Solid cancer incidence other than lung, liver and bone in Mayak workers: 1948–2004

Abstract

Background:

Cancer incidence in the Mayak Production Association (PA) cohort was analysed to investigate for the first time whether external gamma-ray and internal plutonium exposure are associated with raised incidence of solid cancers other than lung, liver and bone (other solid cancers).

Methods:

The cohort includes 22 366 workers of both sexes who were first employed between 1948 and 1982. A total of 1447 cases of other solid cancers were registered in the follow-up period until 2004. The Poisson regression was used to estimate the excess relative risk (ERR) per unit of cumulative exposure to plutonium and external gamma-ray.

Results:

A weak association was found between cumulative exposure to external gamma-ray and the incidence of other solid cancers (ERR/Gy=0.07; 95% confidence intervals (CIs): 0.01–0.15), but this association lost its significance after adjusting for internal plutonium exposure. There was no indication of any association with plutonium exposure for other solid cancers. Among 16 individual cancer sites, there was a statistically significant association with external exposure for lip cancer (ERR/Gy=1.74; 95% CI: 0.37; 6.71) and with plutonium exposure for pancreatic cancer (ERR/Gy=1.58; 95% CI; 0.17; 4.77).

Conclusion:

This study of Mayak workers does not provide evidence of an increased risk of other solid cancers. The observed increase in the risk of cancer of the lip and pancreas should be treated with caution because of the limited amount of relevant data and because the observations may be simply due to chance.

Much of what is known about the long-term carcinogenic effects of radiation exposure come from the Life Span Study cohort of the A-bomb survivors in Japan (Preston et al, 2007; UNSCEAR, 2008; Ozasa et al, 2012). The radiation dose received by these survivors was delivered acutely, primarily gamma-ray with a small neutron contribution. Long-term follow-up of the health of radiation workers in the nuclear industry is important to determine whether risk estimates derived from the A-bomb survivor studies are directly applicable to the lower protracted external and internal exposures experienced by workers. There are important statistical limitations within such studies, the number of people in the studies, the period of observations (follow-up) and the sizes of radiation doses received. If the number of people in a study is small and the radiation doses are low, then a study will have low power to detect and estimate raised cancer risk. Furthermore, there are also other potential uncertainties arising from confounding and other sources of bias in some studies. Despite such difficulties, studies on cohorts of radiation workers have provided important information on cancer risks (Cardis et al, 2007; Muirhead et al, 2009a). A study of the UK radiation workers has shown an association between exposure to external gamma rays and the incidence of solid cancer and leukaemia, consistent with risk estimates derived from the A-bomb survivor data (Muirhead et al, 2009a).

Studies of the radiation workers at the Russian Mayak Production Association (Mayak PA) have provided information on risks from external exposures and internal exposures from plutonium (Shilnikova et al, 2003; Sokolnikov et al, 2008; Azizova et al, 2012; Gilbert et al, 2013). These studies have demonstrated significant association between cancer and non-cancer diseases and exposure to internal plutonium and external gamma ray. Risks of morbidity from cancers of the lung, liver and bone – the organs of primary plutonium deposition – have been reported previously (Labutina et al, 2013). The focus of this paper is to present results for incidence of solid cancers other than those of the lung, liver and bone (here after referred to as ‘other solid cancers'), in relation to external and internal plutonium exposure among radiation workers in the Mayak PA cohort.

Materials and methods

The Mayak PA is the first and largest nuclear weapon-grade plutonium (²³⁹Pu) production plant in Russia and started operation in 1948. A substantial number of workers during the early period of operation were exposed to high levels of radiation from both external gamma-ray and internal alpha-particle irradiation from incorporated plutonium (²³⁹Pu) in body tissues.

Definition of cohort and follow-up

The cohort design, data collection and methods used to determine the vital status have been described in detail previously (Koshurnikova et al, 1999; Labutina et al, 2013). We summarise here some of the main aspects. In brief, the Mayak PA study cohort included 22 373 workers first employed in one of the main facilities (nuclear reactors, radiochemical production and plutonium production) during 1948–1982 and followed up to the end of 2004. Of these, seven workers were excluded from the study: two were diagnosed before the start of the follow-up and five were diagnosed with two first solid malignant neoplasms on the same date. Thus, the final study population comprised 22 366 workers.

