Show simple item record

dc.contributor.authorMoreno Palacios, Pablo
dc.contributor.authorChiu, Chong
dc.date.accessioned2005-09-21T19:47:48Z
dc.date.available2005-09-21T19:47:48Z
dc.date.issued1976
dc.identifier.other22332153
dc.identifier.urihttp://hdl.handle.net/1721.1/27521
dc.description.abstractA one-pass simplified analysis method for steady state PWR core has been developed. The advantages over the other multistage approaches have been discussed and compared- Recommended nodal patterns for modelling the reactor core have been proposed. Also the effect due to the lumped channel technique utilized in both the simplified method and existing multistage methods has been investigated for both D and 3D problems. For the nodal pattern recommended with the proposed one-pass analysis method, use of the lumped channel technique introduces negligible errors.en
dc.description.sponsorshipNew England Electric System, Northeast Utilities Service Co. under the MIT Energy Laboratory Electric Power Programen
dc.format.extent13285840 bytes
dc.format.mimetypeapplication/pdf
dc.language.isoen_USen
dc.publisherMIT Energy Laben
dc.relation.ispartofseriesMIT-ELen
dc.relation.ispartofseries76-006en
dc.titleMethods for steady state thermal-hydraulic analysis of pressurized water reactor coresen
dc.typeTechnical Reporten


Files in this item

Thumbnail
Thumbnail
Thumbnail
Thumbnail

This item appears in the following Collection(s)

Show simple item record