Expected total counts for the Self-Interrogation Neutron Resonance Densitometry measurements of spent nuclear fuel
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Abstract
This poster is focused on the estimation of the total neutron counts that can be achieved ideally with the SINRD measurements of spent nuclear fuel. The contributions compares different detector types and SINRD filters that are used to measure the neutron flux in the fast and in the resonance energy region. Fission chambers using 239Pu or 235U as active material and proportional counters containing 3He or 10B were compared. The fission chambers obtained the highest sensitivity to the 239Pu content, whereas the proportional counters showed the highest total neutron counts.
Details
| Original language | English |
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| Title of host publication | Proceedings of the 2015 ANIMMA conference |
| Place of Publication | Portugal |
| Pages | 1-6 |
| Publication status | Published - Apr 2015 |
| Event | 2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications: International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications - Lisbon, Portugal Duration: 20 Apr 2015 → 24 Apr 2015 |
Conference
| Conference | 2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications |
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| Country | Portugal |
| City | Lisbon |
| Period | 2015-04-20 → 2015-04-24 |
Keywords
- SINRD, spent fuel, NDA, 239Pu, safeguards
ID: 106515