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Optimization of Design of a D2O-moderated 252Cf Source for Personal Dosimetry Performance Test

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

Among the test categories of the personal dosimetry performance test in Korea, the reference neutron radiation field used for the mixed neutron-photon radiation field is generated by a D2Omoderated 252Cf source. There are some differences depending on the standards, D2O-moderated 252Cf source consists of the 252Cf source surrounded by the D2O sphere with a diameter of 30 cm, covered with a Cd shell of thickness approximately 0.051 cm ~ 0.1 cm. In order to optimize the design of the D2O sphere and establish the neutron radiation field for the personal dosimetry performance test in Central Research Institute of KHNP, the neutron spectra have been simulated by MCNP 6.2 code by design conditions and evaluated dose conversion coefficients. In the consideration of neutron irradiation facility, the basic design structure was determined a D2O sphere with a diameter of covered with a Cd shell and a cylindrical well is in the middle of sphere. Neutron source transfer tube is inserted into this well-shaped structure and neutron source was withdrawn from the tube. And by changing the following design conditions in detail, the neutron spectra were evaluated; 1) the entire diameter of the D2O sphere (with or without the diameter of 7.5 cm of well-shaped structure) 2) the location of the neutron source (distance from D2O) 3) thickness of Cd shell 4) purity of D2O. As a source spectrum, the spectrum of bare- 252Cf recommended by ISO 8529-1 was adopted and spectra were tallied using F4 tally at a distance of 120 cm from the neutron source. Finally, the fluence to dose conversion coefficients were calculated using the simulated spectra. As a result of the evaluation, in case that an entire diameter of the D2O sphere with a diameter of the source tube is 37.5 cm, the fluence to dose conversion coefficient was evaluated to about 4.4% lower than an entire diameter of the D2O sphere is 30 cm. And in case that the distance between the D2O and the top of the neutron source was about 3.75 cm which is a radius of well-type structure, it was evaluated to about 1.4% larger than the distance was about 1 cm, and when the thickness of Cd was 0.1 cm, it was evaluated to 0.8% larger than when it was 0.051 cm. Finally, when the purity of D2O was 99.99%, it was evaluated 1.5% lower than when it was 99%. Except for the diameter of D2O sphere, the differences on the other conditions are acceptable considering the uncertainty of the simulation. Therefore, the design of D2O-moderated 252Cf source was determined by considering source integrity, economic perspectives, and dose conversion coefficient given in ISO 8529: a D2O sphere with an entire diameter of 37.5 cm, filled with above 99% purity of D2O, and covered with a cadmium thickness of 0.1 cm. The fluence to dose conversion efficient was evaluated as 110.10 pSv cm2 for ambient dose H*(10), 115.21 pSv cm2 for personal dose Hp(10) respectively.

저자
  • Munhyung Cho(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
  • Yuho Weon(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
  • Hyeongjin Kim(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI)) Corresponding author