- Original Article
- Open Access
Less radiation in a radiology department than at home
© The Author(s) 2011
- Received: 24 September 2010
- Accepted: 27 January 2011
- Published: 15 February 2011
To compare the total work-related radiation dose in our department of radiology with the dose in Dutch residences, taking x-ray radiation, external natural radiation and radon into account.
Annual doses due to exposure to x-rays and external natural radiation were derived from the measured personal dose equivalent [Hp(10)] of 144 workers. Additionally, departmental 222Rn concentrations were assessed over 1 year.
The departmental radon concentration was 5 ± 1 Bq/m3, the personal dose equivalent due to external natural radiation 0.32 ± 0.10 mSv/year, considerably lower than the average Dutch residential values of 13.5 Bq/m3 and 0.88 mSv/year. As a consequence, working results in a lower dose than being at home as long as the x-ray-induced personal dose equivalent is lower than 1.25 mSv/year, which was the case for 131 of the 144 radiological workers, as well as for the whole group on average.
Working in our x-ray department results in a reduction in the collective effective dose, not an increase. The worldwide average radon concentration of 40 Bq/m3, much higher than in the Netherlands, and the large decrease potentially achieved by the high ventilation rates common in hospitals, suggest that even considerably higher reductions are possible in other countries.
- Radiation dosimetry
- Occupational exposure
- Natural radiation
- Healthy worker discussion
- Optimisation of protection
Working in a radiology department is commonly associated with an increased radiation dose due to exposure to x-rays. However, differences in natural radiation at work and at home should also be considered. Two main sources of natural radiation are relevant in this respect, radon progeny and external radiation, with the latter of terrestrial and cosmic origin .
Radon (222Rn) occurs in the decay chain of 238U . As a noble gas, it can exhale from soil and building materials. 222Rn has short-lived non-gaseous decay products that tend to adhere to ambient aerosols. The concentration of the progeny in air is a balance between formation and removal by ventilation, decay and deposition. After inhalation, the alpha-emitting decay products readily settle in the airways of the lung, contributing heavily to the effective dose. External gamma radiation mainly comes from the daughter nuclides of the primordial radionuclides 238U and 232Th, and from 40K . Cosmic radiation at ground level has its origin in interactions of high energy particles from space with elements in the atmosphere . It is attenuated by building materials, with transmission factors ranging from close to unity for wooden constructions to 0.3 for large multi-storey apartments . Amazingly, data on the exposure caused by natural radiation are missing in nearly all fields of professional activity except mining .
Workers in radiology shield themselves against scattered x-rays by wearing protective clothing. The protection factor, which is the ratio between the unshielded personal dosimeter reading Hp(10) due to x-rays and the shielded person’s effective dose, depends on x-ray tube voltage, apron thickness and the use of a thyroid collar and is typically within the range of 10 to 100 [4, 5]. The inverse, the so-called dose conversion factor (0.01–0.1 mSv/mSv), is also often used.
Because the apron protection factor is so high, a relatively small decrease in natural radiation or radon concentration in the department might “compensate” for a typical occupational x-ray exposure. We therefore decided to quantify the radon concentration and the level of natural external and occupational radiation in our department. By comparing with residential values from a recent national survey, the difference between the natural radiation dose at work and at home could be estimated and weighed against the occupational x-ray dose.
Our university hospital is a large six-storey concrete building with the department of radiology centrally located on the fourth floor. Floors consist of 30-cm-thick concrete, with inner walls of gypsum board. Walls of x-ray rooms and barriers in front of operator desks in the department are shielded with 2 mm of lead or lead-equivalent glass. As a consequence, unless in the direct neighbourhood of an exposed patient, the level of scattered radiation is generally negligible.
In 2008 the department employed 144 radiological workers (radiologists, residents and radiographers). On a yearly basis about 150,000 x-ray procedures are performed, of which about 5,500 are interventions. Nuclear medicine studies and cardiological interventions are done in other departments.
222Rn and Hp(10) measurements
At various locations (reporting room, bucky room, CT operator room, canteen, waiting area) within the department, solid-state nuclear track-etch 222Rn detectors (Gammadata Mätteknik, Uppsala, Sweden) were suspended from the ceiling at a height of about 2 m. Additionally, in two air ventilation channels the incoming and outgoing air was monitored, as was the air in the unventilated basement of the hospital. The exposure time was 1 year. The results were compared with the data of a recent Dutch survey, covering about 1,000 newly built houses in the period 1994–2003 .
