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There have been some suggestions that air-crew are at a higher-than-normal risk of developing cancer, since they are exposed to potential genotoxic factors. These include cosmic radiations, airborne pollutants such as the combustion products of jet propulsion, ozone, and electromagnetic fields. We used the Comet assay to investigate DNA damage in flight personnel with the aim of assessing potential health hazards in this occupational category. We studied 40 civil air-crew members who had been flying long-haul routes for at least 5 years, and compared them with a homogeneous control group of 40 healthy male ground staff. The Comet assay, or single-cell gel electrophoresis (SCGE), detects DNA single- and double-strand breaks (DSBs) and alkali-labile lesions in individual cells, and is a powerful and sensitive technique for detecting genetic damage induced by different genotoxic agents. Taking into consideration occupational risk and possible confounding factors, this assay showed a small increase, that did not reach statistical significance, of DNA damage in long-haul crew members compared to controls, indicating a lack of evident genotoxic effects. An association, although again not statistically significant, was found between reduced DNA damage and use of protective drugs (antioxidants).

Nuclear workers, oil well loggers, astronauts, air flight crews, and frequent fliers can be exposed to low doses of neutrons, but the long-term human health consequences of neutron exposure are unknown. While few of these exposed populations are suitable for studying the effects of neutron exposure, patients treated with neutron-beam therapy might be a source of information. To assess the feasibility of conducting a multi-center international study of the late effects of neutron therapy, we surveyed 23 cancer centers that had used neutron beam therapy. For the 17 responding institutions, only 25% of the patients treated with neutrons (2,855 of 11,191) were alive more than 2 years after treatment. In a two-center U.S. pilot study of 484 neutron-treated cancer patients, we assessed the feasibility of obtaining radiotherapy records, cancer incidence and other follow-up data, and of estimating patient organ doses. Patients were treated with 42 MeV neutrons between 1972 and 1989. Applying a clinical equivalence factor of 3.2 for neutrons, total average organ doses outside the treatment beam ranged from 0.14 to 0.29 Gy for thyroid, 0.40 to 2.50 Gy for breast, 0.63 to 2.35 Gy for kidney, and 1.12 to 1.76 Gy for active bone marrow depending upon the primary cancer treatment site. We successfully traced 97% of the patients, but we found that patient survival was poor and that chemotherapy was not confirmable in a quarter of the patients. Based on our findings from the international survey and the feasibility study, we conclude that a large investigation could detect a fivefold or higher leukemia risk, but would be inadequate to evaluate the risk of solid cancers with long latent periods and therefore would likely not be informative with respect to neutron-related cancer risk in humans.

In the criticality accident which occurred on 30 September 1999 at a uranium conversion facility in Tokai-mura, Japan, three workers were severely exposed to neutron and gamma-ray irradiation. Preliminary estimations of doses from blood properties and 24Na concentration in blood were 16-20, 6-10 and 1-4 gamma-ray gray-equivalent (gammaGyEq) respectively for the three workers. For apparent dose estimation, neutron-induced radionuclides in biological materials such as blood, hair and urine were measured. Accordingly, we detected 32p in urine samples. The concentration ratios of 32P in the urine for the three workers showed a similar tendency to those of 24Na in blood. This result indicated that the radioactivity of 32P in urine could be used to estimate the neutron exposure level.

Due to the pronounced energy dependence of the neutron quality factor, accurate assessment of the biologically relevant dose requires knowledge of the spectral neutron fluence rate. Bonner sphere spectrometers (BSSs) are the only instruments which provide a sufficient response over practically the whole energy range of the cosmic ray induced neutron component. Measurements in a 62 MeV proton beam at Paul Scherrer Institute, Switzerland, and in the CERN-EU high-energy reference field led to the assumption that conventional active devices for the detection of thermal neutrons inside the BSS, e.g. 6Lil(Eu) scintillators, also respond to charged particles when used in high-energy mixed radiation fields. The effects of these particles cannot be suppressed by amplitude discrimination and are subsequently misinterpreted as neutron radiation. In contrast, paired TLD-600 and TLD-700 thermoluminescence dosemeters allow the determination of a net thermal neutron signal.

