The investigation of the impact of new ICRU95 operational quantities on the reference fields at JAEA-FRS in terms of the type-testing of the dosimeters

Abstract

ICRU has published Report 95 jointly with ICRP in 2020 proposing new operational quantities. This will impact dosimetry in radiological protection especially for the dosimeters’ performance of energy and angular dependence. To test the performance in detail, it is important to establish radiation reference fields corresponding to the new quantities. The Facility of Radiation Standards (FRS) of the Japan Atomic Energy Agency is a comprehensive Secondary Standard Dosimetry Laboratory in Japan equipped with various reference fields for x-, gamma-, beta-, and neutron radiations. We evaluated the conversion coefficients in terms of the new quantities in the FRS fields and demonstrated type-testing of commercial dosimeters based on the new quantities, which made it possible to conduct the performance tests of the dosimeters in terms of the new quantities at the FRS. Significant differences between the conversion coefficients for new and existing operational quantities were found for some FRS fields, especially for x-ray fields with low energies and large angles, beta-ray fields on the operational quantities for eye lens monitoring, and neutron radiation fields. The H* and H_p responses of the dosimeters were found to be affected at low-energy photon region accordingly.

Keywords

ICRU95 Operational quantities Reference field Type-testing

1. INTRODUCTION

Dosimetry for external radiation protection is accomplished by using dosimeters designed and calibrated to measure operational quantities. Calibration and performance tests of dosimeters for radiation protection purposes are conducted by calibration laboratories. The Facility of Radiation Standards (FRS) of the Japan Atomic Energy Agency (JAEA) is such a calibration laboratory equipped with various radiation reference fields. For over four decades, the FRS has served as a comprehensive Secondary Standard Dosimetry Laboratory (SSDL) in Japan, providing calibration and type-testing services for dosimeters.

In 2020, ICRU/ICRP published a joint report, Report 95 (ICRU, 2020), which proposed a new definition of the operational quantities. The change of operational quantities will impact the dosimeter performances, especially energy and angular dependences. Therefore, type-testing of the dosimeters in terms of radiation energy and angle of incidence is particularly important to consider how to cope with this change. However, no reference field to test the dosimeters in terms of the new quantities was available in Japan prior to this study.

This study aims to enable the performance testing of the dosimeters in terms of the new quantities at the FRS and to investigate the impact of the new quantities on the FRS reference fields.

2. METHODOLOGY

The calibration and type-testing procedures for the dosimeters such as calibration phantoms remain unchanged by the introduction of the new quantities as stated in the ICRU report (ICRU, 2020) except for the values of the conversion coefficients from measurement standard to the new quantities. The conversion coefficients must be determined for each calibration field, taking into account the different energy distributions in each field. The conversion coefficients regarding the new quantities have not yet been evaluated for the Japanese calibration fields including the FRS. To evaluate the impact of the new quantities, this study established the FRS reference fields corresponding to the new quantities in the following two steps: (1) evaluating the conversion coefficients in terms of the new quantities for the FRS reference fields and (2) demonstrating the conduct of performance tests of commercial dosimeters in terms of the new quantities.

2.1. JAEA-FRS

Various reference radiation fields equipped at the FRS are traceable to the national primary standard of the National Metrology Institute of Japan, the National Institute of Advanced Industrial Science and Technology (NMIJ/AIST). The FRS is also accredited as an exclusive JIS (Japan Industrial Standards) testing laboratory for radiation protection monitoring instruments based on ISO/IEC 17025 (ISO/IEC, 2017). The reference fields selected to evaluate the conversion coefficients in this study are summarised in Table 1.

Table 1.
The FRS reference fields used in this study.

Type of reference fields Apparatus Radiation quality Mean energy (MeV)

X-ray fields X-ray generator ISO narrow-spectrum series 0.02–0.26

gamma-ray fields Collimated irradiator S-Cs and S-Co 0.66 and 1.25

High-energy gamma-ray field 4MV Van-de-Graaff accelerator R-F using ¹⁹F(p, αγ)¹⁶O reaction 6.2

beta-ray fields BSS2 (Ambrosi et al., 2007) ⁹⁰Sr/⁹⁰Y, ⁸⁵Kr, and ¹⁴⁷Pm 0.8, 0.24, and 0.06

Thermal neutron field Graphite pile with a ²⁵²Cf source 2.5 × 10⁻⁸

Moderated neutron fields Graphite pile moderated ²⁴¹Am-Be 2.1–2.2

D₂O moderated ²⁵²Cf 0.55

Fast neutron fields Radioactive source above the grating floor ²⁵²Cf and ²⁴¹Am-Be 2.3 and 4.4

Monoenergetic neutron fields 4MV Van-de-Graaff accelerator ⁴⁵Sc(p,n)⁴⁵Ti 0.008 and 0.027

