• 검색 결과가 없습니다.

X-ray Shield for High Energy Gamma Spectrometry using a n-type HPGe Detector

N/A
N/A
Protected

Academic year: 2021

Share "X-ray Shield for High Energy Gamma Spectrometry using a n-type HPGe Detector"

Copied!
2
0
0

로드 중.... (전체 텍스트 보기)

전체 글

(1)

2009년도 춘계 학술발표회 논문집 대한방사선방어학회

250 _ http://www.karp.or.kr

X-ray Shield for High Energy Gamma Spectrometry using a n-type HPGe Detector

Jong In Byun

1

․ Jeong Hwan Row

2

․ Ji Yun Lee

2

․ Ju Yong Yun

1,2

1

University of Science & Technology ․

2

Korea Institute of Nuclear Safety

E-mail: [email protected]

keyword : Cascade coincidence summing, X-ray, HPGe

Introduction

In the last several decades HPGe detectors have been used popularly because of good energy resolution and high efficiency. And HPGe detectors to measure low energy gamma rays also have been developed by several companies. The detectors are generally called as a n-type HPGe detector or LEGe. The commercial n-type HPGe detectors have the front window made from carbonate or beryllium to increase the detection efficiency for low energy photons. For that reason, cascade coincidence summing effects by X- and Gamma rays can be produced. In order to use the n-type HPGe detector for high energy gamma rays, therefore, we should eliminate incidence of X-rays or correct the effects. The correction for X- and Gamma rays might be so complicate and difficult. On the other hand, the summing effects can be terminated by additional X-ray shields at the end cap.

In this study, we optimized the thickness of shielding material selected for the purpose. This paper demonstrates the optimization process and the shield's applicability for detection efficiency calibration and radioactivity analysis.

Materials and Methods

When determining the detection efficiency for HPGe detector, we usually use commercial standard radioactive source. In general, the source contains

241

Am,

109

Cd,

57

Co,

139

Ce,

113

Sn,

203

Hg,

85

Sr,

137

Cs,

60

Co and

88

Y. Of them,

113

Sn,

85

Sr and

88

Y can produce the X- and gamma rays summing effects[1]. Therefore, the material and its thickness should be selected considering the maximum X-ray energy to produce the effects.

The maximum energy line of X-ray is about 40 keV in

139

Ce. Firstly, we compared interaction characteristics with X-rays of Cu and Al. The interests of X-ray energy in Cu are dominantly absorbed by photoelectric effects. That is, the cascade summing effects by multiple scattered X- and Gamma rays can be terminated in Cu. The coefficients were calculated by using XCom software[2]. Cu was determined as shielding material because of the interaction characteristics with X-rays and good workability. Secondly, we optimized the thickness of Cu considering X-ray energy and detection efficiency for Gamma rays.

The thickness was determined as 0.2 cm by

linear attenuation coefficients in Cu. In fact, the

thickness is conservative because the integration

of actual path length of photons to detector is

(2)

2009년도 춘계 학술발표회 논문집 대한방사선방어학회

대한방사선방어학회_ 251 longer than the calculation.

Fig. 2. Total linear attenuation rate excluding coherent scattering, for Cu with varied thickness from 0.05 to 1 cm, calculated with XCOM.

In addition, the probability to produce the cascade summing after penetrating Cu is nearly zero. As shown in Fig. 2, the attenuation rate for about 40 keV is nearly 100 %. Finally, in order to test the detection efficiency with Cu shield, we made efficiency curve and analyzed radioactivity of radioisotopes contained in reference materials.

For the purpose, we used cylindrical types of radioactive sources. The commercial standard radioactive source was diluted in U8 vial ( ∅ 2.4 × 6 cm

3

) with 2 M HCl. And we used a n-type coaxial HPGe detector with a relative efficiency of 30 %. All radioactive sources were measured on the detector window. The gamma ray peaks were measured within relative counting uncertainty of 2

%. To show the applicability of the copper shield, the IAEA reference materials also were filled in U8 vial and the radioactivity analysis results were compared with recommended values.

Results and Discussion

The Fig. 3 shows the characteristics of efficiency curves with cascade coincidence summing effects by X- and Gamma rays. We can

Fig. 3. The efficiency curves with and without cascade summing effects for U8-10mm.

find that detection efficiencies for the

139

Ce and

88

Y are especially underestimated due to X- and Gamma summing. As the curve by circle plots, final corrected efficiency curve is showed by '2nd corrected curve' in Fig. 3. The radioactivity analysis results using the efficiency curve corrected agreed well within the range of recommended values of

137

Cs and

40

K contained in the reference samples.

Conclusions

In this study, we made copper shield to ignore the cascade summing effects by X- and Gamma rays. The thickness of copper shield was determined as 0.2 cm considering detection efficiency and interaction characteristics with X-rays. The radioactivity analysis results for applicability of the copper shield agreed well with recommended values. It is expected for the copper shield to increase the applicability of the n-type HPGe detector with good efficiency calibration.

REFERENCES

1. Firestone, R. B., Shirley, V. S. (Eds.). Table of Isotopes. 8th ed. (1996).

2. Berger, M.J., Hubbell, J.H, etc..(2005), XCOM:

Photon Cross Section Database (version 1.3).

수치

Fig.  2.  Total  linear  attenuation  rate  excluding  coherent  scattering,  for  Cu  with  varied  thickness  from  0.05  to  1  cm,  calculated  with  XCOM.

참조

관련 문서

In this study, the different codes were compared and analyzed for the research on decontamination and decommissioning waste generation by using the codes

• In-situ gamma-ray spectrometry for radioactivity analysis of soil using NaI(Tl) and LaBr 3 (Ce) detectors/ Radiation Protection Dosimetry, 2019. • In-situ CeBr

Although this energy can be released in the form of an emitted photon (X-ray fluorescence), the energy can also be transferred to another electron, which is ejected from

Also, for verifying the study hypothesis, unitary multi-variant analysis, correlation analysis and structural equation model analysis were carried out. The

In gi ngi va,LCs are found i n oralepi thel i um ofnormalgi ngi va and i n smal l er amountsi nthesul cul arepi thel i um,buttheyareprobabl yabsentfrom thejuncti onal epi thel

The structure and film optical properties were investigated by X-ray diffraction(XRD), the particle size and thickness were investigated by scanning

 Three major purposes of a blanket: (1) capture the neutrons generated by fusion and convert their energy into heat, (2) produce the tritium to fuel the DT reaction, and

 Three major purposes of a blanket: (1) capture the neutrons generated by fusion and convert their energy into heat, (2) produce the tritium to fuel the DT reaction, and