Safe transport of radioactive materials in Egypt

Radat.

Pergamon

Phy. Chem. Vol. 44, No. l/2. pp. 181~185.1994 Elsevier Science Ltd. Printed in Great Brilain

0969-806X/94 $6.00+ 0.00

SAFE TRANSPORT

OF RADIOACTIVE EGYPT

MATERIALS

IN

RIFAAT M. K. EL-SHINAWY Radiation Protection Department, Nuclear Research Centre, Atomic Energy Authority, Cairo, Egypt Egypt the national regulations for safe transport of radioactive materials (RAM) are based on the Internationl Atomic Energy Agency (IAEA) regulations. In addition, regulations for the safe Abstract-In

transport of these materials through the Suez Canal (SC) were laid down by the Egyptian Atomic Energy Authority (EAEA) and the Suez Canal Authority (SCA). They are continuously updated to meet the increased knowledge and the gained experience. The technical and protective measures taken during transport of RAM through SC are mentioned. Assessment of the impact of transporting radioactive materials through the Suez Canal using the INTERTRAN computer code was carried out in cooperation with IAEA. The transported activities and empty containers, the number of vessels carrying RAM through the canal from 1963 to 1991 and their nationalities are also discussed. The protective measures are mentioned. A review of the present situation of the radioactive wastes storage facilities at the Atomic Energy site at Inshas is given along with the regulation for safe transportation and disposal of radioactive wastes

international recommendations laid down by IAEA (IAEA, 1990). The national regulations for the safe transport of RAM is based on the IAEA regulations. In addition, regulations for safe transport of RAM through the Suez Canal were laid down by the Egyptian Atomic Energy Authority (EAEA) and the Suez Canal Authority (SCA) (SCA, 1964, 1977). These national regulations are always kept up to date in accordance with the IAEA regulations to increased knowledge and accommodate the experience gained by the different authorities concerned.

INTRODUCTION Radioactive materials (RAM) are very useful and in many fields. A large number of packages containing RAM were transported all over the world by all means of transport. In Egypt the Presidential Decree Number 288 issued in 1957, regulates the activities of the Atomic Energy including, import, export, production, uses . etc. Also the law 59 issued in 1960 regulates the radiation protection aspects for open and sealed sources. International regulations for the safe transport of RAM, IAEA safety series number 6 (SS l985), have evolved with the No. 6; IAEA, development of nuclear energy programmes in many countries following the World War II (W W II). The first edition of SS No. 6 was issued in 1961 and revised in 1965, 1967, 1973 and 1985. National and international regulations have been established for packing and safe transport of all potentially harmful materials to protect man and his environment. RAM are among those hazardous materials. Shipments of RAM will increase in the future, as more nuclear power plants will come on line which in turn results in more radioactive wastes along with other applications such as medical, industrial and research. It was expected in the United States that a total activity of 8.45 x IO” m Ci (31.27 x IO” Bq) will be transported during 1985 (Swindell. 1978). These materials must be prevented from spreading outside the packaging in which they are transported and the external radiation outside the package must be reduced to acceptable levels. All RAM are transported, by all modes of transport (road, rail, sea and air), in accordance with the applied

TRANSPORT THROUGH I-HE SUEZ CANAL In Egypt, studies were made by the EAEA and the SCA to establish the regulations and the recommendations for the safe transport of RAM through the vital and important waterway, the Suez Canal. Permission is granted to carry radioactive materials, through the Canal, after supplying complete informations and documents concerning the radioactive shipment (El-Shinawy and Abdel Malik, 1980). Also full and clear details of the different loads, nature and number of consignments, radioactivity levels, weight of each shipment etc., are to be presented to the SCA and the EAEA together with copies of the above mentioned documents. Escort officers from EAEA inspect on board; they validate the relevant documents and examine the load, carry on the local radiation survey, check the protective measures, make sure that they are good and approve them before the vessel is permitted to proceed to the port of entry (Port-Said 181

182

RIFAAT M. K. EL-SHINAWY Table

I. Number

of vessels carrying

radioactive

materials

passmg through

the Suez Canal (1963-1991)

Year Port Port-Said SW2 Total

I963m 1979

I980

1981

1982

1983

1984

1985

1986

1987

1988

1989

I990

1991

204 197 391

40 27 67

55 36 91

59 52 III

65 50 II5

70 55 I25

47 51 98

46 56 102

46 45 91

38 39 77

54 55 109

56 58 114

46 47 93

or Suez) and to take matters:

a decision

in the following

-Authorizing the vessel to enter the port and transit the Canal. -Handling of other goods inside and outside the vessel. -Authorizing the vessel to make repairs in the port and to take supplies. The number of vessels of different nationalities, carrying radioactive materials on board and crossing the Canal during the period from 1963 to 1991 was 391 vessels with an average of 39 vessels per year (El-Shinawy and Abdel Malik, 1980; El-Shinawy, 1991). On the other hand the number of vessels crossing the Canal during the period from 1980 to 1991 was II93 vessels with an average of 99 vessels