As recommended by the ICRP, the European Union (EU) agreed to abide by mandatory monitoring of radiation doses to crew during civil aviation flights operated by the airlines of the EU member states. A large number of measured and theoretically predicted values for the in-flight radiation doses of northern hemisphere flight routes are available. On the other hand very few data have been published for the southern hemisphere. This paper will present the results of Australian domestic and intemational return flight routes originating from Sydney. The paper also presents results of trans-hemisphere air traffic routes. Neutron and gamma doses were measured using superheated bubble dosemeters and semiconductor detectors respectively. Based on our measurements a method is suggested whereby aircrew may share their personal radiation burden by flight crew hemisphere exchange.

A model which describes the type conductivity inversion and the Fermi level stabilisation in high purity n-silicon under last neutron irradiation has been considered. This model takes into account shallow impurities, oxygen, A- and E-centres and deep amphoteric centres (the vacancy complexes). The role of divacancies is dominant in the Fermi level stabilisation effect. The neutron fluence when the type inversion is observed has been calculated for various initial n-silicon. The results obtained describe peculiarities of the behaviour of neutron integral dosemeters. Characteristics of p-i-n diodes used as fast neutron sensors over a wide dose range and the influence of both the carrier life time and the silicon resistivity changes on the sensor sensitivity are discussed. Using long base diodes fabricated from high resistivity silicon (>10 kohm x cm) allows the sensitivity to reach 5 V x Gy(-1) (tissue).

A study of the effects of exposures of civilian aviation flight personnel to atmospheric ionizing radiation (including high-energy neutrons) is being performed. The results of previous studies and of the criteria required for a more satisfactory outcome in future studies are presented, along with a description of the protocol for the Italian national study. A description of the cohort is given in terms of its size, composition and member eligibility. The various ways of determining the exposure and the health status of past and current aircrew members are discussed, and follow-up procedures are described. An overview of the data management and processing philosophy adopted in the Italian study is given with regard to flight routes, radiation dose evaluation along the flight paths, and construction of exposure matrices. Other studies of potential interest are also discussed. The study is still in progress, so the results are preliminary.

Material presented at a NASA-sponsored workshop on risk models for exposure conditions relevant to prolonged space flight are described in this paper. Analyses used mortality data from experiments conducted at Argonne National Laboratory on the long-term effects of external whole-body irradiation on B6CF1 mice by 60Co gamma rays and fission neutrons delivered as a single exposure or protracted over either 24 or 60 once-weekly exposures. The maximum dose considered was restricted to 1 Gy for neutrons and 10 Gy for gamma rays. Proportional hazard models were used to investigate the shape of the dose response at these lower doses for deaths caused by solid-tissue tumors and tumors of either connective or epithelial tissue origin. For protracted exposures, a significant mortality effect was detected at a neutron dose of 14 cGy and a gamma-ray dose of 3 Gy. For single exposures, radiation-induced mortality for neutrons also occurred within the range of 10-20 cGy, but dropped to 86 cGy for gamma rays. Plots of risk relative to control estimated for each observed dose gave a visual impression of nonlinearity for both neutrons and gamma rays. At least for solid-tissue tumors, male and female mortality was nearly identical for gamma-ray exposures, but mortality risks for females were higher than for males for neutron exposures. As expected, protracting the gamma-ray dose reduced mortality risks. Although curvature consistent with that observed visually could be detected by a model parameterized to detect curvature, a relative risk term containing only a simple term for total dose was usually sufficient to describe the dose response. Although detectable mortality for the three pathology end points considered typically occurred at the same level of dose, the highest risks were almost always associated with deaths caused by tumors of epithelial tissue origin.