⁷Li(p,n)⁷Be 0.144, 0.250, and 0.565

³H(p,n)³He 1.2 and 2.5

²H(d,n)³He 5.0

³H(d,n)⁴He 14.8 and 19

Type of reference fields	Apparatus	Radiation quality	Mean energy (MeV)
X-ray fields	X-ray generator	ISO narrow-spectrum series	0.02–0.26
gamma-ray fields	Collimated irradiator	S-Cs and S-Co	0.66 and 1.25
High-energy gamma-ray field	4MV Van-de-Graaff accelerator	R-F using ¹⁹F(p, αγ)¹⁶O reaction	6.2
beta-ray fields	BSS2 (Ambrosi et al., 2007)	⁹⁰Sr/⁹⁰Y, ⁸⁵Kr, and ¹⁴⁷Pm	0.8, 0.24, and 0.06
Thermal neutron field	Graphite pile with a ²⁵²Cf source	2.5 × 10⁻⁸
Moderated neutron fields	Graphite pile moderated ²⁴¹Am-Be	2.1–2.2
D₂O moderated ²⁵²Cf	0.55
Fast neutron fields	Radioactive source above the grating floor	²⁵²Cf and ²⁴¹Am-Be	2.3 and 4.4
Monoenergetic neutron fields	4MV Van-de-Graaff accelerator	⁴⁵Sc(p,n)⁴⁵Ti	0.008 and 0.027
⁷Li(p,n)⁷Be	0.144, 0.250, and 0.565
³H(p,n)³He	1.2 and 2.5
²H(d,n)³He	5.0
³H(d,n)⁴He	14.8 and 19

2.2. Evaluation of the conversion coefficients

The ICRU report (ICRU, 2020) presented a new set of operational quantities, i.e., H* and H_p for whole-body monitoring, D´_lens and D_{p lens} for eye lens monitoring, and D′_{local skin} and D_{p local skin} for skin monitoring, providing conversion coefficients $[h (E)]$ from fluence to the proposed new quantities for radiations with monoenergetic energy E.

The conversion coefficients $h_{R}$ for the FRS reference fields R were derived from the following equation for photons and neutrons:

h_{R} = \int_{0}^{E_{\max}} h (E) [\frac{d Φ (E)}{d E}] d E

(1)

where

d Φ (E) / d E

is the fluence spectrum for the reference field R. The fluence spectra of the reference fields of the FRS were evaluated by measurements or calculations. Fig. 1 shows the examples of photon spectra obtained from the measurements. As for

h (E)

for photons, values assuming secondary charged-particle equilibrium (CPE) were used because calibration and type-testing are conducted under the CPE conditions in the reference fields. For

h (E)

, interpolation was applied for not given E in the ICRU report (ICRU, 2020), using a 4-point (cubic) Lagrangian interpolation formula. For beta-ray fields, the

h_{R}

were directly calculated according to the new definitions of operational quantities (Fig. 2) using the Monte Carlo code PHITS 3.100 (Sato et al., 2024) as beta-ray fields are not generally monodirectional.

Fig. 1.

Examples of the unfolded photon fluence spectra. (a) S-Cs field, (b) R-F field.

Fig. 2.

Calculation geometries for beta-ray reference fields. (a) D_localskin, (b) D_lens.

2.3. Type-testing of commercial dosimeters

The ionisation chamber (IC) survey metre (AE-133B, Applied Engineering Inc.) and optically stimulated luminescence (OSL) personal dosimeter (Nagase Landauer Inc.) were type-tested in terms of the new quantities using the aforementioned photon fields. The detector of the IC survey metre is a parallel plate-type ionisation chamber with a volume of 60 cm³. It is capable of measuring not only H*(10) but also H´(3) and H´(0.07) with or without additional caps in front of the detector. The OSL dosimeter consists of four elements, which are mainly composed of Al₂O₃:C with different filter combinations, and H_p(10) and H_p(0.07) can be measured using a dose calculation algorithm.

3. RESULTS AND DISCUSSION

3.1. Conversion coefficients

The conversion coefficients for the FRS photon fields (N-40, N-60, N-80, N-100, N-120, N-150, N-200, N-250, N-300, S-Cs, S-Co, and R-F) were evaluated. The differences from those reported by Behrens and Otto (2020) were observed, with variances of up to 3%. The obtained conversion coefficients were then compared with those for the present quantities (ICRU, 1985, 1993) as shown in Fig. 3. The observed divergence from the unity has indicated the larger impact at lower energies especially for H_p. Additionally, the differences tended to increase at large angles of radiation incidence. These could lead to an unacceptable over- or under-response of a dosimeter especially in the low-energy region. To mitigate the impact, the following solutions can be considered: recalibration with an appropriate radiation quality, changes to the dose calculation algorithm or G(E) function (Moriuchi and Miyanaga, 1966), changes to the filter, and redesign of the dosimeter. Because there is no dosimeter with a perfect response, a case-by-case approach will be necessary. To determine which of the above methods is practically best for a dosimeter, it is important to obtain the dosimeter's response using these established fields.

Fig. 3.

The ratios of conversion coefficients to the new operational quantities (OQs) to those of the corresponding present OQs for the FRS photon fields. (a) H_p/H_p(10), (b) D_{p lens}/H_p(3), (c) D_{p local skin}/H_p(0.07).

