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Chapter 6 Radiation Control

  1. Specific Applications of Legislation

As a special feature in application of radiation protection legislation to NPPs, it is required that two laws, the “Reactor Regulation Law'1 and the "Industrial Safety and Health Law" be simultaneously observed as mentioned above. As things are now, many activities of daily facility checks, maintenance tasks, and periodical inspection tasks particularly at NPPs are carried out by workers of contractors, and the responsibility of reactor establishers for radiation protection of the persons engaged in work in controlled areas (radiation workers) in accordance with the "Reactor Regulation Law" and the management responsibility of contractors employing the workers provided in the "Industrial Safety and Health Law" overlap (Figure 6.2.1).

According to these two laws, both an establisher and a contractor are responsible for the same worker in the same facility, but it is irrational for both to redundantly perform monitoring and surveillance of the work environment and dose control of workers for the same work activity in the same area of a NPP

Therefore, for practical control of contracted works, the establisher fulfills its responsibility to comply with the provisions of the "Reactor Regulation Law" by confirming the radiation protection measures to be carried out by contractors in accordance with the "Industrial Safety and Health Law", and in drawing up the contract agreements. The establisher is also responsible for the specifications for the radiation control which specify that the contents of radiation control are prepared and shown to the contractors beforehand to clarify sharing of responsibility, and that the contracted work activities are performed according to these specifications.

For those work activities, the establisher confirms as appropriate that the contractors are performing the radiation control according to the specifications and gives advice and guidance as necessary. Additionally, it is specified that the contractors record the results of their radiation control and submit them to the establisher after completion of their work. Ulis procedure ensures contractors clearly recognize the legislative policy to perform radiation control for their own work is their own

responsibility, and it also clearly positions radiation protection within the integrated labor safety management (prevention of electric shock, falls, etc.).

Utility Company A Contractor H Utility Company B Nuclear Power Station Manufacturer Nuclear Power Station

Industrial Safety and Health Law

Figure 6.2.1 Regulatory framework according to the “Reactor Regulation Law and the “Industrial Safety and Health Law”

  1. Radiation Sources at npPs

  1. Actual Conditions concerning Radiation Sources

The fundamentals of radiation protection are to eliminate any concern about radiation protection by providing satisfactorily functioning radiation safety facilities at plants. However, from a practical standpoint and taking into consideration economical and socially rational aspects,, a part of radiation protection is left to human activities in addition to the facilities. In order to work safely in the environment that requires radiation control, first of all, it is important to have full knowledge on radiation fields (radiation sources) in the facilities.

At a NPP, radiation sources are fission products produced mainly in fuel during nuclear reactor operation and corrosion products produced by activation of metals in the reactor structural materials, etc., but their quantities or behavior are not uniform and therefore, radiation levels due to the sources at any part of the nuclear reactor system are different and depend on each nuclear reactor.

For reduction of personnel doses, prevention of contamination, and reduction of radioactive materials discharged to the environment, the following measures are taken into consideration:

  1. To contain generated fission products in fuel

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rods;

  1. Not to introduce metallic corrosion product into a reactor (to make the amount of activated products as small as possible);

  2. To efficiently collect generated radioactive materials by the clean-up system;

  3. To control radioactive materials so that they do not move or deposit within the systems; and

  4. To safely remove radioactive materials prior to overhaul inspection of components.

In the design of a NPI’ concentrations of fission products and corrosion products in the reactor water are evaluated and the shielding design etc. is done according to the concentrations; but recently, significantly improved fuel integrity has almost entirely eliminated release of fission products into the reactor water. Actually, the concentration of fission products in the reactor water of operating BWRs is approximately 10-6 times the design basis and the major radiation sources of the main steam system are activated products with short half­lives, such as 16N, I90,13N, 18F.

The radioactive nuclides existing in the primary coolant of light water reactors are shown in Table 6.3.1.

The nuclides that should be controlled for radiation protection are mainly activated products, and the major nuclides among them that contribute to radiation doses are the long half-life and high energy gamma ray emitters, “Co (from stainless steel, Stelite etc.) for BWRs and “Co (from nickel- based alloy (Inconel ®) used as the SG heat­transfer-tube material) for PWRs.

Table 6.3.2 shows example nuclides contributing to the surface dose equivalent rate of the BWR and PWR primary system components, and Table 6.3.3 shows the contents of the original sources (mainly stable cobalt and nickel) in the steels and other metal materials.

The surface dose equivalent rates at the BWR and PWR primary system components arise as the result of a complicated involvement of generation rates of the activated products “Co or “Co in a reactor and their deposit mechanisms onto components. The surface dose equivalent rates generally increase until approximately 4 EFPY (Effective Full Power Years) and then, reach their equilibrium, but they change depending on the water chemistry

control situations and measures taken for the water chemistry control (Figure 6.3.1).