The cancer registry was established by the SUBI Epidemiological laboratory (which continues to maintain it) jointly with Federal State Health Institution of the Central Medical sanitary Department of the Federal Medical-Biological Agency of Russia. Information was obtained from the medical records of oncology, postmortem services, as well as the archival data of the Mayak workers' polyclinic for the period from 1948 to 2004. The diagnoses were coded in accordance with the Ninth Revision of International Classification of Diseases, ICD-9 (WHO, 1977). Cancer cases were identified for workers who lived in the city at the time of diagnosis. The data completeness is restricted by the lack of diagnosed cases after workers migrate from Ozyorsk (this date terminates the follow-up period for a worker). The analyses of other solid cancer incidence data are based on first diagnosis but excluded non-melanoma skin cancers because of incomplete registration. Overall, 1447 other solid cancer cases were identified; among these, 0.7% of cancers (10 cases) reported were obtained from death certificates, whereas 5.5% of cases were diagnosed through autopsy findings. The majority of cases had morphological diagnosis (91.2%). Autopsies were carried out for about 30% of workers who had been diagnosed with cancer. In the first decades of Mayak PA operation, about 60% of cancer cases had postmortem or medico legal reports completed, but the current autopsy rate is 15% with such examinations more likely to be performed on workers who had higher levels of plutonium exposure.

Information on exposure to external gamma-ray and to internal plutonium

The analysis was performed using external and internal dose estimates from an updated dosimetry system, Mayak Doses-2008 (MWDS 2008) (Vasilenko et al, 2007; Khokhryakov et al, 2013). External radiation exposure to Mayak workers was mainly by gamma-ray from the reactor plant and monitored by the Mayak PA Radiation Protection Department using individual film badges with adjustment for energy and angular dependence of the detector. The measurements for cumulative external exposure in workers are expressed as the recorded operational quantity [Hp(10)], which is the personal equivalent dose at a tissue penetrating to a depth of 10 mm (ICRU, 1988), expressed as in Gy. Individual doses from external gamma-ray were available for the whole study cohort.

The main sources of internal plutonium exposure were from the Radiochemical and Plutonium production plants. All workers employed at the radiochemical and plutonium production plants were potentially exposed to internally deposited ²³⁹Pu and external gamma radiation. A small number of workers at the reactor plant have also been monitored for plutonium exposure but the rest of the reactor workers were assumed to have zero internal plutonium doses. However, information on internal exposures was available for only about 30% of the workers in the cohort because routine urine measurements did not begin until about 1970. Among workers monitored for plutonium exposure, absorbed dose to the liver was used as a proxy dose estimate, recorded in Gy. The internal doses from inhalation of ²³⁹Pu were estimated from plutonium concentration in urine samples using biokinetic models of the behaviour of plutonium in the body. The calculations took account of occupational history, solubility of inhaled plutonium aerosols and the smoking status of each worker (Khokhryakov et al, 2013). For those workers who were potentially exposed to plutonium, but had no direct measurements, six categories of potential exposure have been developed (Shilnikova et al, 2003), referred to as plutonium-surrogate indices, based on the workers' employment: (1) auxiliary and reactor plant workers hired between 1948 and 1982; (2) radiochemical plant workers hired between 1954 and 1982, main plutonium department workers hired between 1964 and 1982 and plutonium auxiliary department workers hired between 1959 and 1982; (3) plutonium auxiliary department workers hired between 1950 and 1958, radiochemical plant workers hired between 1948 and 1953 and main plutonium department workers hired between 1959 and 1963; (4) Plutonium auxiliary department workers hired between 1948 and 1949 and main plutonium department workers hired 1954–1958; (5) main plutonium department workers hired between 1950 and 1953; and (6) main plutonium department workers hired between 1948 and 1949. For this analysis, plutonium exposures of unmonitored workers were designated as low (plutonium-surrogate indices 2, 3 and 4) and high, to include workers employed in the main plutonium department between 1948 and 1958 (indices 5 and 6).

Auxiliary plant workers were excluded here because of data quality problems and the likely small impact on the risk estimates that their inclusion would provide.