Table 2. Vessels of different nationalities

per year as shown in Table I. Table 2, gives the different nationalities of vessels crossing the Suez Canal with radioactive shipments on board from 1963 to 1985. The total activity transported on board vessels through the Suez Canal in the period from 1963 to 1991 for different radionuclides and the number of empty packages and containers were tabulated as shown in Table 3. It was noticed that most of the vessels carrying natural concentrates and ores passing through the Canal from Suez to Port-Said (were loaded from Asian and South African ports), while most vessels carrying enriched uranium and manufactured isotopes used for different applications, passing through the Canal from Port-Said to Suez were loaded from U.S., Canadian and European Ports.

passing through the Suez Canal with radmactive 1963mOct. 1985 Transit

Nationality Australian Belgian Bengladeshian Burmese Chinese Damsh Dutch Egypttan English French Greek Holland Indian Indonesian Iranian Iraqian ltallan Japanese KWtWl Kwaltlan Liberian Malaysian NWVeg1all Pakistan1 Panamanian Phihppmo Polish Romanian Saud1 Arabian Singaporean South African Spamsh Swedish SWISS USA USSR YugoslaWin Total

1963-1979

I980

1981 3

1982

I983

I984

I

I

-

_

2 _

3 I7

5 19

6 25

4 20

7 20

2

2

5 I _~ I I

3 I 5 I

I I 7 2

4 5

I 4 I9 22

4

25 3

2 I 6 I0

I 5 IS

I 6 x

29 4 I 2 6 I

31 7 I I 6 I

26 2 2 2 I

I

_ 33

9

6

I I

4

2

_~ 2

4

I

I I

II 4

67

2 , I h

7

,

I

I

4

3

6

I I 2

I

4

2 I

2 3

II5

I25

_

391

1985

-_ _ 2 6 I2 31 4 I 4 5 -

3

5 x IO

on board from

year

4

4 II 70 I56 23 7 I9 6

shipments

VI

III

9x

I83

Safe transport of radioactive materials in Egypt Table 3. Activity and number of empty containers transported through the Suez Canal (1963-1991) Total activity Year 1963-1967 1975-1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1978 I990 1991

mCi 2.60 2.80 5.85 7.665 5.724 5.635 7.016 16.229 7.09 5.79 4.74 3.77 8.55 3.40

x x x x x x x x x x x x x x

Empty containers (EC)*

Rq IO’ 108 IO6 IO’ IO’ IO’ IO’ IO’ IO” IO” IO’ IO’ lob 106

9.62 x 10.36 x 21.76 x 28.361 x 21.180 x 20.851 x 25.958 x 60.049 x 26.23 x 21.42 x 17.53 x 13.95 x 31.64 x 12.59 x

IO” IO” IO” lOI4 lOI lOI lOI lOI lOI5 lOI 10’0 IO” IO” IO”

20 35 26 47 80 558 229 87 I6 2 5 5 234

The INTERTRAN computer code (IAEA, 1983) was used to predict the radiological risks resulting from the transport of radioactive materials through the Suez Canal under both normal and accidental situations (Sabek et al., 1988). The results indicate that there has been a considerable increase in the transport of RAM through the Canal since 1980. The average collection dose per year was found to be 4.5 man-rem which is negligible if the high population density within the Suez Canal zone is considered. The radiological risks calculated from actual impact data were found to be lower by a factor of lo6 than those calculated from default input data. This can be attributed to the low accident probability in the Suez Canal compared with that in the open sea.

*EC, is the container which had previously contained radioactive materials. TRANSPORT It is worth mentioning that during the period from 1963 (start date of the transport of RAM through the Suez Canal) till 1985, only one accident involving small amounts of radioactivity was recorded. On 9th December 1981 a collision took place between M/V Garnet, Panamian flag, and M/V Mola Venture, Liberian flag, nearby the wave breaker at the Port-Said area. As a result of the collision, M/V Garnet was sunk. According to the loading list and the Suez Canal transit permission, issued by the EAEA, the ship was carrying two small packages containing radioactive material (strontium-90, 5 mCi each) (El-Shinawy, 1981). At that time, the necessary radiation protection measures were taken by the competent authorities in Egypt. In August 1985, the EAEA was informed that the salvage operation of the vessel would start and was asked to take the necessary steps and radiation protection measures for picking up these two sources out of the lower hold number four. Water and snail samples were collected from this hold and radioassayed at the Radiation Protection Department Laboratories. The results showed that no radioactivity above background was detected. After picking up the packages out of the water; it was found that they consisted of two muddy wooden boxes 40 x 20 x 20 cm. The condition of the boxes was influenced by the long time under water, making the wood easy to damage. Only one metal label for radioactivity was still fixed on one side of each box. Tests confirming the existence of radioactive materials, and free surface contamination were carried out. Also, the two containers were subjected to detailed inspection procedures and the results showed that the radioactive sources still existed in their original closed form. These two containers were cleaned, repacked in one wooden box and relabelled according to the national and international regulations for safe transport of radioactive materials and transported to the country of origin (El-Shinawy and Hassib, 1985). This means that the regulations and recommendations currently used for the safe transport through the Suez Canal are almost satisfactory.