Dose reduction measures are important for NPPs together with safety and reliability improvements; therefore, multilateral dose reduction measures have been adopted particularly at Japanese NPPs. Whenever new-generation plants have started their operations, excellent dose reduction results have been achieved.

Trends in collective doses at the first periodic inspection of BWR and PWR plants are shown in Figure 6.3.2. Some of the latest plants have their annual total dose below 0.2 man-Sv.

Also for the preceding reactors, measures have been taken including improvements of corrosion resistance and composition of steel materials as originating sources, control of corrosion products to be introduced into a reactor that become radiation sources, removal and decontamination of radiation sources, shielding of radiation sources, and improvement of work practices, all of which have resulted in a significant dose reduction.

Moreover, efforts to reduce piping dose equivalent rate by zinc injection into the feedwater and condensate system have been made. This approach suppresses deposition of ionic state “Co by having the oxide film on the piping surface take in zinc from DZO (Depleted Zinc Oxide) in which the abundance ratio of &'Zn is reduced in order to avoid an increase in dose equivalent rate due to “Zn. The effect of reduction of piping dose equivalent rate by application of this technology to BWR plants in and outside Japan has been confirmed, but, as a secondary effect, there have been some cases showing performance degradation of the primary loop recirculation system (increase in flow path resistance due to precipitation of zinc compound (ZnCr2OJ on jet pumps), which means that the application should be studied on a case-by-case basis depending on the water chemistry control of each plant.

Major measures for dose reduction at old and new plants are shown in Table 6.3.4.

NSRA, Japan

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Chapter 6 Radiation Control

Table 6.3.1 Radioactive nuclides in LWR primary coolant

Nuclide

Half life

Type of decay

Products by decay

Activation of coolant

13n

9.96

min

0~

16O (p, a)

I6n

7.13

sec

0", y

16O (n, a )

17n

4.16

sec

0 “, n

I7O (n, a )

18p

109.8

min

0 +, EC

18O (p, n)

I9O

26.9

sec

13 y

18O (n, y )

Activation of dissolved or introduced impurities

3H

12.3

y

0-

6Li (n, a)

24Na

15.02

hr

0 ", y

23Na (n, y), 27A1 (n, a)

41Ar

Activation of structural materials

1.83

hr

0 > y

40Ar (n, y)

51Cr

27.70

day

EC, y

50Cr (n, y )

54Mn

312.5

day

EC, y

54Fe (n, p)

56Mn

2.579

hr

0 ’> y

5JMn (n, y ), 56Fe (n, p)

i9Fe

44.6

day

0 , y

58Fe (n, y )

58Co

70.8

day

EC, 0+, y

S8Ni (n, p)

60Co

5.271

y

0", y

59Co (n, y )

64 Cu

12.70

hr

EC, 0 ~ 0 +, y

63Cu (n, y )

65Zn

244.1

day

EC, y

64Zn (n, y )

76As

26.3

hr

0 ", y

75As (n, y )

95Zr

64.0

day

0 , y

54Zr (n, y )

9SNb

35.0

day

0 ", y

95Zr ( 0 ")

"Mo

66.0

hr

0 ", y

98Mo (n, y )

io°mAg

250.4

day

0 ", y

i09Ag(n, y)

i24Sb

60.2

day

0 ", y

I23Sb (n, y )

134Cs

2.062

y

0 ", y

i33Cs (n, y )

[Sources]

  1. C. H. Hogg & L D. Weber, Symposium on Radiation Effects on Metals and Neutron Dosimetry, American Society for Testing Materials, Philadelphia, pp. 133-140,1963

  2. Y. Murakami et al., Radiation Data Book, Chijin Shokan, 1982, [Core data section]

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Table 6.3.2 Contribution of nuclides to the dose equivalent rate of piping of the reactor coolant system

“Co

^Co

51Mn

59Fe

Others

BWR

Nuclide composition (%)

37

10

48

5

-

Contribution to dose rate (%)

60

7

29

4

-

PWR

Nuclide composition (%)

11 to 37

63 to 85

Very small

Very small

Very small

Contribution to dose rate (%)

32 to 68

32 to 65

Very small

Very small

-

[Source] Atomic Energy Society of Japan, Special Committee for Research of High Temperature Water Chemistry, "Water Chemistry Control and Fundamental Technology of Nuclear Power Plants"

Table 6.3.3 Materials constituting the primary system components

Material

Major application

Elemental composition (%)

Ni

Fe

Cr

Co

Zr

600-type nickel-based alloy

(Inconel 600)

SG heat transfer tube

75

8

15

O.lto 0.02

-

Stainless steel

Piping etc.

9 to 12

Balance

17 to 19

0.1 to 0.2

-

Zircaloy-4

Fuel cladding tube

-

0.2

0.1

< 0.002

Balance

Stelite

Valve and control rod drive mechanism

2

2

28

62

-

Carbon steel

Piping etc.

<0.2

Balance

<0.2

0.001 to 0.01

-