Persistent Link:
http://hdl.handle.net/10150/291445
Title:
Benchmarking TWODANT using the French CRAC experiments
Author:
Bettan, Yehoshua Michael, 1959-
Issue Date:
1993
Publisher:
The University of Arizona.
Rights:
Copyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.
Abstract:
Critical calculations of unreflected cylinders filled with fissile solution were performed using the TWODANT code with the 118-isotope, 16-group Hansen-Roach neutron cross-section library. The benchmark experiments used were the France CRAC experiments. In these experiments unreflected 300mm and 800mm cylinders were used to contain the solution. The fissile solution was highly enriched (approximately 93%) uranyl nitrate solution of various concentrations. These concentrations varied from 21.4 g/l to 383 g/l in total uranium. The calculational results were compared to the experimental results and to calculations performed using the Monte-Carlo codes MCNP with a continuous-energy neutrons cross-section library and KENO V.a with a cross-section library based on the 16-group Hansen-Roach neutron cross-section set. The TWODANT and KENO V.a codes underestimated the calculated keff for most cases whereas MCNP in most cases showed a keff estimation much closer to unity. Dimension search performed using TWODANT show that the code is able to follow the trend in the measured critical height with a relatively constant bias of 8.96% of the measured height.
Type:
text; Thesis-Reproduction (electronic)
Keywords:
Engineering, Nuclear.
Degree Name:
M.S.
Degree Level:
masters
Degree Program:
Graduate College; Nuclear and Energy Engineering
Degree Grantor:
University of Arizona
Advisor:
Seale, Robert L.

Full metadata record

DC FieldValue Language
dc.language.isoen_USen_US
dc.titleBenchmarking TWODANT using the French CRAC experimentsen_US
dc.creatorBettan, Yehoshua Michael, 1959-en_US
dc.contributor.authorBettan, Yehoshua Michael, 1959-en_US
dc.date.issued1993en_US
dc.publisherThe University of Arizona.en_US
dc.rightsCopyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.en_US
dc.description.abstractCritical calculations of unreflected cylinders filled with fissile solution were performed using the TWODANT code with the 118-isotope, 16-group Hansen-Roach neutron cross-section library. The benchmark experiments used were the France CRAC experiments. In these experiments unreflected 300mm and 800mm cylinders were used to contain the solution. The fissile solution was highly enriched (approximately 93%) uranyl nitrate solution of various concentrations. These concentrations varied from 21.4 g/l to 383 g/l in total uranium. The calculational results were compared to the experimental results and to calculations performed using the Monte-Carlo codes MCNP with a continuous-energy neutrons cross-section library and KENO V.a with a cross-section library based on the 16-group Hansen-Roach neutron cross-section set. The TWODANT and KENO V.a codes underestimated the calculated keff for most cases whereas MCNP in most cases showed a keff estimation much closer to unity. Dimension search performed using TWODANT show that the code is able to follow the trend in the measured critical height with a relatively constant bias of 8.96% of the measured height.en_US
dc.typetexten_US
dc.typeThesis-Reproduction (electronic)en_US
dc.subjectEngineering, Nuclear.en_US
thesis.degree.nameM.S.en_US
thesis.degree.levelmastersen_US
thesis.degree.disciplineGraduate Collegeen_US
thesis.degree.disciplineNuclear and Energy Engineeringen_US
thesis.degree.grantorUniversity of Arizonaen_US
dc.contributor.advisorSeale, Robert L.en_US
dc.identifier.proquest1352333en_US
dc.identifier.bibrecord.b27086410en_US
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