624/01 FORTRAN+ASSEMBLER
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

          D. F. Pearce
          AEE Winfrith
          Dorchester, Dorset
          United Kingdom.
top ]
16. MATERIAL AVAILABLE
NEA-0624/01
File name File description Records
NEA0624_01.001 INFORMATION 14
NEA0624_01.002 ASSEMBLER SOURCE 1568
NEA0624_01.003 FORTRAN SOURCE 10924
NEA0624_01.004 OVERLAY CARDS 22
NEA0624_01.005 JCL 92
NEA0624_01.006 INPUT FILE FOR TEST CASE 17
NEA0624_01.007 INPUT CARDS FOR TEST CASE 47
NEA0624_01.008 OUTPUT OF TEST CASE 1815
NEA0624_01.009 DATA LIBRARY (BINARY) 45
top ]
17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • H. Heat Transfer and Fluid Flow
  • K. Reactor Systems Analysis

Keywords: feedback, fuel management, hydraulics, iterative methods, neutron diffusion equation, power distribution, pressure vessels, reactivity, simulation, three-dimensional, two-dimensional, water cooled reactors, x-y-z.