WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles.
The WOSUB-codes are spin-offs and extensions of the MATTEO-code [1]. The series of three reports describe WOSUB-I and WOSUB-II in their respective status as of July 31, 1977. This report is the first in a series of three, the second of which contains the user's manual [2] and the third...
| Main Authors: | , , |
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| Format: | Technical Report |
| Language: | en_US |
| Published: |
Massachusetts Institute of Technology. Energy Laboratory
2006
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| Subjects: | |
| Online Access: | http://hdl.handle.net/1721.1/31319 |
| _version_ | 1826217512424964096 |
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| author | Wolf, Lothar Guillebaud, Louis Jean Marie Faya, A. |
| author_facet | Wolf, Lothar Guillebaud, Louis Jean Marie Faya, A. |
| author_sort | Wolf, Lothar |
| collection | MIT |
| description | The WOSUB-codes are spin-offs and extensions of the
MATTEO-code [1]. The series of three reports describe WOSUB-I
and WOSUB-II in their respective status as of July 31, 1977.
This report is the first in a series of three, the
second of which contains the user's manual [2] and the third
[3] summarizes the assessment and comparison with experimental
data and various other subchannel codes.
The present report introduces the drift-flux and vapor
diffusion models employed by the code, discusses the solution
method and reviews the constitutive equations presently built
into the code. Wherever applicable, possible exteriors of the
models are indicated especially with due regard of the findings
presented in [3].
Overall, the review of the model and the package of
constitutive equations demonstrate that WOSUB-I and II
constitute true alternatives for BWR bundle and PWR test bundle
calculations as compared to the commonly applied COBRA-IIIC,
and COBRA-IIIC/MIT codes which were primarily designed for PWR
subchannel and core calculations, respectively. In fact, the
incorporation of the drift flux and the vapor diffusion pro-
cesses into a subchannel code has to be cdnsidered.a major step
towards a more basic understanding and a well balanced engineer-
ing approach without the extra burden of a true two-fluid two-
phase model.
Recommendations for improvements in the various areas
are indicated and should serve as guidelines for future develop-
ment of this code which in light of the encouraging results pre-
sented in [3] seems to be highly warranted.
The WOSUB-code is still in the stage of evolutionary
development. In this context, the review reflects the achieve-
ments as of July 1977. |
| first_indexed | 2024-09-23T17:04:47Z |
| format | Technical Report |
| id | mit-1721.1/31319 |
| institution | Massachusetts Institute of Technology |
| language | en_US |
| last_indexed | 2024-09-23T17:04:47Z |
| publishDate | 2006 |
| publisher | Massachusetts Institute of Technology. Energy Laboratory |
| record_format | dspace |
| spelling | mit-1721.1/313192019-04-12T08:25:49Z WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. Wolf, Lothar Guillebaud, Louis Jean Marie Faya, A. Boiling water reactors. Nuclear fuel elements |x Computer programs. The WOSUB-codes are spin-offs and extensions of the MATTEO-code [1]. The series of three reports describe WOSUB-I and WOSUB-II in their respective status as of July 31, 1977. This report is the first in a series of three, the second of which contains the user's manual [2] and the third [3] summarizes the assessment and comparison with experimental data and various other subchannel codes. The present report introduces the drift-flux and vapor diffusion models employed by the code, discusses the solution method and reviews the constitutive equations presently built into the code. Wherever applicable, possible exteriors of the models are indicated especially with due regard of the findings presented in [3]. Overall, the review of the model and the package of constitutive equations demonstrate that WOSUB-I and II constitute true alternatives for BWR bundle and PWR test bundle calculations as compared to the commonly applied COBRA-IIIC, and COBRA-IIIC/MIT codes which were primarily designed for PWR subchannel and core calculations, respectively. In fact, the incorporation of the drift flux and the vapor diffusion pro- cesses into a subchannel code has to be cdnsidered.a major step towards a more basic understanding and a well balanced engineer- ing approach without the extra burden of a true two-fluid two- phase model. Recommendations for improvements in the various areas are indicated and should serve as guidelines for future develop- ment of this code which in light of the encouraging results pre- sented in [3] seems to be highly warranted. The WOSUB-code is still in the stage of evolutionary development. In this context, the review reflects the achieve- ments as of July 1977. Topical 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. 2006-03-13T15:57:27Z 2006-03-13T15:57:27Z 1978-09 Technical Report 05699880 http://hdl.handle.net/1721.1/31319 en_US MIT-EL 78-023 7735220 bytes application/pdf application/pdf Massachusetts Institute of Technology. Energy Laboratory |
| spellingShingle | Boiling water reactors. Nuclear fuel elements |x Computer programs. Wolf, Lothar Guillebaud, Louis Jean Marie Faya, A. WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. |
| title | WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. |
| title_full | WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. |
| title_fullStr | WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. |
| title_full_unstemmed | WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. |
| title_short | WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. |
| title_sort | wosub a subchannel code for steady state and transient thermal hydraulic analysis of bwr fuel pin bundles |
| topic | Boiling water reactors. Nuclear fuel elements |x Computer programs. |
| url | http://hdl.handle.net/1721.1/31319 |
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