External exposure was monitored using thermoluminescence dosimeters (TLDs). In the Netherlands a single dosimeter is used, worn at the height of the chest on the shirt or the outside of protective clothing. These obligatory dosimeters contain two detectors of Mg, Ti doped lithium-fluoride and are issued on a 4-weekly basis by NRG (Nuclear Research and consultancy Group, Arnhem, the Netherlands). Their readings are indicated as Hp(10)Reading and they cover the year 2008. Gammadata Mätteknik and NRG, who also took care of the read out, are certified for their services by the respective national authorities. The devices used for measuring the radon concentration and Hp(10) were identical to those applied in the national survey [6, 7]. Systematic differences therefore are thought to be negligible.
Effective and collective (effective) doses
As some workers are hardly exposed to x-rays, the readings of the personal dosimeter can also be used to estimate the dose in the department due to the external natural radiation, Hp(10)Nat_work. To keep the analysis manageable only two groups of workers of (beforehand) unknown size were assumed: one group that merely received external natural radiation, and one that was additionally exposed to x-rays. The number of exposed persons in the background-only group was modelled with a delta-function, that in the group exposed to both background and x-rays with an exponentially decreasing function. The inherent spread in TLD readings was taken into account by convoluting these two functions with a suitable Gaussian. In a least-squares fit procedure to the low-dose part of the dose distribution actually observed all parameters characterising the two functions and the Gaussian were obtained . The “position” of the (convoluted) delta function is Hp(10)Nat_work.
Conversion factors and constants used in the calculation of the effective dose
Conversion of 222Rn concentration to effective dose
nSv/(Bq h m-3)
Equilibrium factor 222Rn progeny
Total hours per year
Fractional working time (1,752 h year-1)
Conversion of Hp(10) external natural radiation to effective dose
Apron protection factor [Hp(10)x-rays /effective dose]
When is the dose at work lower than at home?
After finding that both the level of radon and external gamma radiation were considerably lower within the department than in dwellings, we estimated the personal x-ray dose equivalent that can be incurred without the effective dose becoming higher than it would be at home. To this purpose ΔE in Eq. 4 was set to zero, and the equation was solved for Hp(10)x-rays.
In countries where the obligatory dosimetry is performed with two dosimeters, one above and one below the apron, the following procedure might be followed to find the break-even exposure: Calculate ENat_work and ENat_home using Eq. 3. Any combination of dosimeter readings that results in an effective dose Ex-rays equal to (ENat_home − ENat_work) corresponds to a break-even exposure. Ex-rays can be calculated from the two dosimeter readings with the algorithm that applies for the configuration in which the dosimeters are worn.
It seemed of interest to broaden the scope of our findings beyond our own hospital. To enable an estimation of a break-even Hp(10)x-rays in other institutions, the following assumptions were made: (1) In a region with a given geology, all buildings have the same basic radon concentration, namely that of homes. (2) The radon concentration scales with the inverse of the ventilation rate. The ventilation rate is defined as the volume of air that enters a room per hour divided by the room volume. Assuming a value for the ratio of the ventilation rate in a hospital and a dwelling, an estimate of a regional Hp(10)x-rays that undoes the protection against natural radiation at work can be calculated. Note that residential radon concentrations as required in this model are widely available.
222Rn concentration measured in the hospital
Air intake for ventilation, from roof
3 ± 1
7 ± 1
5 ± 1
Basement of hospital
26 ± 10
Protective clothing had a Pb-equivalent thickness of 0.25 or 0.35 mm and normally included thyroid protection. Tube voltage during occupational exposure was nearly always below 100 kVP. A conservative estimate of the apron protection factor under these conditions is 10 mSv/mSv [4, 5]. Because of part-time employees, average working hours corresponded to 86% of a full-time job (thus PTF = 0.86 in Eq. 3).