WITHIN THE NUCLEAR CENTER (NRC)

RESEARCH

Inside the NRC, the irradiated samples were transported from the reactor building, as requested, to the Isotope Production Division (IPD) of the Nuclear Chemistry Department. The number of these irradiated samples which were transported in the period from 1964 till October 1985 is illustrated in a form of a histogram as shown in Fig. 1. From this figure, it is clear that 1587 samples of different activity levels, depending upon the irradiation time, were transported with an average of 72 samples per year. The highest number of irradiated samples was observed in 1965 as 320 samples, while the lowest number was observed in 1982 as 17 samples only. At the time of transport a transport certificate (El-Shinawy and Abdel Malik, 1980) with all the necessary information for safe transport, was issued in duplicate by the Health Physicist in charge. One copy of the certificate was kept by the transport worker and the other was delivered to the IPD for their records.

TRANSPORT

OUTSIDE

THE NRC

This includes: (a) transport of radioisotopes from the IPD to the Distribution Center (DC) at Dokki; (b) transport of radioactive materials from Cairo International Airport (CIAP) to the DC at Dokki and then to the different users; and (c) from Alexandria Port to different places. (a) From IPD to DC at Dokki After processing of the irradiated samples in the IPD the produced isotopes were transported in a special truck to the DC. The total amount of activity as well as the number of packages are given in Table 4 for the period from 1963 to 1979 and from 1980 to October 1985. Transport certificates were issued by the health physicist in charge at the time of transport (ElShinawy and Abdel Malik, 1980). The first one was affixed to the opposite sides of each package while the second certificate was delivered to the receiver.

RIFAATM. K. EL-SHINAWY

184 500

r

197n

1965

Fig. 1. Number

(6) From CIAP

1975

to DC at Dokki

TRANSPORTATION

Port to different places

and number

of packages transported (1963-0~1. 1985)

from IPD to DC at Dokki

19X@-1985

1963-1979 Productmn period isotope I All P CR CZi Na Number of packages Average/y

mCi 5.609 0.601 0.509 0.568 0.506 0.280

x x x x x x

r&I

Bq IO4 IO4 104 IO’ IO’ IO1

20.75 2.22 1.88 2.10 1.87 I .04 886 82

OF RADIOACTIVE WASTES

The site for the solid radioactive waste storage facilities (SRWSF) was chosen within the hot zone at the south east of the Atomic Energy Authority (AEA) at Inshas (Abdel Malik et al., 1991). There are five facilities for solid radioactive waste and contaminated foodstuff. The solid radioactive waste collected from different laboratories (inside and outside NRC) is packed in suitable containers or in polyethylene bags. Radiation levels and all information about the transported waste are recorded on a special tag prior to transport to the SRWSF in accordance with IAEA regulations for the safe transport of RAM SS No. 6. Complete radioactive waste transport and storage certificates (RAWTC and RAWSC) were issued at the time of transport and storage operations.

Large radioactive sources used for medical. research and industrial applications are always transported by sea. Most of the imported large sources were transported via Alexandria Port. During the period from 1965 to 1976 and 1990, 13 sources were transported from Alexandria to Cairo under special protection and physical security arrangements as Table 4. Activity

Production

shown in Table 6. A transport certificate was issued at the time of loading from Alexandria and delivered to the receiver at the time of destination.

The total activity transported from CIAP to the DC at Dokki as well as the number of packages are presented in Table 5 for the periods from 1965 to 1979 and from 1980 to 1985. Most of these radionuchdes are not produced at the IPD of the Chemistry Department in the NRC and were therefore imported from West Germany and England. At the time of loading of these packages at CIAP, a tiansport certificate was issued, one copy was delivered to the receiver at the time of destination, while the other was kept with the transport worker. (c) From Alexandria

19x5

1980

of the irradiated samples transported from the reactor building to the Isotope Center inside the Nuclear Research Center (19641985).

x x x x x x

IO” IO” IO” IO” IO” IO”

Bq 4.15 x IO” 0.37 x 109 0.96 x IO”’

1.122 x 104 0.10 x 102 0.26 x IO’

105 18

Safe transport

of radioactive

materials

Table 5. Total activity and number of packages transported from

185

in Egypt

CIAP

to DC

at

Dokki (196sOct.