This study aims to investigate a shielding design against neutrons and gamma rays from a source of 252Cf, using Monte Carlo simulation. The shielding materials studied were borated polyethylene, borated-lead polyethylene and stainless steel. The Monte Carlo code MCNP4B was used to design shielding for 252Cf based neutron irradiator systems. By normalising the dose equivalent rate values presented to the neutron production rate of the source, the resulting calculations are independent of the intensity of the actual 252Cf source. The results show that the total dose equivalent rates were reduced significantly by the shielding system optimisation.

The direct ion storage (DIS) dosemeter is a new type of electronic dosemeter from which the dose information for both Hp(10) and Hp(0.07) can be obtained instantly at the workplace by using an electronic reader unit. The number of readouts is unlimited and the stored information is not affected by the readout procedure. The accumulated dose can also be electronically reset by authorised personnel. The DIS dosemeter represents a potential alternative for replacing the existing film and thermoluminescence dosemeters (TLDs) used in occupational monitoring due to its ease of use and low operating costs. The standard version for normal photon and beta dosimetry, as well as a developmental version for neutron dosimetry, have been characterised in several field studies. Two new small size variations are also introduced, including a contactless readout device and a militarised version optimised for field use.

The effectiveness of fission neutrons is compared to that of gamma rays and X rays with regard to the induction of malignancies in male Sprague-Dawley rats. The analysis is based on autopsy results. It is focused on tumors that tend to be present in animals dying early, which is indicative of a high degree of lethality. The relative biological effectiveness (RBE) is deduced from a comparison of the cumulative hazard functions. Different nonparametric models-the constant relative risk model, a time shift model, and an acceleration model-are employed in the comparison, and the resulting values of RBE are seen to be substantially independent of the choice of model. The results are in good agreement with earlier studies of nonlethal lung tumors in the same series of experiments. At neutron doses of 20 to 60 mGy, the RBE of fission neutrons is about 50.

In this paper, a stochastic model of cell survival, which was developed by Cotlet and Blue, based on the work of Jones, is extended to describe bone marrow cell survival in high dose rate radiation fields with arbitrary neutron to gamma-ray absorbed dose rate ratios. Mathematical formulas are obtained that describe the interaction of the neutron and gamma-ray components of the absorbed dose, for radiation fields with arbitrary neutron to gamma-ray dose rate ratios, for exposures of cells to various absorbed doses, at various high dose rates.

Chinese hamster ovary (CHO) cells were exposed to thermal and epithermal neutrons, and the occurrence of mutations at the HPRT locus was investigated. The Kyoto University Research Reactor (KUR), which has been improved for use in neutron capture therapy, was the neutron source. Neutron energy spectra ranging from nearly pure thermal to epithermal can be chosen using the spectrum shifters and thermal neutron filters. To determine mutant frequency and cell survival, cells were irradiated with thermal and epithermal neutrons under three conditions: thermal neutron mode, mixed mode with thermal and epithermal neutrons, and epithermal neutron mode. The mutagenicity was different among the three irradiation modes, with the epithermal neutrons showing a mutation frequency about 5-fold that of the thermal neutrons and about 1.5-fold that of the mixed mode. In the thermal neutron and mixed mode, boron did not significantly increase the frequency of the mutants at the same dose. Therefore, the effect of boron as used in boron neutron capture therapy (BNCT) is quantitatively minimal in terms of mutation induction. Over 300 independent neutron-induced mutant clones were isolated from 12 experiments. The molecular structure of HPRT mutations was determined by analysis of all nine exons by multiplex polymerase chain reaction. In the thermal neutron and mixed modes, total and partial deletions were dominant and the fraction of total deletions was increased in the presence of boron. In the epithermal neutron mode, more than half of the mutations observed were total deletions. Our results suggest that there are clear differences between thermal and epithermal neutron beams in their mutagenicity and in the structural pattern of the mutants that they induce. Mapping of deletion breakpoints of 173 partial-deletion mutants showed that regions of introns 3-4, 7/8-9 and 9-0 are sensitive to the induction of mutants by neutron irradiation.