The average annual personal dose-equivalent Hp(10)x-rays was calculated according to Eq. 1 from the NRG readings and the local background as 0.44 ± 0.11 mSv; the maximum was 11.6 mSv. The collective annual personal dose equivalent for Hp(10)x-rays was 63 mSv. The annual collective occupational effective dose due to x-rays (Ex-rays) was 11.5 mSv; in this calculation Eq. 2 was used, and the results of the individual workers were summed. These low values show that current protection programs work well. The net collective effective dose ΔE for all 144 radiological workers was found to be just negative (−3.5 mSv; Eq. 4).
Due to the lower level of radon and external gamma radiation in the department, a worker can incur an Hp(10) due to x-rays of 1.25 mSv/year above the apron before the net effective dose becomes positive. In 2008 only 13 of the 144 radiological workers received a dose higher than their not-working equals. All 13 were involved in interventions or fluoroscopic studies. The dose savings due to radon and external radiation were about equal in our department.
In this study we included natural radiation in the calculation of the work-related radiation dose. Our data demonstrated that the effective dose for 131 of the 144 radiological workers was lower than it would have been if they had stayed at home, notwithstanding the low natural background in the Netherlands. Even the net collective effective dose was negative, implying an overall lower radiation dose at work than at home. To our knowledge this finding has not been reported before.
The low radon concentration in our department, a factor of 2 to 3 lower than in residences, is due to the high ventilation rate of 3–10 h-1, in combination with limited recirculation of the ventilation air. In the basement of the hospital, where active ventilation was absent, the radon concentration therefore increased substantially. In Dutch living rooms the air change rate is considerably lower than in the hospital, with an average value of 0.9 h-1 . Moreover, there is a large difference in the origin of the ventilated air: in Dutch living rooms, only about 60% comes directly from outside with a low radon concentration (around 3 Bq/m3). The remainder, however, mainly originates from the hallway with comparable concentrations to those in living rooms . A further point of difference between dwellings and our hospital is that the radiology department is well isolated from the basement, which suggests that contribution from the soil is negligible.
The low external natural dose rate is partly due to high attenuation of cosmic and terrestrial radiation by the 30-cm concrete floors of the hospital. Owing to self-absorption, the thickness of the concrete floors (which also contain some activity) does not seriously affect the gamma exposure rate [9, 10]. As all internal partition walls are made of gypsum panels, little extra contribution to the dose rate from these is expected . Moreover, some of the gypsum walls are clad with 2 mm of lead, also providing some additional shielding against background gamma radiation.
Our results on radon are qualitatively similar to those recently reported by Whicker and McNaughton . These authors found lower radon concentrations in offices than in homes, the ratio also being about 3, although the residential radon concentrations in Los Alamos (about 75 Bq/m3) were substantially higher than in the Netherlands. The authors also attribute the ratio of 3 to differences in the ventilation rate.
As studies similar to ours are lacking, conclusions for other hospitals can be tentative at best. The shielding of cosmic and terrestrial radiation might be comparable for other hospitals, provided they are large. However, the reduction in the radon dose could in principle be much higher. The worldwide average radon concentration is about 40 Bq/m3 , and because regulations require most hospital rooms to have high ventilation rates, the absolute reduction in radon concentration can be high. This will be illustrated by an example that applies to some of our workers. For the village of Eijsden, 6 km from the hospital, residential radon concentrations with an average of 46 Bq/m3 have been reported . Workers living in this village can have an annual x-ray dosimeter reading of 3.2 mSv without surpassing the dose they would receive in staying at home. In the light of the worldwide average of 40 Bq/m3, the result for Eijsden is likely to be more representative for many countries than that of the Netherlands as a whole. Here it might be emphasised that the break-even dose and the slope in Fig. 2 scale with the apron protection factor. We used a value of 10, a rather conservative estimate according to the study of Siiskonen et al. , who reported values between 44 and 258 for a 0.35 mm Pb apron and thyroid protection.
This study did not include the effect of the daughters of thoron (220Rn, the radon isotope in the 232Th series); however, taking this into account is bound to increase the difference between well ventilated and poorly ventilated spaces even further. Moreover, the ICRP  recently published a “Statement on Radon” announcing a revision of dose conversion coefficients: “The Commission advises that the change is likely to result in an increase in effective dose per unit exposure of around a factor of two.” Application of such new dose coefficients will strengthen the conclusions of this study even further.