1985)

Year

1965-1979

1980

1981 Total activity in

Isotope I-131

32,060

-

I48

c-14

I9

Zn-65

63

s-35

89

Fe-59

5883

Te-99

27,177

8 8

3097 91,467 x IO9

Au-198 h-192

-

4107

P-32

56,684

x IO’

x IO9

15,170 x I09

Xe-I33 number

65

42

1869

280

I5 I9

75,332

x IO9

x IO9

-

1905

93

-

370

59,200 1028

81

51

296, I85 56

247,900

Kr-85 NP/Y* Kits

198.357

-

-

133,200

x ”

188,404

-

TI-201

*NP,

96,866

37 -

Am-241

I6

65,266 -

93

Ce- I44

56 I9

47,508

499,500

3352 69,597

I78

16

29,230 -

75, I88

Co-60

399

51,005

-

-

4

-

1036

II8

K-42

1758

93

-

259

75,968

Ca- I37

222

4 93

5554

Mn-54

100,825

307

4

-

55

H-3

70,855

41

1850

I44

107

Q-90

9102

30

-

1280

Ca-45

1985

specified

17,427

14

1984

-

422

Na-22

1983

Bq x IO’ otherwise

4841

3345

CT-5 I

1982

1776

-

1850 69

153

338

349

770

3x5

I302

1551

of packages.

Table

6. Transported applications

radioactive

from

Radioactive

material

Year

*co

1965

mco

1969

sources for medical,

Alexandria

Port

to different

research and industrial places as indicated

Activity (mCi

x IO’) 20 80

Receiver Cancer

Insritute

Regional

Isotope

Centre

60

Atomic

E. Establishment

1971

“Co MC0 MC0

5

Atomic

E. Establishment*

1974

"'CS

20

Badrawi

28.6

Radiation

Technology

Centre

Radiation

Technology

Centre

30.3

Radiation

Technology

Centre

60.0

Cancer

45.0

Tumour

35.0

Cancer

I969 1971

1974

ace

1916

“Co

I917

"'CS MC0 “Co “Co MC0

1977 1977 1979 1990 *To

Harwell,

England

5

4300

989.4

American

Radiation

University

Private

Clinic

Institute Institute Institure Technology

Centre

for irradiation.

REFERENCES Abdel-Malik W. E. Y., Ibrahim A. S., El-Shinawy R. M. K. and Gomaa M. A. (1991) Radioactive Waste Storage Facilities of Atomic Energy Authority Egypt. Technical Report Submitted to the Competent Authorities. El-Shinawy R. M. K. (1981) Technical Report Concerning Radioactive Materials on Board of the Sunken Vessel M/V GARNET at Port-Said Area. Submitted to the Competent Authorities. El-Shinawy R. M. K. (1991) Technical Report Concerning Transport of Radioactive Materials Through Suez Canal. Submitted to the Competent Authorities. El-Shinawy R. M. K. and Hassib G. M. (1985) Technical Report Concerning Salvage Operalion of the Sunken Vessel M/V GARNET and Picking up the Radioactive Maferials. Submitted to the Competent Authorities. El-Shinawy R. M. K. and Abdel Malik W. E. Y. (1980) Transporl of Radioactive Consignments Through and Within Arab Republic of Egypt. A.R.E. AEE./Int. Rep. No 93.

(1983) INTERTRAN. A System for Assessing the Impact from Transporting Radioactive Materials. TECDOC-287, IAEA, Vienna. IAEA (1985) (As Amended 1990) Regulations for the Safe Transport of Radioactive Materials, Safety Series No. 6. IAEA, Vienna. Sabek M. G., Aly A. I. M., Abdel-Aal M. M., El-Sinawy R. M. K., El-Ghamry M., Hassib G. M. and Hammad F. H. (1988) Use of INTERTRAN code for risk assessment of radioactive materials being transported through the Suez Canal. Proc. Int. Conf. Rad. Prof. Nucl. Energy, organized by IAEA and held in Sydney. SCA (1964) Suez Canal Authority, Arab Republic of Egypt, Transit Department. Circular No 4/3 B,-406012, Ismailia. SCA (1977) Suez Canal Authority, Arab Republic of Egypt. Rules of Navigation, Appendix for Vessels Carrying Dangerous Cargo. Ismailia. Swindell G. E. (1978) The transport of radioactive materials. IAEA Bull. 20, No. 5. IAEA