Difference between revisions of "Determination of Unknown Sample"

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*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.
 
*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.
  
{| width="551" height="201" cellspacing="1" cellpadding="1" border="1" style=""
+
{| width="551" cellspacing="1" cellpadding="1" border="1" style=""
|+ Table 3: results from spectroscopy of unknown sample
+
|+ Table 3: results from spectroscopy of unknown sample  
 
|-
 
|-
| Photo Peak no.
+
| Photo Peak no.  
| Energy (keV
+
| Energy (keV  
| Net Count
+
| Net Count  
| Uncertainty
+
| Uncertainty  
 
| FWHM (keV
 
| FWHM (keV
 
|-
 
|-
| align="right" | 1
+
| align="right" | 1  
| align="right" | 67.63
+
| align="right" | 67.63  
| align="right" | 166011
+
| align="right" | 166011  
| align="right" | 1885
+
| align="right" | 1885  
 
| align="right" | 0.44
 
| align="right" | 0.44
 
|-
 
|-
| align="right" | 2
+
| align="right" | 2  
| align="right" | 100.26
+
| align="right" | 100.26  
| align="right" | 79985
+
| align="right" | 79985  
| align="right" | 902
+
| align="right" | 902  
 
| align="right" | 1.00
 
| align="right" | 1.00
 
|-
 
|-
| align="right" | 3
+
| align="right" | 3  
| align="right" | 152.56
+
| align="right" | 152.56  
| align="right" | 34987
+
| align="right" | 34987  
| align="right" | 401
+
| align="right" | 401  
 
| align="right" | 1.16
 
| align="right" | 1.16
 
|-
 
|-
| align="right" | 4
+
| align="right" | 4  
| align="right" | 222.08
+
| align="right" | 222.08  
| align="right" | 29011
+
| align="right" | 29011  
| align="right" | 335
+
| align="right" | 335  
 
| align="right" | 1.52
 
| align="right" | 1.52
 
|-
 
|-
| align="right" | 5
+
| align="right" | 5  
| align="right" | 511
+
| align="right" | 511  
| align="right" | 210890
+
| align="right" | 210890  
| align="right" | 2385
+
| align="right" | 2385  
 
| align="right" | 2.24
 
| align="right" | 2.24
 
|-
 
|-
| align="right" | 6
+
| align="right" | 6  
| align="right" | 1121.14
+
| align="right" | 1121.14  
| align="right" | 32098
+
| align="right" | 32098  
| align="right" | 391
+
| align="right" | 391  
 
| align="right" | 1.67
 
| align="right" | 1.67
 
|-
 
|-
| align="right" | 7
+
| align="right" | 7  
| align="right" | 1188.7
+
| align="right" | 1188.7  
| align="right" | 14563
+
| align="right" | 14563  
| align="right" | 173
+
| align="right" | 173  
 
| align="right" | 1.17
 
| align="right" | 1.17
 
|-
 
|-
| align="right" | 8
+
| align="right" | 8  
| align="right" | 1221.28
+
| align="right" | 1221.28  
| align="right" | 23825
+
| align="right" | 23825  
| align="right" | 265
+
| align="right" | 265  
 
| align="right" | 2.01
 
| align="right" | 2.01
 
|}
 
|}
 +
 +
[[Category:Neutron_Activation_Analysis]][[Category:HPGe_detector]][[Category:Gamma_spectroscopy]]

Revision as of 09:54, 27 June 2012

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 theefficiency 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