Statistical methods

The data were analysed using the same methods as in previous studies of this cohort (Shilnikova et al, 2003; Sokolnikov et al, 2008; Labutina et al, 2013). The Poisson regression was used to test for an association between incidence from other solid cancers and exposure to both external gamma-ray using Hp(10) dose (Gy) and plutonium using internal liver dose (Gy). For each worker, person-years at risk were accumulated over time from the date of first employment at one of the main plants of the reactor, radiochemical or plutonium production plants of Mayak PA between 1948 and 1982 entry into the study to the date of exit from the study, which ended on the date of first cancer registration, date of death, date of leaving Ozyorsk, or the 31 December 2004, whichever was earliest. Tabulations of person-years at risk and other solid cancer incidence cases were created with the DATAB module of the EPICURE software (Preston et al, 1998). Data were cross-classified by gender, attained age (14 categories by 5-year age intervals), calendar year in 12 categories, age at first plutonium exposure in 4 categories, smoking status in 3 categories (unknown, nonsmoker and smoker), plant in 3 categories (nuclear reactors, radiochemical production and plutonium production), alcohol consumption in 6 categories, estimated cumulative external exposure in 8 categories (0, 0.05, 0.2, 0.5, 1, 2, 3 and 4 Gy) and estimated cumulative internal exposure in 7 categories (0, 0.0001, 0.025, 0.05, 0.1, 0.25 and 1 Gy) for internal cumulative dose. To allow for a latent period in a radiation effect, analyses were also performed using the cumulative external dose and internal liver dose lagged by 0, 5, 10, 15 and 20 years. Because of indications that some workers were monitored for plutonium as a result of suspected diseases, person-years were classified as unmonitored until 2 years following the first monitoring date (Sokolnikov et al, 2008; Gilbert et al, 2013). The data were fitted to the following model:

where λ₀ is the background cancer incidence rate in the absence of radiation exposure (dose=0) and depends on attained age (a), gender (g) and smoking status (sm); excess relative risk is the ERR modelled by combining separately ERR_ed due to external gamma-rays and ERR_id due to internal alpha-radiation for monitored workers; ERR_sur is the excess relative risk (RR) due to internal alpha-radiation for unmonitored workers in the radiochemical and plutonium production plants. More specifically the ERR was modelled as:

ERR=ERR_ed+ERR_id+ERR_sur

Allowance was made in the analyses to control for background factors affecting cancer risk using various parametric models by including covariates in the model as well as non-parametric models through stratification. The results from all of these models showed that attained age, gender and smoking status were the most important factors in modelling the background rates for other solid cancer incidence. However, the parametric approach produced a slightly better description of the background rates compared with the non-parametric approach, and this approach has also been used in previous analyses of Mayak cohort studies (Skolnikov et al, 2008; Gilbert et al, 2013). The final model for the baseline risks included a function of the gender-specific logarithm of attained age, the logarithm of attained age squared and gender-specific smoking status. Additional adjustment of the baseline model for year of birth cohort and calendar time, alcohol consumption, period of first employment or plant did not have any significant effect for the model.

Deviations from the linear model (Equation 1) are evaluated by fitting alternative model, for example, the linear-quadratic model is a dose–response model that measures the concavity of the dose–response relationship. Analyses were also conducted to evaluate factors that may modify the dose–response trend such as attained age, gender, age at first employment and so on. All the analyses here were carried out using the AMFIT module in the EPICURE (Preston et al, 1998). Likelihood ratio tests and likelihood-based confidence intervals (CIs) were reported. All P-values quoted were two-sided and a statistical significance level of 5% was used.

Results

The study cohort included 22 366 workers, of whom 5687 (25%) were females, first employed at one of the main plants during 1948 to 1982 and with a total of 535 932 person-years follow-up to the end of 2004. Table 1 summarises the characteristics of the study cohort. About half of the Mayak PA workers (55%) were first employed during the period of first production (1948–1958). At the end of the follow-up period, vital status was known for almost all cohort members (95.2%). About half of the workers had died (48%) and 41% of the workers had migrated from the city Ozyorsk at the end of 2004. Information on alcohol consumption was available for 78% of the workers. Most importantly, information on smoking status was collected for about 89% of the Mayak PA cohort members (Table 1).

Table 1. Characteristics of the Mayak PA worker's cohort first employed from 1948 to 1982 and followed up to 2004.

	Exposed to plutonium (monitored)a	No plutonium exposureb	Potential plutonium exposure (unmonitored)c	Total
Number of workers	6699d	5154	10 513	22 366
Females (%)	30	22	24	25
Number of person-years	256 866	1 179 698	161 097	535 932
Year of employment
1948–1958	3331	2979	5979	12 289
1959–1982	3368	2175	4534	10 077
Vital status (%)
Known	99.9	95.1	92.7	95.2
Alive	62.6	50.4	46.5	51.9
Dead	37.4	49.6	53.5	48.1
Untraced	0.1	4.9	7.3	4.8
Migrated	3.9	43.1	60.5	41.3
Plant
Reactor	260	5154	—	5414
Radiochemical	3537	—	5654	9191
Pu production	2902	—	4859	7761
Attained age
<55	1656	3258	8301	13 215
55–64	1754	754	1165	3673
65–74	2214	745	737	3696
75+	1075	397	310	1782
Age at hire
<20	2013	1346	3581	6640
20–24	2294	2030	3386	7710
25–29	1046	841	1412	3299
30+	1346	937	2134	4417
Smoking status
Nonsmoker	2911	1832	3767	8510
Smoker	3260	2761	5373	11 394
Unknown	528	561	1373	2462
Alcohol consumption status
Never drinkers	1448	1057	1945	4450
Drinkers	3912	3089	5919	12 920
Unknown	1339	1008	2549	4896
Mean external gamma Hp(10) dose in Gy (range)	0.62 (0–5.5)	0.44 (0–6.8)	0.38 (0–6.7)	0.51 (0–6.8)
Mean internal liver dose in Gy (range)e	0.31 (0–36)	—	—	0.31 (0–36)
Solid cancers other than the lung, liver and bone	759	290	398	1447

