Difference between revisions of "Determination of Unknown Sample"

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Return to [[Gamma Spectroscopy Analysis|Main]]  
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In table 3 the analysis results of the unknown, n-irradiated sample is shown. Use the results to&nbsp;:  
 
In table 3 the analysis results of the unknown, n-irradiated sample is shown. Use the results to&nbsp;:  
  
 
*Determine which metal the sample consist of. Use the identified <span class="texhtml">γ</span>-ray energies to do this. if you need a database you can use [http://nucleardata.nuclear.lu.se/nucleardata/toi/ this one]  
 
*Determine which metal the sample consist of. Use the identified <span class="texhtml">γ</span>-ray energies to do this. if you need a database you can use [http://nucleardata.nuclear.lu.se/nucleardata/toi/ this one]  
*Determine the absolute amount of the metal. Use the counts measured in table 3 and theefficiency curve you made in exercise 3B. Use at least two different <span class="texhtml">γ</span> lines to do this, we recommend E<sub><span class="texhtml">γ</span></sub> = 222.08 keV and E<sub><span class="texhtml">γ</span></sub> 1 MeV. The neutron flux was 10<sup>5</sup> n/(s cm<sup>2</sup>) during the irradiation, and the irradiation time was 18 days. The sample was measured directly after the irradiation.
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*Determine the absolute amount of the metal. Use the counts measured in table 3 and the efficiency curve you made in exercise 3B. Use at least two different <span class="texhtml">γ</span> lines to do this, we recommend E<sub><span class="texhtml">γ</span></sub> = 222.08 keV and E<sub><span class="texhtml">γ</span></sub> 1 MeV. The neutron flux was 10<sup>5</sup> n/(s cm<sup>2</sup>) during the irradiation, and the irradiation time was 18 days. The sample was measured directly after the irradiation.
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{| cellspacing="1" cellpadding="1" border="1" width="551" style=""
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|+ Table 3: results from spectroscopy of unknown sample
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|-
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| Photo Peak no.
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| Energy (keV
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| Net Count
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| Uncertainty
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| FWHM (keV
 +
|-
 +
| align="right" | 1
 +
| align="right" | 67.63
 +
| align="right" | 166011
 +
| align="right" | 1885
 +
| align="right" | 0.44
 +
|-
 +
| align="right" | 2
 +
| align="right" | 100.26
 +
| align="right" | 79985
 +
| align="right" | 902
 +
| align="right" | 1.00
 +
|-
 +
| align="right" | 3
 +
| align="right" | 152.56
 +
| align="right" | 34987
 +
| align="right" | 401
 +
| align="right" | 1.16
 +
|-
 +
| align="right" | 4
 +
| align="right" | 222.08
 +
| align="right" | 29011
 +
| align="right" | 335
 +
| align="right" | 1.52
 +
|-
 +
| align="right" | 5
 +
| align="right" | 511
 +
| align="right" | 210890
 +
| align="right" | 2385
 +
| align="right" | 2.24
 +
|-
 +
| align="right" | 6
 +
| align="right" | 1121.14
 +
| align="right" | 32098
 +
| align="right" | 391
 +
| align="right" | 1.67
 +
|-
 +
| align="right" | 7
 +
| align="right" | 1188.7
 +
| align="right" | 14563
 +
| align="right" | 173
 +
| align="right" | 1.17
 +
|-
 +
| align="right" | 8
 +
| align="right" | 1221.28
 +
| align="right" | 23825
 +
| align="right" | 265
 +
| align="right" | 2.01
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|}
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[[Category:Neutron_Activation_Analysis]] [[Category:HPGe_detector]] [[Category:Gamma_spectroscopy]]

Latest revision as of 14:16, 28 June 2012

Return to Main


In table 3 the analysis results of the unknown, n-irradiated sample is shown. Use the results to :

  • Determine which metal the sample consist of. Use the identified γ-ray energies to do this. if you need a database you can use this one
  • Determine the absolute amount of the metal. Use the counts measured in table 3 and the efficiency curve you made in exercise 3B. Use at least two different γ lines to do this, we recommend Eγ = 222.08 keV and Eγ 1 MeV. The neutron flux was 105 n/(s cm2) during the irradiation, and the irradiation time was 18 days. The sample was measured directly after the irradiation.
Table 3: results from spectroscopy of unknown sample
Photo Peak no. Energy (keV Net Count Uncertainty FWHM (keV
1 67.63 166011 1885 0.44
2 100.26 79985 902 1.00
3 152.56 34987 401 1.16
4 222.08 29011 335 1.52
5 511 210890 2385 2.24
6 1121.14 32098 391 1.67
7 1188.7 14563 173 1.17
8 1221.28 23825 265 2.01