JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR
NAME OR DESIGNATION OF PROGRAM
, DESCRIPTION OF PROBLEM OR FUNCTION
, METHOD OF SOLUTION
, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
, TYPICAL RUNNING TIME
, UNUSUAL FEATURES OF THE PROGRAM
, RELATED AND AUXILIARY PROGRAMS
, MACHINE REQUIREMENTS
, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED
, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
, NAME AND ESTABLISHMENT OF AUTHOR
1. NAME OR DESIGNATION OF PROGRAM
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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.
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.
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
: JOSHUA is limited to two energy groups.
7. UNUSUAL FEATURES OF THE PROGRAM
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.
||Tested at NEADB
- D.F. Pearce:
JOSHUA III - A Three-Dimensional Diffusion Code with Thermal
Hydraulic Feedback for Fuel Management Studies in Water Cooled
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)
11. MACHINE REQUIREMENTS
12. PROGRAMMING LANGUAGE(S) USED
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
15. NAME AND ESTABLISHMENT OF AUTHOR
D. F. Pearce
||INPUT FILE FOR TEST CASE
||INPUT CARDS FOR TEST CASE
||OUTPUT OF TEST CASE
||DATA LIBRARY (BINARY)
- 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.