Abbreviation: PA=Production Association.

^aWorkers with internal dose estimates.

^bReactor workers exposed only gamma.

^cRadiochemical and plutonium plant workers who were unmonitored for internal dose.

^dOf those, 260 workers are from the reactor plant.

^eAmong exposed workers.

The mean cumulative external gamma H_p(10) dose was 0.51 Gy (0.54 Gy for men and 0.44 Gy for women), but the mean dose was substantially higher among cohort members who started to work between 1948 and 1958 (0.81 Gy), compared with those who started to work between 1959 and 1982 (0.15 Gy). A total of 3862 workers were exposed to more than 1 Gy, and 95 workers to more than 4 Gy. Among the plutonium-exposed cohort members, the mean cumulative liver plutonium dose was 0.31 Gy (0.24 Gy for men and 0.47 Gy for women). There were a total of 1447 cases (33% in females) of other solid cancers.

Figure 1 shows the mean annual exposure values for external H_p(10) dose and for liver dose from plutonium exposure. The gamma-ray dose decreased sharply after 1951 because of improvements in radiation protection, whereas the internal liver dose showed a slightly different pattern because of the long-term retention of plutonium in body organs. As explained previously, internal dose values were estimated on the basis of occupational history and urine measurements where available.

Figure 1.

The mean annual external H_p(10) dose from gamma-ray exposure (mGy), the internal liver dose from plutonium exposure (mGy) among workers by calendar year.

Risks from external gamma-ray and internal plutonium exposure

A total of 1447 other solid cancers were recorded for the 22 366 workers in the Mayak PA cohort. A statistically borderline significant relationship with cumulative external gamma dose was observed for other solid cancers as a group on the basis of a zero-year lag (ERR/Gy=0.07; 95% CI: 0.01; 0.15; P=0.06) after adjusting for age, gender and smoking status. Alternative lag periods of 5, 10, 15 or 20 years were used, but the resulting risk estimates did not change substantially. There was no statistically significant association for other solid cancers with internal liver dose for monitored workers (ERR/Gy=0.10; 95% CI: −0.02; 0.26, P=0.15) or plutonium-surrogate indices for unmonitored workers (P>0.5). The evidence for a trend with external dose became weaker and was not statistically significant after adjusting for internal dose for monitored workers (ERR/Gy=0.06, 95% CI: −0.01; 0.14, P=0.12), whereas the external dose findings were little changed after adjusting for unmonitored plutonium exposed among workers using the surrogate indices (ERR/Gy=0.07, 95% CI: −0.005; 0.15, P=0.07).

Figure 2 shows the external dose-category-specific estimates and the linear dose–response trend for other solid cancers. Having adjusted for internal exposure, the point estimates increase with dose category, although the RRs do not differ significantly from those at zero dose. Figure 2 also shows reasonable good agreement between a linear trend and exposure dose categories, but the external dose trend was not statistically significant. There was also no evidence of nonlinearity in the external dose response based on the linear-quadratic model (P>0.5) or when the data used were restricted to cohort members with external doses under 3 Gy (P>0.5).

Figure 2.

Relative risks of other solid cancer incidence in relation to external exposure categories and the linear trend (and 95% CI), having adjusted for internal exposure (based on 0-year lag).

Table 2 presents the ERR/Gy estimates for the modifying factors of interest for external dose response after adjusted non-radiation factors. The ERR/Gy increased with attained age and the greatest risk was observed in workers for ages 70 and older, but the differences were not statistically significant. There was also no indication of strong effect modification by gender, age at first employment, gender smoking status or plant.

Table 2. The ERR/Gy across categories of modifying factors of interest and relative risks (RR) by external dose categories for other solid cancers with adjustment for internal dose.

