WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. Volume II. User's Manual
Name
MIT-EL-78-024-05699880.pdf
Size
9.57 MB
Format
Adobe PDF
Checksum (MD5)
1c98fb1fc28f2e223cb375762c8d5451
Author(s)
Guillebaud, Louis Jean Marie.
Levine, A.
Boyd, W.
Faya, A.
Wolf, Lothar
Date Issued
July 1977
Publisher
MIT Energy Laboratory
Series/Report no.
MIT-EL
78-024
Abstract
The WOSUB-codes are spin-offs and extensions of the MATTEO-
code [ 2 ]. The series of reports describe WOSUB-I
and WOSUB-II in their respective status as of July 31, 1977.
This report is the second of a series of three reports
describing the WOSUB code. It gives a detailed description of
the input data, flow charts, and output, and contains the list-
ings of WOSUB-I and WOSUB-II. For the purpose of future ex-
tensions parameters, common blocks and variables used in the
code are listed in full detail.
WOSUB-I and WOSUB-II are subchannel computer codes for the
steady-state and transient analysis of the thermal-hydraulic
characteristics of Boiling Water Reactor (BWR) fuel rod bundles.
Both codes are also applicable'to analyze PR bundles, especially
when these are ducted--a situation which most often arises in
experimental set-ups.
The main difference between WOSUB-I and WOSUB-II is that
the former is designed to analyze small bundles, whereas the
latter is capable to handle symmetric sections of today's large-
sized BWR bundles. In addition, WOSUB-II does not contain all
of the additions made in WOSUB-I yet, because it is deemed
appropriate to introduce these into the smaller code first,
before they are implemented into the bigger one.
Both codes are still in the stage of evolutionary develop-
ment. Thus, changes are to be expected in the near future. There-
fore, it should be noticed that this report reflects the develop-
ment as of July 1977 only.
Description
WOSUB (Computer program).
Subjects
Nuclear fuel elements |x Computer programs.
Boiling water reactors.
Persistent DSpace Link
