Undergraduate Thesis Or Project

 

Measuring Neutron Absorption Cross Sections of Natural Platinum via Neutron Activation Analysis Public Deposited

Downloadable Content

Download PDF
https://ir.library.oregonstate.edu/concern/undergraduate_thesis_or_projects/0z708x84n

Descriptions

Attribute NameValues
Creator
Abstract
  • This thesis presents a measurement of the resonance integral and thermal cross section – which together represent the total neutron absorption cross section – of the naturally occurring isotopes of platinum that emit gamma radiation upon neutron absorption. The measurements were made via neutron activation analysis. Platinum samples were bombarded by neutrons produced in Oregon State University’s TRIGA nuclear reactor. Afterwards, the decay of the excited samples was measured to determine the activity of each isotope, yielding measurements of the cross sections for each. This experiment was repeated multiple times in different reactor locations to improve accuracy. Previous measurements of these values have been flawed by poor photon detector resolution, and evolving branching ratios, half-lives, natural abundances. A search of the literature reveals poor agreement and large error estimations. The results from this thesis are consistent, with one exception: there appears to be a systematic disagreement between the resonance integral measurements of samples bombarded in two different reactor locations. This discrepancy has now been seen in several experiments, which indicates inconsistent epithermal flux throughout OSU’s reactor.
Resource Type
Date Available
Date Issued
Degree Level
Degree Name
Degree Field
Degree Grantor
Commencement Year
Academic Affiliation
Non-Academic Affiliation
Table of Contents
  • 1 INTRODUCTION 1• 1.1 MOTIVATION 1• 1.2 CROSS SECTION AND NEUTRON ENERGY 2• 1.3 DECAY SCHEME AND NUCLEAR SPIN 5• 1.4 PLATINUM ISOTOPES 62 EXPERIMENTAL METHODS 8• 2.1 EXPERIMENT OVERVIEW 8• 2.2 INDEPENDENT EXPERIMENTS 8• 2.3 FLUX MONITORS 11• 2.4 CAPTURE OF GAMMA SPECTRA 11• 2.4 DATA ANALYSIS 12• 2.5 DETECTOR EFFICIENCY 143 RESULTS 16• 3.1 CLICIT RESULTS 16• 3.2 CADMIUM-ENCLOSED RABBIT RESULTS 17• 3.3 NON CADMIUM-ENCLOSED RABBIT RESULTS 19• 3.4 THERMAL COLUMN RESULTS 20• 3.5 UNCERTAINTY CALCULATIONS 214 DISCUSSION 22• 4.1 PREVIOUS RESULTS 22• 4.2 PT-190 → PT-191 CROSS SECTION 23• 4.3 PT-194 → PT-195M CROSS SECTION 24• 4.4 PT-196 → PT-197G CROSS SECTION 24• 4.5 PT-196 → PT-197M CROSS SECTION 24• 5.6 PT-198 → PT-199G CROSS SECTION 245 CONCLUSION 266 ACKNOWLEDGEMENTS 277 REFERENCES 28
Rights Statement
Publisher
Peer Reviewed
Language
Replaces
Additional Information
  • description.provenance : Rejected by Deanne Bruner(deanne.bruner@oregonstate.edu), reason: Hi Nick,Per your request, I'm rejecting your submission.Thanks,Deanne J. BrunerScholars Archive Techniciandeanne.bruner@oregonstate.edu541.737.7330 on 2012-06-11T22:50:45Z (GMT)
  • description.provenance : Submitted by Nicholas Petersen (peternic@onid.orst.edu) on 2012-06-13T12:27:56ZNo. of bitstreams: 1Petersen Final Thesis.pdf: 455757 bytes, checksum: f2e1b43be37da3962759a6ebe258fd7b (MD5)
  • description.provenance : Submitted by Nicholas Petersen (peternic@onid.orst.edu) on 2012-06-11T08:37:40ZNo. of bitstreams: 1Thesis.pdf: 801661 bytes, checksum: 2df27aee0f7416e143cdab1dc6927b0d (MD5)
  • description.provenance : Made available in DSpace on 2012-06-13T14:59:19Z (GMT). No. of bitstreams: 1Petersen Final Thesis.pdf: 455757 bytes, checksum: f2e1b43be37da3962759a6ebe258fd7b (MD5) Previous issue date: 2012-06-11
  • description.provenance : Approved for entry into archive by Sue Kunda(sue.kunda@oregonstate.edu) on 2012-06-13T14:59:19Z (GMT) No. of bitstreams: 1Petersen Final Thesis.pdf: 455757 bytes, checksum: f2e1b43be37da3962759a6ebe258fd7b (MD5)

Relationships

Parents:

This work has no parents.

Items