	Cases	Person-years	ERR/Gya (95% CI)	P-valueb
Gender:
Male	968	379 932	0.06 (−0.03; 0.16)
Female	479	156 838	0.11 (−0.03; 0.30)	0.41
Smoking status
Never smokers	604	223 846	0.04 (−0.07; 0.18)
Current smokers	766	263 613	0.06 (−0.03; 0.16)	0.18
Unknown	77	48 473	0.64 (0.03; 1.75)
Plant
Reactor	327	128 369	0.03 (−0.10; 0.17)
Radiochemical	650	221 595	0.07 (−0.01; 0.17)	>0.5
Plutonium plant	470	186 968	0.14 (−0.04; 0.37)
Attained age (years)
<50	296	370 393	−0.05(<0; 0.09)
50–54	383	91 269	0.02 (−0.1; 0.15)
60–64	467	54 145	0.10 (−0.05; 0.18)	0.08
70+	301	20 125	0.22 (0.08; 0.38)
Age at first hired (years)
<20	242	164 348	0.04 (−0.09; 0.19)
20–24	456	184 604	0.10 (0.01; 0.22)	>0.5
25–34	434	125 218	0.02 (−0.08; 0.14)
35+	315	61 761	0.07 (−0.06; 0.25)

Abbreviations: ERR=excess relative risk; CI=confidence interval.

^aBackground rates adjusted for age, gender and smoking status and based on 0-year lag period.

^bTest of homogeneity of the ERR/Gy across categories.

Table 3 gives RR estimates for various external gamma-ray dose categories (<0.2 Gy, 0.2–0.5 Gy, 0.5–1.0 Gy and >1 Gy) for other solid cancers as a group and the selected 16 individual cancer sites and the corresponding gender averaged ERR/Gy with 95% CIs. For the analysis of each specific cancer site, adjustments were made for attained age, gender and smoking unless otherwise indicated. The majority showed a positive dose–response relationship (11 out of 16), although the relationship was only significant for cancer of the lip (ERR=1.74, 95% CI: 0.37; 6.71, P=0.002) and borderline statistical significance for oesophagus (ERR=0.89, 95% CI: <0; 5.29, P=0.06) and stomach (ERR/Gy=0.15, 95% CI: −0.01; 0.39, P=0.07) with external dose, irrespective of whether adjustment was made for internal exposure or any of the plutonium-surrogate indices for unmonitored workers. However, no association was found for the other 12 sites with external exposures.

Table 3. Relative risk (RR), ERR/Sv and 95% confidence interval (CI) for selected cancer sites by cumulative external exposure from gamma-ray (based on 0-year lag period and background rates were adjusted for attained age, gender and smoking).