The induction of dicentric chromosomes in human lymphocytes from one individual irradiated in vitro with monoenergetic neutrons at 565 keV was examined to provide additional data for an improved evaluation of neutrons with respect to radiation risk in radioprotection. The resulting linear dose-response relationship obtained (0.813 +/- 0.052 dicentrics per cell per gray) over the dose range of 0.0213-0.167 Gy is consistent with published results obtained for irradiation with neutrons from different sources and with different spectra at energies lower than 1000 keV. Comparing this value to previously published "average" dose-response curves obtained by different laboratories for (60)Co gamma rays and orthovoltage X rays resulted in maximum RBEs (RBE(m)) of about 37 +/- 8 and 16 +/- 4, respectively. However, when our neutron data were matched to low-LET dose responses that were constructed several years earlier for lymphocytes from the same individual, higher values of RBE(m) resulted: 76.0 +/- 29.5 for (60)Co gamma rays and 54.2 +/- 18.4 for (137)Cs gamma rays; differentially filtered 220 kV X rays produced values of RBE(m) between 20.3 +/- 2.0 or 37.0 +/- 7. 1. The results highlight the dependence of RBE(m) on the choice of low-LET reference radiation and raise the possibility that differential individual response to low-LET radiations may need to be examined more fully in this context.

Neutrons are associated with therapeutic high energy x-ray beams as a contaminant that contributes significant unwanted dose to the patient. Measurement of both photon and neutron scattered dose at the position of a fetus from chest irradiation by a large field 18 MV x-ray beam was performed using an ionization chamber and superheated drop detector, respectively. Shielding construction to reduce this scattered dose was investigated using both lead sheet and borated polyethylene slabs. A 7.35 cm lead shield reduced the scattered photon dose by 50% and the scattered neutron dose by 40%. Adding 10 cm of 5% borated polyethylene to this lead shield reduced the scattered neutron dose by a factor of 7.5 from the unshielded value. When the 5% borated polyethylene was replaced by the same thickness of 30% borated polyethylene there was no significant change in the reduction of neutron scatter dose. The most efficient shield studied reduced the neutron scatter dose by a factor of 10. The results indicate that most of the scattered neutrons present at the position of the fetus produced by an 18 MV x-ray beam are of low energy and in the thermal to 0.57 MeV range since lead is almost transparent to neutrons with energies lower than 0.57 MeV. This article constitutes the first report of an effective shield to reduce neutron dose at the fetus when treating a pregnant woman with a high energy x-ray beam.

Purpose: To investigate the protective effects of dimethyl sulfoxide (DMSO) on cell killing and mutagenicity at the HPRT locus in Chinese hamster ovary (CHO) cells against thermal and epithermal neutrons produced at the Kyoto University Research (KUR) reactor., Methods and Materials: DMSO was added to cells 15 min before irradiation and removed 15 min after irradiation. Cells were irradiated by thermal and epithermal neutrons with or without boron at 10 ppm. The biological endpoint of cell survival was measured by colony formation assay. The mutagenicity was measured by the mutant frequency in the HPRT locus. A total of 378 independent neutron-induced mutant clones were isolated in separate experiments. The molecular structure of HPRT mutations was determined by analysis by multiplex polymerase chain reaction of all nine exons., Results: The D(0) values of epithermal and thermal neutrons in three different modes, i.e., thermal, epithermal, and mixtures of thermal and epithermal, were 0.8-1.2 Gy. When cells were treated with DMSO, the D(0) values increased to 1.0-2.3, especially in the absence of boron. DMSO showed a protective effect against mutagenesis of the HPRT locus induced by epithermal and thermal neutron irradiation. After DMSO treatment, the mutagenicity was decreased, especially when the cells were irradiated in epithermal neutron mode. Molecular structure analysis indicated that total and partial deletions were dominant and the incidence of total deletions was increased in the presence of boron in the thermal neutron and mixed modes. In the epithermal neutron mode, more than half of the mutations were total deletions. When cells were treated with DMSO, the incidence of total deletions by thermal neutron irradiation with boron and epithermal irradiation decreased., Conclusions: Our results suggest that DMSO has various protective effects against cytotoxic and mutagenic effects of thermal and epithermal neutrons, and that the extent of protection is reflected by the percentage of absorbed dose distribution for each neutron irradiation mode.

