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The 252Cf isotope sources have a recommended standard neutron spectrum of spontaneous fission, and have been widely used in scientific researches, such as the detection efficiency calibration of neutron detectors, the characterization of neutron dose equivalent meters, the active analysis of special nuclear materials, etc. However, it is often necessary to correct the neutron emission rate due to its short half-life of 2.645 years. As the source age increases the contributions from 250Cf and 248Cm spontaneous fission become more significant, thus the neutron emission rate cannot be calculated simply according to the 252Cf decay law. In addition, the indirect measurement method by manganese bath activation needs a long period more than 8 hours; and it will have a large uncertainty while the source strength is lower than 104 n/s. In order to develop a more portable measurement method for larger suitable dynamic range, the comprehensive algorithms based on the neutron multiplicity counting are studied in this paper. On the basis of the measurement equations under the point model assumption, the neutron coincidence counting rate is correlated with the total neutron counting rate, and then the regression analyses with different coincidence gates and different source locations in the counter are performed. On the assumption that the average neutron die-away time is constant in the sensitive range of detection system, therefore the characteristic coefficient from the changing process can be extracted, and two kinds of methods of measuring the neutron strength are established, which are independent of the efficiency variation. The verification experiments are carried out by the JCC-51 neutron coincidence counter. It is shown that the values measured by the two regression methods are consistent with the corrected results of the nominal value within 2% deviation. Furthermore, the detection efficiency is inversed by dividing the total neutron counting rate with the neutron emission rate when the source is placed at the central axis, which accords with the result of Monte Carlo simulation by using the MCNPX code well. It can provide an accurate method of determining the neutron emission rate of 252Cf spontaneous fission, and also an approach to calibrating the detection efficiency of neutron coincidence counter while the source strength is unknown.
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Keywords:
- 252Cf spontaneous fission /
- neutron emission rate /
- coincidence measurements /
- regression analysis
[1] David T, Roberto B, Roberto M, Alan T, Andreas Z 2018 Radiat. Prot. Dosim. 180 21
[2] Tadashi A, Toshikazu S, Ikuo M, Masakuni N, Yuichi O 1991 IEEE Trans. Nucl. Sci. 38 1040
[3] Reeder P L, Bowyer S M 2002 Nucl. Instrum. Methods Phys. Res. A 484 469
[4] Lawrence C C, Flaska M M, Ojaruega M, Andreas E, Clarke S D, Pozzi S A, Becchetti F D 2010 IEEE Nulcear Science Symposium & Medical Imaging Conference Knoxville, USA, October 30-November 6, 2010 p110
[5] Józefowicz K, Golnik N, Tulik P, Zielczyński M 2007 Radiat. Prot. Dosim. 126 134
[6] Thiem N L, Hoai N T, Khai T N, Giap V T 2017 Nucl. Eng. Technol. 49 277
[7] Mihalczo J T, Mullens J A, Mattingly J K, Valentine T E 2000 Nucl. Instrum. Methods Phys. Res. A 450 531
[8] Pozzi S A, Segovia J 2002 Nucl. Instrum. Methods Phys. Res. A 491 326
[9] Roberts N J, Jones L N 2007 Radiat. Prot. Dosim. 126 83
[10] Hwang S T, Lee K 1988 Nucl. Instrum. Methods Phys. Res. A 273 381
[11] Croft S, Henzlov D 2013 Nucl. Instrum. Methods Phys. Res. A 714 5
[12] Ridnik T, Dubi C, Israelashvili I, Bagi J, Huszti J 2014 Nucl. Instrum. Methods Phys. Res. A 735 53
[13] Ensslin N, Harker W C, Krick M S, Langner D G, Pickrell M M, Stewart J E 1998 Los Alamos National Laboratory Report LA-13422-M
[14] Francesca F, Paolo P 2010 Radiat. Meas. 45 1034
[15] Berndt R, Brutscher J, Mortreau P 2014 Symposium on International Safeguards: Linking Strategy, Implementation and People Vienna, Austria, October 20-24, 2014 p1
[16] Pelowitz D B 2011 Los Alamos National Laboratory Report LA-CP-11-00438
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[1] David T, Roberto B, Roberto M, Alan T, Andreas Z 2018 Radiat. Prot. Dosim. 180 21
[2] Tadashi A, Toshikazu S, Ikuo M, Masakuni N, Yuichi O 1991 IEEE Trans. Nucl. Sci. 38 1040
[3] Reeder P L, Bowyer S M 2002 Nucl. Instrum. Methods Phys. Res. A 484 469
[4] Lawrence C C, Flaska M M, Ojaruega M, Andreas E, Clarke S D, Pozzi S A, Becchetti F D 2010 IEEE Nulcear Science Symposium & Medical Imaging Conference Knoxville, USA, October 30-November 6, 2010 p110
[5] Józefowicz K, Golnik N, Tulik P, Zielczyński M 2007 Radiat. Prot. Dosim. 126 134
[6] Thiem N L, Hoai N T, Khai T N, Giap V T 2017 Nucl. Eng. Technol. 49 277
[7] Mihalczo J T, Mullens J A, Mattingly J K, Valentine T E 2000 Nucl. Instrum. Methods Phys. Res. A 450 531
[8] Pozzi S A, Segovia J 2002 Nucl. Instrum. Methods Phys. Res. A 491 326
[9] Roberts N J, Jones L N 2007 Radiat. Prot. Dosim. 126 83
[10] Hwang S T, Lee K 1988 Nucl. Instrum. Methods Phys. Res. A 273 381
[11] Croft S, Henzlov D 2013 Nucl. Instrum. Methods Phys. Res. A 714 5
[12] Ridnik T, Dubi C, Israelashvili I, Bagi J, Huszti J 2014 Nucl. Instrum. Methods Phys. Res. A 735 53
[13] Ensslin N, Harker W C, Krick M S, Langner D G, Pickrell M M, Stewart J E 1998 Los Alamos National Laboratory Report LA-13422-M
[14] Francesca F, Paolo P 2010 Radiat. Meas. 45 1034
[15] Berndt R, Brutscher J, Mortreau P 2014 Symposium on International Safeguards: Linking Strategy, Implementation and People Vienna, Austria, October 20-24, 2014 p1
[16] Pelowitz D B 2011 Los Alamos National Laboratory Report LA-CP-11-00438
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