Cancer site (ICD-9 code)		<0.2 Sv	0.2–0.5 Sv	0.5–1.0 Sv	⩾1 Sv	Total (no. of female)	ERR/Sv (95% CI)	P-value
Solid cancers other than lung, liver, bone (140–154,156–161, 163–169, 171, 172, 174–199)	Cases RR (95% CI)	536 1.00	299 1.08 (0.94; 1.25)	227 1.06 (0.90; 1.24)	385 1.16 (1.01; 1.33)b	1447 (47)	0.07 (0.01; 0.15)	0.06a
Person-years at risk	—	272 834	101 958	70 004	91 134	535 932 (156,838)	—	—
Mean external gamma exposure	—	0.068	0.32	0.72	1.84	0.51 (0.44)	—	—
Lip (140)	Cases	6	7	4	18	35 (2)	1.74 (0.37; 6.71)	0.002b
	RR (95% CI)	1.00	2.13 (0.71; 6.39)	1.63 (0.45; 5.89)	4.93 (1.89; 12.9)b
Mouth, tongue, salivary gland and pharynx (141–149)	Cases RR (95% CI)	23 1.00	10 0.75 (0.36; 1.59)	7 0.67 (0.29; 1.58)	10 0.60 (0.28; 1.28)	85 (11)	−0.14 (NA)	0.24
Oesophagus (150)	Cases	6	5	4	15	30 (5)	0.89 (NA; 5.29)c	0.06a
	RR (95% CI)	1.00	1.43 (0.41; 5.02)	1.37 (0.34; 5.58)	2.80 (0.81; 9.59)
Stomach (151)	Cases	97	68	53	83	301 (56)	0.15 (−0.01; 0.39)d	0.07a
	RR (95% CI)	1.00	1.31 (0.96; 1.80)	1.33 (0.94; 1.87)	1.34 (0.98; 1.82)a
Colon (153)	Cases	63	27	22	32	144 (50)	−0.14 (NA)	0.23
	RR (95% CI)	1.00	0.83 (0.52; 1.30)	0.88 (0.54; 1.43)	0.81 (0.52; 1.25)
Rectum (154)	Cases	36	25	21	27	109 (37)	0.03 (−0.18; 0.38)	>0.50
	RR (95% CI)	1.00	1.36 (0.81; 2.27)	1.45 (0.84; 2.51)	1.16 (0.69; 1.94)
Gallbladder (156)	Cases	10	5	5	9	29 (12)	0.15 (−0.48; 1.72)	>0.50
	RR (95% CI)	1.00	1.05 (0.36; 3.11)	1.39 (0.47; 4.14)	1.64 (0.64; 4.18)
Pancreas (157)	Cases	21	14	15	21	71 (11)	0.14 (−0.16; 0.70)	0.25
	RR (95% CI)	1.00	1.13 (0.57; 2.23)	1.53 (0.78; 3.00)	1.32 (0.71; 2.45)
Larynx (161)	Cases	18	8	8	11	45 (4)	−0.12 (NA)	>0.50
	RR (95% CI)	1.00	0.72 (0.31; 1.67)	0.92 (0.40; 2.13)	0.78 (0.36; 1.68)
Female breast (174)w	Cases	54	21	14	18	107	0.21 (−0.08; 0.69)	0.24
	RR (95% CI)	1.00	1.23 (0.74; 2.05)	1.18 (0.65; 2.13)	1.19 (0.69; 2.04)
Uterus (179–182)w	Cases	33	12	4	18	67	0.35 (−0.07; 1.11)	0.12
	RR (95% CI)	1.00	1.10 (0.57; 2.14)	0.52 (0.18; 1.47)	1.81 (1.01; 3.23)
Prostate (185)m	Cases	13	17	9	31	70	0.16 (−0.12; 0.73)	0.27
	RR (95% CI)	1.00	1.82 (0.88; 3.75)	1.12 (0.48; 2.63)	2.04 (1.06; 3.91)
Bladder (188)	Cases	20	7	15	16	58 (4)	0.004 (NA)	>0.50
	RR (95% CI)	1.00	0.53 (0.22; 1.26)	1.41 (0.72; 2.76)	0.87 (0.45; 1.71)
Kidney (189)	Cases	33	16	16	20	85 (21)	−0.12 (NA)	0.49
	RR (95% CI)	1.00	0.86 (0.47; 1.57)	1.11 (0.60; 2.02)	0.86 (0.48; 1.52)
Brain and CNS (191-192)	Cases	19	12	8	9	48 (7)	−0.15 (NA)	0.19
	RR (95% CI)	1.00	1.17 (0.57; 2.43)	1.05 (0.46; 2.43)	0.78 (0.35; 1.76)
Thyroid (193)	Cases	10	8	2	9	29 (13)	0.40 (−0.24; 1.84)	0.22
	RR (95% CI)	1.00	1.93 (0.75; 4.94)	0.67 (0.15; 3.10)	2.16 (0.86; 5.47)

Abbreviations: ERR=excess relative risk; ICD=International Classification of Diseases; NA=not applicable; RR=relative risk, confidence intervals cannot be calculated because the model did not converge to a maximum likelihood solution; w=women only; m=men only.

^aStatistically borderline significant.

^bStatistically significant (P<0.05).

^cAdditional adjustment period of first employment and plant.

^dAdjusted for age, gender and alcohol.

Except for pancreatic cancer, there was no statistically significant trend for the other cancer sites with either internal liver dose among monitored workers or plutonium-surrogate indices for unmonitored workers. Of the 60 cases of pancreatic cancer among the male workers, 32 and 15 cases were among monitored and unmonitored plutonium workers, respectively. A significant positive association between internal plutonium exposure and pancreatic cancer was observed (ERR/Gy=1.35, 95% CI: 0.14; 3.74) after adjusting for age and gender. Additional adjustment for smoking status had little effect. The RR increased with increasing dose; the RR compared with the reference category of <0.001 Gy (38 cases) in categories 0.001–0.049 Gy (9 cases), 0.05–0.49 Gy (19 cases) and ⩾0.5 Gy (5 cases) were 1.19 (95% CI: 0.57; 2.46), 1.79 (95% CI: 1.01; 3.18) and 2.11 (95% CI: 0.81–5.47), respectively. The RR among workers with liver doses of above 0.05 Gy was twice that of workers with cumulative liver doses of <0.001 Gy. There was no evidence of any effect of the surrogate indices (based on 19 cases diagnosed among the unmonitored workers). Additional adjustment for surrogate indices for unmonitored workers or for external dose showed no substantial modifying effects on the overall ERR/Gy for the pancreatic cancer.