Female hybrid mice (C57BL/6J x HLG) were exposed to 0.5 Gy of cyclotron neutrons (mean energy 5.8 MeV) after mating with HLG males when embryos were at the early zygote stage. Uterine contents were examined on gestation day 19 for prenatal mortality and malformed development. The results were compared to those obtained after irradiation of zygotes with 1.0 and 1.7 Gy X rays. The number of malformed fetuses was greater than for the unirradiated controls. Gastroschisis was the main observation, but exencephaly was also observed. The neutron relative biological effectiveness (RBE) for the induction of lethal events and malformations in the [(C57BL/6J x HLG)F(1)x HLG] mice was estimated. This value is higher than that for the RBE calculated for the HLG strain, which is known to be more sensitive to radiation than the hybrids.

Purpose: Occupational exposure to neutrons typically includes significant doses of low-energy neutrons, with energies below 100 keV. In addition, the normal-tissue dose from boron neutron capture therapy will largely be from low-energy neutrons. Microdosimetric theory predicts decreasing biological effectiveness for neutrons with energies below about 350 keV compared with that for higher-energy neutrons; based on such considerations, and limited biological data, the current radiation weighting factor (quality factor) for neutrons with energies from 10 keV to 100 keV is less than that for higher-energy neutrons. By contrast, some reports have suggested that the biological effectiveness of low-energy neutrons is similar to that of fast neutrons. The purpose of the current work is to assess the relative biological effectiveness of low-energy neutrons for an endpoint of relevance to carcinogenesis: in vitro oncogenic transformation., Methods: Oncogenic transformation induction frequencies were determined for C3H10T1/2 cells exposed to two low-energy neutron beams, respectively, with dose-averaged energies of 40 and 70 keV, and the results were compared with those for higher-energy neutrons and X-rays., Results: These results for oncogenic transformation provide evidence for a significant decrease in biological effectiveness for 40 keV neutrons compared with 350 keV neutrons. The 70 keV neutrons were intermediate in effectiveness between the 70 and 350 keV beams., Conclusions: A decrease in biological effectiveness for low-energy neutrons is in agreement with most (but not all) earlier biological studies, as well as microdosimetric considerations. The results for oncogenic transformation were consistent with the currently recommended decreased values for low-energy neutron radiation weighting factors compared with fast neutrons.

This paper addresses some of the pertinent questions relating to the assessment of radiation risk for humans in space; the paper is not intended as a comprehensive review. The radiation field is briefly summarised and doses to be expected are given based on recent on-board measurements. The problems in adapting terrestrial epidemiological data to the space situation are outlined. Apart from the intrinsic uncertainties in deriving risk factors the specific difficulties are mainly concerned with the effects of energetic charged particles for which no human data exist. The necessity for continuing ground-based research is stressed. Also discussed is whether the principles of radiation protection successfully applied on Earth are really suitable for the space situation or whether they should be replaced by a different approach.

This study was undertaken to investigate the biological effect of monoenergetic neutrons on human lymphocyte DNA and chromosomes. Monoenergetic neutrons of 2.3, 1.0, 0.79, 0.57, 0.37 and 0.186 MeV were generated, and 252Cf neutrons and 60Co gamma-rays were also used for comparison. Biological effect was evaluated two ways. The RBE values with the comet assay were estimated as 6.3 and 5.4 at 0.37 MeV and 0.57 MeV relative to that of 60Co gamma-rays, and chromosome aberration rates were also observed in these different levels of monoenergetic neutrons. The yield of chromosome aberrations per unit dose was high at lower neutron energies with a gradual decline with 0.186 MeV neutron energy. The RBE was increased to 10.7 at 0.57 MeV from 3.9 at 252Cf neutrons and reached 16.4 as the highest RBE at 0.37 MeV, but the value decreased to 11.2 at 0.186 MeV. The response patterns of initial DNA damage and chromosome exchange were quite similar to that of LET. These results show that the intensity of DNA damage and chromosomal exchange is LET dependent. RBE of low energy neutrons is higher than that of fission neutrons. Low energy neutrons containing Hiroshima atomic bomb radiation may have created a significantly higher incidence of biological effect in atomic bomb survivors.