The conversion coefficients for the FRS beta-ray fields of ⁹⁰Sr/⁹⁰Y, ⁸⁵Kr, and ¹⁴⁷Pm were evaluated. The differences from those reported by Behrens (2021) were mostly within 5%, but larger discrepancies were observed for D_{local skin}(⁸⁵Kr; $α$ = 75°) (29% smaller), D_{local skin}(¹⁴⁷Pm; $α$ = 60°) (10% smaller), and D_lens(⁹⁰Sr/⁹⁰Y; $α \geq 30 \circ$ ) (14%–26% smaller), where $α$ is angle of incidence. These differences arise from the calculation conditions. For instance, only a single eye model was located at the reference point of the calibration field in our study (Fig. 2), whereas the model of head with double eyes was employed in the literature. The D_{p local skin} conversion coefficients for the beta-ray fields were almost unchanged between the new and the present quantity except for 16%–27% smaller values for ¹⁴⁷Pm (Fig. 4a), although the density and thickness of the target layers to calculate conversion coefficients have changed. In contrast, the values at 0° and angular dependency were significantly affected for D_{p local skin} (Fig. 4b).

Fig. 4.

The ratio of conversion coefficients to the new OQs to the present OQs for the FRS beta-ray fields. (a) D_{p local skin}/H_p(0.07), (b) Angular dependence of D_{p lens}/H_p(3) for ⁹⁰Sr/⁹⁰Y field.

The conversion coefficients for the FRS neutron fields listed in Table 1 were evaluated and then compared with those for the present quantities. As shown in Fig. 5, the conversion coefficients were largely changed over the entire region in neutron energy. In addition, the values of the new quantity were smaller than those of the present quantity by around 60% for 144 and 250 keV at 0°, while the values of the new quantity were larger than those of the present quantity by 18% for 5 MeV at 0°. It should be noted that angular dependence was also affected especially below the 100 keV region.

Fig. 5.

The ratio of conversion coefficients to the new OQs to the present OQs for the FRS neutron fields.

3.2. Type-testing of commercial dosimeters

The response characteristics of the IC survey metre and OSL personal dosimeters were investigated using the above fields. The IC survey metre was over-responded for photons in terms of H* below 40 keV, whereas the D´_lens and D´_{local skin} responses remained unchanged compared to the corresponding responses for the present quantities over a range from 30 keV to 6 MeV and for incident angles from 0° up to 60° as shown in the Fig. 6. As for the OSL dosimeter, H_p response for photons increased at lower energy and higher angle of radiation incidence, while D_{p local skin} response was not affected (Fig. 7).

Fig. 6.

Energy and angular responses of the IC survey metre. (a) H* response, (b) D'_lens response, (c) D'_{local skin} response.

Fig. 7.

Energy and angular responses of the OSL dosimeter. (a) H_p energy response, (b) H_p angular response, (c) D_{p local skin} response.

4. CONCLUSIONS

In summary, the conversion coefficients regarding the new operational quantities were evaluated for a wide variety of reference fields with different radiation types and energies at the FRS. This enables testing the dosimeters’ characteristics in terms of the new quantities. To investigate the impact on the new quantities, performance tests were demonstrated for commercial photon dosimeters widely used in Japan using established FRS fields. This indicated the H* and H_p responses below 40 keV, and the H_p response at lower energy and higher angle of radiation incidence for the tested dosimeters would need some improvements.

Footnotes

ACKNOWLEDGEMENTS

This study was supported by a grant from the Nuclear Regulation Authority, Japan.

References

Ambrosi

Buchholz

Helmstädter

, 2007. The PTB Beta Secondary Standard BSS 2 for radiation protection. J. Inst. 2, P11002.

Behrens

, 2021. Conversion coefficients from absorbed dose to tissue to the newly proposed ICRU/ICRP operational quantities for radiation protection for beta reference radiation qualities. J. Radiol. Prot. 41(4), 871

Behrens

Otto

, 2020. Conversion coefficients from total air kerma to the newly proposed ICRU/ICRP operational quantities for radiation protection for photon reference radiation qualities. J. Radiol. Prot. 42(1), 011519

ICRU. 1985. Determination of Dose Equivalents Resulting from External Radiation Sources. ICRU Report 39. International Commission on Radiation Units and Measurements. Bethesda, MD.

ICRU. 1993. Quantities and Units in Radiation Protection Dosimetry. ICRU Report 51. International Commission on Radiation Units and Measurements. Bethesda, MD.

ICRU. 2020. Operational quantities for external radiation exposure. ICRU Report 95, J. ICRU 20(1).

ISO/IEC. 2017. General Requirements for the Competence of Testing and Calibration Laboratories. ISO/IEC 17025:2017

Moriuchi

Miyanaga

, 1966. A method of pulse height weighting using the discrimination bias modulation. Health Phys. 12(10), 1481–1487

Sato

Iwamoto

Hashimoto

, et al., 2024. Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33. J. Nucl. Sci. Technol. 61(1), 127–135.