Discussion

Considering solid cancers other than lung, liver and bone cancers, a strong association has been reported previously between external dose and other solid cancers in mortality analyses of the Mayak cohort (Shilnikova et al, 2003). The current study of incidence data supports this finding from the mortality data, although the association with external dose was shown to be weak when adjusted for smoking status. Unlike the mortality analyses, the incidence analysis did not show a statistically significant effect for external dose after adjusting for internal liver dose, although the estimates from this study and the mortality data were nearly identical (Table 4). There was also no evidence of nonlinearity for the external dose response. In terms of plutonium exposure, the incidence data did not show any effect of internal exposures for other solid cancers as a group. This finding is not surprising as plutonium doses are delivered largely to the lung, liver and bone, with much lower doses to other organs. However, the mortality study of the Mayak cohort suggested a smaller but still statistically significant effect of internal exposure on the risk of death for these cancers (Shilnikova et al, 2003). The differences between the results of this study and those obtained from the mortality study (Shilnikova et al, 2003) can be attributed to the use of the revised dosimetry system MWDS-2008 in place of earlier systems using plutonium body burden and the inclusion of smoking adjustment and the extended follow-up period. It should also be noted that the previous mortality analyses were based on ‘archive' doses, whereas MWDS 2008 included corrections for energy and angular dependence for external gamma-radiation doses. In contrast to the mortality analyses, the incidence analyses excluded cancers that were diagnosed after migration.

Table 4. Comparison of estimates of the gender-averaged ERR/Gy (90% CI) for exposure to external dose for cancers in the Mayak cohort, NRRW, the 15-country nuclear worker study and the Japanese A-bomb survivors.

	Study period	No. of study population	Range of doses in Gy (mean)	No. of deaths or cases	ERR/Gy (90% CI)
Mayak PA workers studya
Incidence (0-year lag) (this study)	1948–2004	22 366	0–7 (0.5)	1447	0.06 (−0.001; 0.13)
Mortality (5-year lag) (Shilnikova et al, 2003)	1948–1972	21 500	0–>10 (0.8)	1062	0.08 (0.02; 0.12)
Third NRRW study (10-year lag)
Mortality Incidence (Muirhead et al, 2009a)	1955–2001	174 541	0–0.5 or more (0.025)	5118 8443	0.32 (0.02; 0.67)b 0.31 (0.05; 0.58)b
15-country nuclear worker study (10-year lag)
Mortality (Cardis et al, 2007)	1943–2000	407 391	0–0.5 or more (0.019)	3528	0.59 (−0.16; 1.51)b
Japanese A-bomb survivorsc (5-year lag)
Mortality (Ozasa et al, 2012)	1950–2003	86 611	0–4 (0.20)	10 929	0.42 (0.32; 0.53)
Incidence (Preston et al, 2007)	1958–1998	105 427		17 448	0.47 (0.40; 0.54)

Abbreviations: CI=confidence interval; ERR=excess relative risk; NRRW=National Registry for Radiation Workers.

^aBased on all solid cancers other than lung, liver, bone and non-melonama skin cancers.

^bBased on all solid cancers excluding lung and pleura cancer.

^cBased on solid cancers and survivors exposed at ages of 30 years or more, at an attained age of 70 years, 5 year. c: 95% confidence interval.

The International Agency for Research on Cancer (IARC) has carried out a combined analysis of mortality among nuclear industry workforces in 15 countries to provide greater precision in direct estimates of cancer risk (Cardis et al, 2007). In the UK, the third analysis of the National Registry for Radiation Workers (NRRW) examined mortality and incidence data among radiation workers (Muirhead et al, 2009a). These groups of radiation workers were exposed primarily to a protracted low-dose exposure from X-rays or gamma rays. In addition, in a study of 14 319 workers employed at the Sellafield plant of British Nuclear Fuels in the UK, cancer mortality and incidence were examined in relation to exposures to plutonium and external radiation (Omar et al, 1999). Table 4 shows estimates of the ERR/Gy from the current study and other radiation worker studies, together with results from analysis of the Japanese A-bomb survivors data. The risk estimates from the present study and the previous mortality analysis of other solid cancers are lower than the tabulated values from other studies, although the CIs from the Mayak studies overlap with those for the UK workers (Muirhead et al, 2009a) and the studies of 15-country nuclear workers (Cardis et al, 2007). However, the Mayak results are inconsistent with the Japanese A-bomb study; surprisingly, a lower estimate was obtained for this study as compared with that derived from the A-bomb survivors. The differences between these two studies are likely due to the small number of cases in the present study, the magnitude of radiation doses received (higher in the Mayak cohort) and/or the use of Hp(10) doses for the Mayak analysis, whereas the A-bomb data analyses involve estimates of organ dose to colon. The study of plutonium workers in the UK (Omar et al, 1999) did not find any association between cancers of any specific site, or all cancers combined, and cumulative plutonium and external radiation doses.

