A computer program for three-dimensional nuclear and thermal-hydraulic analysis of BWR core: STEADY-ACE
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
A FORTRAN computer program named as STEADY-ACE has been developed to predict the three-dimensional distributions of neutron flux, power and void fraction in a BWR core. The program consists of two subprograms, i.e., the few-group three-dimensional diffusion subprogram DIFFUSION-ACE and the thermal-hydraulic subprogram HYDRO-ACE. The two subprograms are combined in an iterative way so that the interdependency of the power distribution and the void fraction distribution can be treated consistently. The program STEADY-ACE provides a prediction of BWR core performance in a good accuracy in a reasonably short computation time. The computation time of the example case of JPDR quarter core (72/4 assemblies) is 7 CPU minutes on the machine FACOM 230-75. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
11571912.pdf
Files
(1.5 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:ceff3d10faa0c74dcac4b038fced38ae
|
1.5 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 45 p.
- Report number
- JAERI--1264
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 11571912
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BWR TYPE REACTORS; HYDRODYNAMICS; ITERATIVE METHODS; MANUALS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; POWER DISTRIBUTION; REACTOR CORES; S CODES; THERMODYNAMICS; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- COMPUTER CODES; DOCUMENT TYPES; FLUID FLOW; FLUID MECHANICS; MECHANICS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS