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EVALUATION OF SYRINGE SHIELD EFFECTIVENESS IN HANDLING RADIOPHARMACEUTICALS by Yong-In CHO 1 , Chang-Soo KIM 2 , and Jung-Hoon KIM 2* 1 Department of Nuclear Medicine, Dongnam Institute of Radiological & Medical Science, Pusan, Korea 2 Department of Radiological Science, College of Health Sciences, Catholic University of Pusan, Pusan, Korea Technical paper DOI: 10.2298/NTRP1502158C The purpose of this study was to evaluate the effectiveness of the radiation shield of radionuclide syringes and the personal dose equivalent by performing a simulation of radionuclides used in nuclear medicine diagnosis. In order to evaluate the dose depending on the distance between the radiation source and the ICRU sphere against the thickness of the shielding device, the distance at which a nuclear medicine worker may inadvertently come into contact with radiation from the radiation source was set at 0 cm to 30 cm according to the thickness of the shield, thus fixing the ICRU sphere. For a dose evaluation, Hp(10), Hp(3), and Hp(0.07) measurable in specific depth of the ICRU were evaluated. It was found that a dose measured on skin surface of nuclear medicine workers was relatively higher, that the dose varied in relation to the thickness of the radiation shield, and that the shielding effect de- creased for some radiation sources such as 67 Ga and 111 In. It proved necessary to increase thickness of shielding device to the radiation sources such as 67 Ga and 111 In. It is also consid- ered that a study of proper shielding thickness will be needed in future. Key words: ICRU sphere, syringe shield, personal dose equivalent, radionuclide INTRODUCTION Nuclear medicine workers are commonly ex- posed to radiation from radioisotopes and radio- pharmaceuticals due to the nature of their job which includes the compounding, distribution, and injection of radiopharmaceuticals [1]. For these reasons, studies on reducing the amount of radiation to which nuclear medicine workers are exposed have been conducted continuously. The most popular radionuclide used for diagnosis in the field of nuclear medicine is 99m Tc but various others including 18 F, 131 I, 123 I, 201 Tl, 67 Ga and 111 In are used as well [2]. Each radionuclide has its own unique combination of energy emission and half-life, so the exposure dose that a nuclear medicine worker may receive differs according to the different physical characteristics of each radionuclide being handled [3]. Accordingly, it is necessary to use proper shielding devices with regard to the gamma-ray en- ergy being emitted from the radionuclide used. Vari- ous types of syringe shields used to reduce the expo- sure dose to hands when transferring and injecting radiopharmaceuticals have been developed and are currently used commercially [4]. In some studies, it was reported that many nuclear medicine workers of medical institutes actually did not use any radiation shields because of discomfiture or in- convenience, or they felt that using them hampered their work efficiency, so they often performed their tasks overlooking radiation exposure to their hands. Al- though the personal exposure dose of nuclear medicine workers is measured quarterly with a calibrated per- sonal dosimeter, doing so is restricted to measuring ex- posure of the whole body rather than any specific ex- tremities [5, 6]. In addition, the personal exposure dose is different corresponding to the work environment of each institute, skill of workers, and how the shielding devices are used, which makes it difficult to be confi- dent in the dosimeter for evaluating the personal expo- sure dose by energy and direction dependency [7]. This study is intended to simulate the personal dose equivalent depending on the thickness of a typi- cal syringe shield used in a typical nuclear medicine institute and a dose in accordance with distance when injecting radiopharmaceuticals, thus providing basic data about the effectiveness of shielding devices and radiation protection of nuclear medicine workers. MA TERIALS AND METHODS Monte Carlo simulation The Monte Carlo simulation is a method of sim- ulating the behavior of neutrons, photons, and elec- Y.-I. Cho, et al.: Evaluation of Syringe Shield Effectiveness in Handling ... 158 Nuclear Technology & Radiation Protection: Year 2015, Vol. 30, No. 2, pp. 158-163 * Corresponding author; e-mail: donald@cup.ac.kr

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EVAL U A TION OF SY RINGE SHIELD EF FEC TIVE NESS INHAN DLING RADIOPHARMACEUTICALS

by

Yong-In CHO 1, Chang-Soo KIM 2, and Jung-Hoon KIM 2*

1 De part ment of Nu clear Med i cine, Dongnam In sti tute of Ra dio log i cal & Med i cal Sci ence, Pu san, Ko rea2 De part ment of Ra dio log i cal Sci ence, Col lege of Health Sci ences, Cath o lic Uni ver sity of Pu san, Pu san, Ko rea

Tech ni cal pa perDOI: 10.2298/NTRP1502158C

The pur pose of this study was to eval u ate the ef fec tive ness of the ra di a tion shield ofradionuclide sy ringes and the per sonal dose equiv a lent by per form ing a sim u la tion ofradionuclides used in nu clear med i cine di ag no sis. In or der to eval u ate the dose de pend ing onthe dis tance be tween the ra di a tion source and the ICRU sphere against the thick ness of theshield ing de vice, the dis tance at which a nu clear med i cine worker may in ad ver tently comeinto con tact with ra di a tion from the ra di a tion source was set at 0 cm to 30 cm ac cord ing to the thick ness of the shield, thus fix ing the ICRU sphere. For a dose eval u a tion, Hp(10), Hp(3),and Hp(0.07) mea sur able in spe cific depth of the ICRU were eval u ated. It was found that adose mea sured on skin sur face of nu clear med i cine work ers was rel a tively higher, that the dose var ied in re la tion to the thick ness of the ra di a tion shield, and that the shield ing ef fect de -creased for some ra di a tion sources such as 67Ga and 111In. It proved nec es sary to in creasethick ness of shield ing de vice to the ra di a tion sources such as 67Ga and 111In. It is also con sid -ered that a study of proper shield ing thick ness will be needed in fu ture.

Key words: ICRU sphere, sy ringe shield, per sonal dose equiv a lent, radionuclide

IN TRO DUC TION

Nu clear med i cine work ers are com monly ex -posed to ra di a tion from ra dio iso topes and ra dio-pharmaceuticals due to the na ture of their job whichin cludes the com pound ing, dis tri bu tion, and in jec tionof radiopharmaceuticals [1]. For these rea sons, stud ies on re duc ing the amount of ra di a tion to which nu clearmed i cine work ers are ex posed have been con ductedcon tin u ously. The most pop u lar radionuclide used fordi ag no sis in the field of nu clear med i cine is 99mTc butvar i ous oth ers in clud ing 18F, 131I, 123I, 201Tl, 67Ga and111In are used as well [2]. Each radionuclide has itsown unique com bi na tion of en ergy emis sion andhalf-life, so the ex po sure dose that a nu clear med i cineworker may re ceive dif fers ac cord ing to the dif fer entphys i cal char ac ter is tics of each radionuclide be inghan dled [3]. Ac cord ingly, it is nec es sary to use propershield ing de vices with re gard to the gamma-ray en -ergy be ing emit ted from the radionuclide used. Var i -ous types of sy ringe shields used to re duce the ex po -sure dose to hands when trans fer ring and in ject ingradiopharmaceuticals have been de vel oped and arecur rently used com mer cially [4].

In some stud ies, it was re ported that many nu clear med i cine work ers of med i cal in sti tutes ac tu ally did notuse any ra di a tion shields be cause of dis com fi ture or in -

con ve nience, or they felt that us ing them ham peredtheir work ef fi ciency, so they of ten per formed theirtasks over look ing ra di a tion ex po sure to their hands. Al -though the per sonal ex po sure dose of nu clear med i cinework ers is mea sured quar terly with a cal i brated per -sonal do sim e ter, do ing so is re stricted to mea sur ing ex -po sure of the whole body rather than any spe cific ex -trem i ties [5, 6]. In ad di tion, the per sonal ex po sure doseis dif fer ent cor re spond ing to the work en vi ron ment ofeach in sti tute, skill of work ers, and how the shield ingde vices are used, which makes it dif fi cult to be con fi -dent in the do sim e ter for eval u at ing the per sonal ex po -sure dose by en ergy and di rec tion de pend ency [7].

This study is in tended to sim u late the per sonaldose equiv a lent de pend ing on the thick ness of a typ i -cal sy ringe shield used in a typ i cal nu clear med i cinein sti tute and a dose in ac cor dance with dis tance whenin ject ing radiopharmaceuticals, thus pro vid ing ba sicdata about the ef fec tive ness of shield ing de vices andra di a tion pro tec tion of nu clear med i cine work ers.

MA TE RI ALS AND METH ODS

Monte Carlo sim u la tion

The Monte Carlo sim u la tion is a method of sim -u lat ing the be hav ior of neu trons, pho tons, and elec -

Y.-I. Cho, et al.: Eval u a tion of Sy ringe Shield Ef fec tive ness in Han dling ...158 Nu clear Tech nol ogy & Ra di a tion Pro tec tion: Year 2015, Vol. 30, No. 2, pp. 158-163

* Cor re spond ing au thor; e-mail: don [email protected]

trons in var i ous 3-D struc tures of ma te ri als to solvesta tis ti cal prob lems by ran dom sam pling [8]. In thisstudy, the sim u la tion was per formed us ing MCNPX(Ver.2.5.0) de vel oped by the Los Alamos Na tionalLaboratory (N. Mex., USA).

The In ter na tional Com mis sion on Ra di a tionUnits and Mea sure ment (ICRU) has sug gested op er a -tional quan ti ties for the pur pose of mea sur ing or mon i -tor ing the ef fec tive dose. Among them, the per sonaldose equiv a lent Hp (d), used for the pur pose of per sonal mon i tor ing is de fined as a dose equiv a lent to the depthdose Hp(10), lens dose Hp(3), and skin sur face doseHp(0.07) at 10 mm, 3 mm, and 0.07 mm depths from the outer sur face of the ICRU sphere [9]. The sphere is30 cm in di am e ter; it has 1 g/cm3 of in ner den sity andcom prises tis sue-equiv a lent ma te ri als in clud ing ox y -gen 76.2 %, car bon 11.1 %, hy dro gen 10.1 %, and ni tro -gen 2.6 %. In this study, the ex ist ing sphere sug gestedby the ICRU was sim u lated as shown in fig. 1.

A com mer cially avail able sy ringe shield that ispop u larly used when in ject ing radionuclides for gen -eral di ag no sis of nu clear med i cine uses a tung sten (W)plate that is 1~2 mm thick, has an atomic num ber of 74and a den sity of 19.25 g/cm3. In or der to eval u ate theac tual ef fec tive ness of such a shield, the sy ringe shieldused in this study was formed from a tung sten cyl in deras shown in fig. 2 and sim pli fied to place a uni formlysized ra di a tion source in side.

Dose as sess ment

The radionuclides used in this study in cluded99mTc, 123I, 201Tl, 67Ga, and 111In, with the en ergy andoc cur rence rate of each radionuclide se lected us ing ra -di a tion source in for ma tion as shown in tab. 1 [10].

First, in or der to eval u ate how the dose changesin re la tion to the thick ness of the shield ing de vice,three thick nesses were cho sen (non, 1 mm, and 2 mm)and the dis tance be tween each ra di a tion source and the ICRU sphere fixed at 10 cm, which was de fined as thesur face ra di a tion dose in com pli ance with Ko reaAtomic En ergy reg u la tions. Next, in or der to eval u atethe dose de pend ing on the dis tance be tween the ra di a -tion source and the ICRU sphere against the thick nessof the shield ing de vice, the dis tance at which a nu clearmed i cine worker may in ad ver tently come into con tactwith ra di a tion from the ra di a tion source was set at0 cm, the sur face area, to 30 cm ac cord ing to the thick -ness of the shield, thus fix ing the ICRU sphere. Foreval u at ing the dose, the dose of depth Hp(10), lensHp(3), and skin sur face Hp(0.07) mea sur able to spe -cific depths of the ICRU were eval u ated. For Tallyspec i fi ca tion cards, the ab sorbed en ergy per unit mass[MeVg–1] was ob tained by us ing the F6 Tally and con -verted to the per sonal dose equiv a lent when work ingfor one hour, con sid er ing 37 MBq (1 mCi) of ra di a tionac tiv ity for the same dose eval u a tion to eachradionuclide. In or der to re duce the sta tis ti cal er ror ofcal cu la tion be low 3 %, the sim u la tion was re peated1×108 times.

RE SULTS

Dose ac cord ing to the thick nessof the shield ing de vice

As a re sult of mea sur ing the dose at a fixed dis -tance of 10 cm be tween the ra di a tion source and the

Y.-I. Cho, et al.: Eval u a tion of Sy ringe Shield Ef fec tive ness in Han dling ...Nu clear Tech nol ogy & Ra di a tion Pro tec tion: Year 2015, Vol. 30, No. 2, pp. 158-163 159

Fig ure 1. Sim u lated di a gram of the ICRU sphere

Fig ure 2. Sim u la tion of radionuclide and sy ringe shield

Ta ble 1. Radionuclides data

g en ergy(yield)[keV]

99mTc 123I 201Tl 67Ga 111In

140.5(0.89)159.0(0.83) 68.9(0.27) 93.3(0.37) 274.0(0.94)

18.4(0.04) 27.5(0.46) 11.8(0.11) 184.6(0.20) 173.0(0.08)

18.3(0.02) 27.2(0.25) 80.3(0.11) 300.2(0.16)

31.0(0.09) 167.4(0.10) 393.5(0.05)

31.7(0.03) 79.8(0.05) 91.3(0.03)

529.0(0.01) 82.6(0.04) 209.0(0.02)

11.9(0.04)

135.3(0.03)

13.8(0.02)

12.0(0.02)

11.6(0.01)

Half life 6.01 h 13.2 h 2.8 d 3.261 d 2.8 d

ICRU sphere to eval u ate the dose ac cord ing to thethick ness of the shield ing de vice when in ject ing eachradionuclide, it was found that the depth doseHp(10) was 8.688 mSv/h for 99mTc, 8.696 mSv/h for123I, 5.341 mSv/h for 201Tl, 11.828 mSv/h for 67Ga, and18.509 mSv/h for 111In when us ing no sy ringe shield.When us ing 1 mm tung sten (typ i cal of a com mer ciallyavail able sy ringe shield), it was found that the depthdose Hp(10) was 0.191 mSv/h for 99mTc, 0.587 mSv/hfor 123I, 0.134 mSv/h for 201Tl, 3.965 mSv/h for 67Ga,and 8.532 mSv/h for 111In, and the ef fec tive ness of theshield ing ac cord ing to ra di a tion sources was in or derof 99mTc, 201Tl, 123I, 67Ga, and 111In. For the lens doseHp(3) and skin sur face dose Hp(0.07), it was found (as shown in tab. 2) that the ef fec tive ness of a 1 mm tung -sten shield was in the same iden ti cal or der of 99mTc,201Tl, 123I, 67Ga, and 111In. It was also shown that theshield ing ef fect of a 2 mm tung sten shield for the depth dose Hp(10), lens dose Hp(3), and skin sur face doseHp(0.07) showed a sim i lar ten dency as can be seen intab. 2.

Dose to dis tance be tween thera di a tion source and the ICRU sphere

As a re sult of mea sur ing the dose ac cord ing tothe dis tance be tween the ICRU sphere and the ra di a -tion source, it was found (as shown in fig. 3) that at the0 cm point at which the dis tance from the ICRU spherewas the sur face, the depth dose was 34.939 mSv/h for99mTc, 34.894 mSv/h for 123I, 20.944 mSv/h for 201Tl,48.161 mSv/h for 67Ga, and 75.830 mSv/h for 111In. Onthe con trary, as the depth dose 30 cm from theICRU sphere was mea sured as 2.526 mSv/h for99mTc, 2.529 mSv/h for 123I, 1.549 mSv/h for 201Tl,3.431 mSv/h for 67Ga, and 5.359 mSv/h for 111In, it wassug gested that when the dis tance in creased, the dosede creased, and the lens and skin sur face doses showedan equiv a lent ten dency to the above re sults.

When us ing a 1 mm tung sten shield (as with a typ -i cal com mer cially avail able sy ringe shield), the depthdose at the point of 0 cm of which the dis tance from theICRU sphere was the sur face, was mea sured as 0.527mSv/h for 99mTc, 1.963 mSv/h for 123I, 0.389 mSv/h for201Tl, 14.137 mSv/h for 67Ga, and 29.794 mSv/h for 111In. On the con trary, it was shown that as the depth dose at

30 cm from the ICRU sphere was mea sured as 0.063mSv/h for 99mTc, 0.181 mSv/h for 123I, 0.043 mSv/h for

Y.-I. Cho, et al.: Eval u a tion of Sy ringe Shield Ef fec tive ness in Han dling ...160 Nu clear Tech nol ogy & Ra di a tion Pro tec tion: Year 2015, Vol. 30, No. 2, pp. 158-163

Ta ble 2. Dose ac cord ing to thick ness of sy ringe shield in in ject ing each radionuclide (unit: [mSvh–1])

Hp(10) Hp(3) Hp(0.07)

RNa NSb 1 mm W 2 mm W NS 1 mm W 2 mm W NS 1 mm W 2 mm W99mTc 8.688 0.191 0.005 9.543 0.196 0.006 10.06 0.200 0.006

123I 8.696 0.587 0.239 9.950 0.611 0.250 10.59 0.625 0.256201Tl 5.341 0.134 0.011 9.498 0.139 0.012 15.42 0.143 0.01467Ga 11.83 3.965 2.124 12.41 4.156 2.220 12.68 4.247 2.266111In 18.51 8.532 3.992 19.50 8.946 4.166 19.95 9.142 4.252

a RN (Radionuclides), and b NS (Non sy ringe shield)

Fig ure 3. Dose ac cord ing to dis tance be tween the ICRUsphere and the ra di a tion source in us ing no sy ringeshield: (a) Hp(10, (b) Hp(3), and (c) Hp(0.07)

201Tl, 1.184 mSv/h for 67Ga, and 2.556 mSv/h for 111In ra -di a tion source, the dose equiv a lent de creased ac cord ing to the in crease of the dis tance de spite the pres ence of the shield ing de vice. It was also found that the lens and theskin sur face doses showed a sim i lar ten dency to the pre -vi ous re sults, and the re duced dose ra tio among the ra di -a tion sources was higher by as much as 1~1.5 times for67Ga and 111In (fig. 4).

De spite us ing an in creased thick ness, 2 mmtung sten, it was found also (as shown in fig. 5) thatwhen the dis tance in creased, the dose de creased, andthe re duced dose ra tio was higher by as much as 1~1.5times for 123I (fig. 5). In ad di tion, it was sug gested thatthe re duced dose ef fect was higher in or der of skin sur -face, lens and depth dose re gard less of thick ness of theshield ing de vice.

DIS CUS SION

In this study, it was in tended to eval u ate the per -sonal dose ac cord ing to the thick ness of the com mer -cial sy ringe shields cur rently used in de part ments ofnu clear med i cine and the dose ac cord ing to the dis -tance when in ject ing a radionuclide. The re sultsshowed that there were some dif fer ences in the dosesac cord ing to the thick ness of the sy ringe shield andthese re sults showed that the emit ted gamma ray wasre duced due to the shield ing ef fect of the tung stenshield ing ma te rial. It was sug gested that in the ra di a -tion sources with en ergy dis tri bu tion of gamma raysover 200 keV such as 67Ga and 111In, the prob a bil ity ofpho ton in ter ac tion was lower than that of a ra di a tionsource in a low en ergy area, so the shield ing ef fect was

Y.-I. Cho, et al.: Eval u a tion of Sy ringe Shield Ef fec tive ness in Han dling ...Nu clear Tech nol ogy & Ra di a tion Pro tec tion: Year 2015, Vol. 30, No. 2, pp. 158-163 161

Fig ure 4. Dose ac cord ing to dis tance be tween the ICRUsphere and the ra di a tion source in us ing 1 mm tung stenshield ing device: (a) Hp(10), (b) Hp(3), and (c) Hp(0.07)

Fig ure 5. Dose ac cord ing to dis tance be tween the ICRUsphere and the ra di a tion source in us ing 2 mm tung stenshield ing de vice: (a) Hp(10), (b) Hp(3), and (c) Hp(0.07)

re duced more rel a tively. For the skin sur face dose, itwas con sid ered that as the dose was mea sured at ashal low point of 0.07 mm depth into the ICRU sphereand the num ber of pho tons ab sorbed and scat tered in -side of the sphere was less than that of the lens anddepth doses, it was mea sured higher. As a re sult ofmea sur ing doses ac cord ing to dis tance be tween theICRU sphere and the ra di a tion source, there was a ten -dency that as the dis tance in creased, the dose de -creased, and it was found that the re duced dose ra tioac cord ing to shield thick ness and by ra di a tion sourceswas dif fer ent, re spec tively. Namely, it is con sid eredthat as the dis tance from the ra di a tion source in -creases, the dose de creases from the in verse square ofthe dis tance. In sev eral pre vi ous ra di a tion stud ies onnu clear med i cine work ers, it was re ported that the ef -fect of shield ing was dif fer ent due to dif fer ences inwork en vi ron ments and as for ra di a tion eval u a tion,var i ous er rors such as un der es ti ma tion or over es ti ma -tion of doses might oc cur de pend ing on the wear ingsites and types of do sim e ter [11,12]. As a method tocom ple ment these er rors, a sim u la tion per formed incom puter vir tual space, an ideal con di tion, has beeneval u ated as one of the use ful tools able to re duce var i -ous er rors [13,14]. In the sim u la tion of Work ing Pack -age 4 un der the ORAMED Pro ject and other stud ies, itwas men tioned that the thick ness of any shield ing de -vice han dling 99mTc should be at least 2 mm of tung sten [15-17]. In this study, sim i lar re sults were shown andad di tion ally, the ef fect of the shield ing de vice wascom pared con sid er ing phys i cal char ac ter is tics byradionuclides. As a re sult, it seems that in case of otherradionuclides such as 67Ga and 111In, an in creased ap -pli ca tion of the shield ing de vice is nec es sary by theirphys i cal char ac ter is tics in spite of the lower ap pli ca -tion fre quency. This study is sig nif i cant in that it iden -ti fies the ef fec tive ness of sy ringe shields and per sonaldose ten dency through sim u la tion test ing forradionuclides cur rently used in gen eral di ag no sis ofnu clear med i cine and pro vides ba sic data con cern ingra di a tion pro tec tion of nu clear med i cine work ers.

CON CLU SION

As the re sults of the test on sy ringe shieldsthrough a Monte Carlo sim u la tion, it was iden ti fiedthat the skin sur face dose of nu clear med i cine work erswas rel a tively higher and there were dif fer en ti ateddose re duc tion ef fects by radionuclides ac cord ing tothe thick ness of sy ringe shield used. Ac cord ingly, onthe ba sis of these re sults, it is rec om mended that nu -clear med i cine work ers do not over look ap pli ca tion ofthe sy ringe shield and ra di a tion to pro tect their handsand it is also nec es sary to in crease the thick ness of theshield ing de vice to pro tect against ra di a tion sourcessuch as 67Ga and 111In. It is con sid ered also that a studyfor proper shield ing thick ness should be done in the

fu ture. In ad di tion, it is con sid ered that work ers should shorten the time re quired in han dling the shield ing de -vice through sim u la tion train ing and skills im prove -ment and al ways be mind ful of tak ing all nec es sarypre cau tions to pro tect against per sonal ra di a tion ex po -sure through oblig a tory ap pli ca tion of shield ing de -vices and wear ing of proper pro tec tive gear.

AU THOR CON TRI BU TIONS

MCNPX sim u la tions and data pro cess ing weredone by Y.-I. Cho un der the su per vi sion of J.-H. Kim.Dis cus sions re gard ing this pa per were held with J.-H.Kim and C.-S. Kim. The writ ing of the manu script, in -clud ing fig ures and ta bles, were done by Y.-I. Cho.

REF ER ENCES

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[6] Yeong Seon, K., et al., The Use ful ness Eval u a tion ofRa di a tion Shield ing De vices in PET Scan Pro ce dures, Ko rean So ci ety of J Nu clear Med i cine Tech nol ogy, 14(2010), 2, pp. 65-76

[7] Blunck, Ch., et al., Ra di a tion Pro tec tion inInhomogeneous Beta-Gamma Fields and Mod el lingof Hand Phan toms with MCNPX, Ra di a tion Pro tec -tion Do sim e try, 134 (2009), 1, pp. 13-22

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[10] Faw, R. E., Ken neth Shultis, J., Ra dio log i cal As sess -ment: Sources and Doses, Amer i can Nu clear So ci ety,La Grange Park, Ill., USA, 1999

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Y.-I. Cho, et al.: Eval u a tion of Sy ringe Shield Ef fec tive ness in Han dling ...162 Nu clear Tech nol ogy & Ra di a tion Pro tec tion: Year 2015, Vol. 30, No. 2, pp. 158-163

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[15] Ferrari, P., Sans-Merce, M., Carnicer, A., Main Re -sults of the Monte Carlo Stud ies Car ried Out for Nu -clear Med i cine Prac tices within the ORAMED Pro -ject, Ra di a tion Mea sure ment, 46 (2011), 11, pp.1287-1290

[16] Mariotti, F, Gualdrini, G., Ex trem ity Do sim e try Prob -lems Dur ing the Han dling of Radionuclides Sy ringesin Nu clear Med i cine: A Monte Carlo Ra di a tion Trans -port Sim pli fied Ap proach, Ra di a tion Mea sure ment,46 (2011), 4, pp. 430-435

[17] Cho. Y.-I., et al., An Eval u a tion of Ef fec tive ness onTech ne tium-99m Sy ringe Shield, Pro ceed ings, Sym -po sium – Ko rea Con tents As so ci a tion, 2014, pp.431-432

Re ceived on April 21, 2015Ac cepted on June 6, 2015

Y.-I. Cho, et al.: Eval u a tion of Sy ringe Shield Ef fec tive ness in Han dling ...Nu clear Tech nol ogy & Ra di a tion Pro tec tion: Year 2015, Vol. 30, No. 2, pp. 158-163 163

Jong-In ^O, ^ang-Su KIM, Jung-Hun KIM

PROCENA EFEKTIVNOSTI ZA[TITE [PRICEVAPRI RADU SA RADIOFARMACIMA

Ciq ovog rada je procena efektivnosti i za{tite od zra~ewa kod {priceva saradionuklidima i procena li~nog doznog ekvivalenta simulacijom radionuklida kori{}enih udijagnosti~koj nuklearnoj medicini. Kako bi se procenio odnos izme|u doze, koja zavisi odrastojawa izme|u izvora zra~ewa i ICRU sfere, i debqine za{titnog materijala, za rastojawe prikome tehni~ar odeqewa nuklearne med i cine mo`e slu~ajno do}i u kontakt sa radioaktivnimizvorom uzeto je rastojawe 0-30 cm prema debqini za{titnog materijala, ~ime se fiksira polo`ajICRU sfere. Za procenu doze, mereni su Hp(10), Hp(3) i Hp(0.07) na specifi~nim dubinama u ICRUsferi. Uo~eno je da je doza na povr{ini ko`e tehni~ara visoka, da se doza mewa u zavisnosti oddebqine za{titnog materijala i da se za{titni efekat smawuje za neke radioaktivne izvore kao{to su 67Ga i111In, te je za ove radioizotope potrebno pove}ati debqinu za{titnog materijala.Zakqu~eno je tako|e da je ubudu}e potrebno izvr{iti detaqnu studiju debqina za{titnihmaterijala.

Kqu~ne re~i: ICRU sfera, za{tita od zra~ewa za {priceve, li~ni dozni ekvivalent, ..........................radionuklid