Sixteen individual cancer sites were evaluated in this study, and, as a consequence, there is an 80% chance of obtaining at least one statistically significant result even if no real effects exist. The site-specific results in this study showed a statistically significant association with radiation for cancer of the lip and pancreas for which no association with radiation was reported in previous studies. The paper by Preston et al (2010) also presents preliminary site-specific estimates on the basis of Mayak mortality data and also discusses general difficulties in evaluating site-specific risks including the problem of multiple testing.

Lip

This study provides evidence of a relationship with increasing cumulative exposure to external dose (ERR/Gy=1.74; 95% CI: 0.37; 6.71, P=0.002), but there have not been any previous reports of such an association. Additional adjustment for internal dose among monitored and also for unmonitored workers led to no change to the ERR/Gy. The RR increased with increasing external dose; the highest exposure category (1⩾Gy) was associated with a five-fold significantly higher risk of incidence compared with the reference category <0.2. However, we cannot rule out the possibility that this may reflect chance finding due to the small number of cases (35 cases). Although measured and unmeasured confounding factors may have influenced association of external exposure with lip cancer risk, we were able to control, in particular, cigarette smoking, but for UV-radiation exposure, it was difficult to obtain the information among workers.

Oesophagus

Having adjusted for age, gender, smoking, period of first employment and plant, this study suggested a weak association with external exposure (ERR/Gy=0.89, 95% CI: 0.001; 5.29, P=0.06) based on 30 cases (among these 16 and 13 cases of oesophageal cancer diagnosed among the monitored and unmonitored plutonium workers, respectively). This is consistent with the findings from the study of the Japanese A-bomb survivors (Preston et al, 2007), which found statistically significant elevated risks (ERR/Gy=0.52, 90% CI: 0.15; 1.0) based on 352 cases. However, the IARC study of nuclear workers and the third analysis for the UK radiation workers found no evidence of a significant association with external dose for oesophageal cancer (Cardis et al, 2007; Muirhead et al, 2009a). Additional adjustment for internal liver dose and plutonium-surrogate indices led to a small increase of the ERR/Gy for external dose and the result remains the same.

Stomach

There was some indication of an increased risk from external exposure (ERR/Gy=0.15, 95% CI: −0.01; 0.39, P=0.07), supporting the finding of a significant increased risk for the Japanese A-bomb survivors (ERR/Gy=0.34, 90% CI: 0.22; 0.47) (Preston et al, 2007). Neither the IARC 15 country study nor the UK third analysis reports an association between stomach cancer and external exposure of radiation workers (Cardis et al, 2007, Muirhead et al, 2009a). The findings for external dose remained the same after adjusting for internal liver dose as well as additional adjustment for the plutonium-surrogate categorical indices for unmonitored workers. There was no statistically significant trend in stomach cancer either with internal liver dose (P>0.5) or any of the plutonium-surrogate indices (P=0.33), based on 138 and 92 cases of stomach cancers diagnosed among the monitored and unmonitored plutonium workers, respectively.

Pancreas

There was a significant association of pancreatic cancer incidence with internal plutonium dose, both with and without adjusting for external gamma dose (ERR/Gy=1.58; 95% CI; 0.17; 4.77, P=0.02). Tobacco use is the main identified risk factor for cancer of pancreas. For this analysis, the background model was adjusted for age and gender, but additional adjustment for smoking status had little effect on the dose–response analysis for internal dose. This finding is surprising and not fully understood as plutonium deposition leads to relatively little exposure (or dose) to tissues other than those primary deposition organs, lung, liver and bone. Thus, the observed increase in the risk of this cancer should be treated with caution because of the lack of an established associated between pancreatic cancer and either external or internal radiation exposure (Omar et al, 1999; UNSCEAR, 2006; Cardis et al, 2007; Preston et al, 2007; UNSCEAR, 2008; Muirhead et al, 2009a) or may occur simply by chance because of multiple testing.

Strengths and limitations

The major strengths of this study are the large number of workers including both male and female individuals who were monitored for internal plutonium exposure as well as external gamma radiation, the long follow-up period, the wide range of radiation exposures, the cancer registry and particularly the information available on confounding factors such as smoking and alcohol use. A limitation in this study include the proportion of missing plutonium dose estimates in the early years, uncertainties in organ dose estimates for plutonium and unknown incidence data particular among the migrants. In addition, the small number of observed cancers to certain sites limits the power of the study to show significant associations with radiation exposure and the problem of multiple testing.