Optimisation of occupational radiation protection in radiology was clearly successful. Slightly more than a century ago radiology started with radiation casualties, loss of fingers and other dreadful effects caused by normal (non-interventional) x-ray imaging; now the dose for the same work can be lower than that at home. This is something to cherish (but it should not reduce radiation awareness).
Our findings should be good news for all radiological workers, and especially for the small but non-negligible group of workers with radiophobia.
As occupational doses are low today, natural radiation at work and at home should be taken into account in risk assessments of radiological workers, which has not been done so far (see for example Yoshinaga et al. ).
Differences in natural radiation appear potentially relevant in the so-called healthy worker discussion , in addition to x-ray exposure and socio-economic factors that have an impact on health.
According to the ICRP  the principle of optimisation of protection applies to all exposure situations. As optimisation should take economic and societal factors into account, this could potentially imply that a worker’s radiation protection could most easily be further optimised at the worker’s home.
With respect to the level of “dose constraints”  for radiological workers, the “break-even dose” might possibly serve as a natural reference for a large group of radiological workers.
This article is distributed under the terms of the Creative Commons Attribution Noncommercial License which permits any noncommercial use, distribution, and reproduction in any medium, provided the original author(s) and source are credited.
- United Nations Scientific Committee on the Effects of Atomic Radiation (2000) UNSCEAR 2000 report to the general assembly, with scientific annexes. Vol. I, Annex B, exposures from natural radiation sources. United Nations, New YorkGoogle Scholar
- Miller KM, Beck HL (1984) Indoor gamma and cosmic ray exposure rate measurements using a Ge spectrometer and pressurised ionisation chamber. Radiat Prot Dosim 7:185–189Google Scholar
- Whicker JJ, McNaughton MW (2009) Work to save dose: contrasting effective dose rates from radon exposure in workplaces and residences against the backdrop of public and occupational regulatory limits. Health Phys 97:248–256View ArticlePubMedGoogle Scholar
- Siiskonen T, Tapiovaara M, Kosunen A, Lehtinen M, Vartiainen E (2007) Monte Carlo simulations of occupational radiation doses in interventional radiology. Br J Radiol 80:460–468View ArticlePubMedGoogle Scholar
- Netherlands Commission on Radiation Dosimetry (2008) Code of practice for personal dosimetry of professionals wearing protective clothing during radiological procedures. Report 19. Netherlands Commission on Radiation Dosimetry, DelftGoogle Scholar
- Bader S, Dekkers SAJ, Blaauboer RO (2010) Radiation dose in newly-built dwellings in the Netherlands. RIVM report 610790009/2010 (in Dutch). National Institute for Public Health and the Environment, BilthovenGoogle Scholar
- de Jong P, van Dijk JWE (2009) Analysis of the external dose rate in dwellings. VERA survey 2006. Report NRG-K5098/09.97299 (in Dutch). National Institute for Public Health and the Environment, BilthovenGoogle Scholar
- ICRP (1997) Publication 74: conversion coefficients for use in radiological protection against external radiation. Annals of the ICRP, volume 26/3. Elsevier Science, OxfordGoogle Scholar
- de Jong P, van Dijk W, van der Graaf ER, de Groot TJ (2006) National survey on the natural radioactivity and 222Rn exhalation rate of building materials in the Netherlands. Health Phys 91:200–210View ArticlePubMedGoogle Scholar
- de Jong P, van Dijk W (2008) Modeling gamma radiation dose in dwellings due to building materials. Health Phys 94:33–42View ArticlePubMedGoogle Scholar
- Albering HJ, Hoogewerff JA, Kleinjans JC (1996) Survey of 222Rn concentrations in dwellings and soils in the Dutch Belgian border region. Health Phys 70:64–69View ArticlePubMedGoogle Scholar
- ICRP (2009) Statement on radon. International Commission on Radiological Protection, ref 00/902/09. http://www.icrp.org/icrp_radon.asp. Accessed September 23, 2010
- Yoshinaga S, Mabuchi K, Sigurdson AJ et al (2004) Cancer risks among radiologists and radiologic technologists: review of epidemiologic studies. Radiology 233:313–321View ArticlePubMedGoogle Scholar
- ICRP (2007) Publication 103: the 2007 recommendations of the ICRP. Annals of the ICRP, volume 37/2-4. Elsevier Science, OxfordGoogle Scholar