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dc.contributor.authorGuillebaud, Louis Jean Marie.
dc.contributor.authorLevine, A.
dc.contributor.authorBoyd, W.
dc.contributor.authorFaya, A.
dc.contributor.authorWolf, Lothar
dc.date.accessioned2006-03-13T15:57:58Z
dc.date.available2006-03-13T15:57:58Z
dc.date.issued1977-07
dc.identifier.other05699880
dc.identifier.urihttp://hdl.handle.net/1721.1/31321
dc.descriptionWOSUB (Computer program).en
dc.description.abstractThe 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.en
dc.description.sponsorshipopical report for Task 3 of the Nuclear Power Reactor Safety Research Program sponsored by New England Electric System, Northeast Utilities Service Co. under the M.I.T. Energy Laboratory Electric Power Program.en
dc.format.extent10033375 bytes
dc.format.mimetypeapplication/pdf
dc.language.isoen_USen
dc.publisherMIT Energy Laboratoryen
dc.relation.ispartofseriesMIT-ELen
dc.relation.ispartofseries78-024en
dc.subjectNuclear fuel elements |x Computer programs.en
dc.subjectBoiling water reactors.en
dc.titleWOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. Volume II. User's Manualen
dc.typeTechnical Reporten


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