Both cell lethality and neoplastic transformation were assessed for C3H10T1/2 cells exposed to neutrons with energies from 0.040 to 13.7 MeV. Monoenergetic neutrons with energies from 0.23 to 13.7 MeV and two neutron energy spectra with average energies of 0.040 and 0.070 MeV were produced with a Van de Graaff accelerator at the Radiological Research Accelerator Facility (RARAF) in the Center for Radiological Research of Columbia University. For determination of relative biological effectiveness (RBE), cells were exposed to 250 kVp X rays. With exposures to 250 kVp X rays, both cell survival and radiation-induced oncogenic transformation were curvilinear. Irradiation of cells with neutrons at all energies resulted in linear responses as a function of dose for both biological endpoints. Results indicate a complex relationship between RBEm and neutron energy. For both survival and transformation, RBEm was greatest for cells exposed to 0.35 MeV neutrons. RBEm was significantly less at energies above or below 0.35 MeV. These results are consistent with microdosimetric expectation. These results are also compatible with current assessments of neutron radiation weighting factors for radiation protection purposes. Based on calculations of dose-averaged LET, 0.35 MeV neutrons have the greatest LET and therefore would be expected to be more biologically effective than neutrons of greater or lesser energies.

An interest in the possible cancer causing ability of neutrons began soon after their discovery. Early use of neutrons from radioactive sources and from cyclotrons led to a need to define risk for such exposures. This need was soon followed by a more tangible need to define risk to the general population of high LET radiation from nuclear fall out and use of the Atomic bomb and possible use of the H-bomb. Neutrons were soon found to be very effective cell killing agents compared to conventional ionizing radiation. However High LET radiation sources and neutrons in particular, come in many different energies and from many types of sources. I will survey the differences between different energy neutrons and conventional types of radiation, particularly with respect to the dose rate of exposures and the influence of repair or lack thereof and more recently the effect of cell cycle distribution on the carcinogenic outcome. I will illustrate these ideas with examples of carcinogenicity studies and mutation studies from my own laboratory and in some cases from the work of others. Lastly I will introduce some possible avenues for molecular studies of neutron effects that might answer such vexing questions as the real risk at very low doses, is repair error free or error prone, do neutrons cause genetic instability for many cell generations after exposure, and others? There remain many questions about the biology of neutron action that require answers if we are to protect the ever increasing number of people exposed to them because of their growing use in medicine, in the military and in commercial industry.

Following the hormonal treatment of rats with high prolactin levels and glucocorticoid deficiency (Prl+/Glc-) for 48 days (Day +48), total recoverable mammary DNA was increased by more than sevenfold, tritiated thymidine uptake by nearly fourfold, and total mammary clonogens by about fivefold. Irradiation with 4, 40, and 80 cGy X-rays on Day +48 increased total mammary carcinomas per rat-day-at-risk linearly with dose, and 40 and 80 cGy significantly decreased first carcinoma latency. A dose of 40 cGy X-rays before hormone treatment (Day -1) yielded tumor latencies and frequencies insignificantly different from unirradiated controls but significantly different from those when the dose was given on Day +48. Total carcinomas per rat-day-at-risk were fitted better by a function of dose to the power 0.4 than by a linear function after exposure to 1, 10. and 20 cGy fission neutrons, and 10 and 20 cGy significantly shortened the time to appearance of the first cancer. In contrast to results with X-rays, 10 cGy neutrons on Day -1 yielded tumor frequencies and latencies insignificantly different from 10 cGy neutrons on Day +48. The carcinogenic action of X-rays, but not of neutrons, was thus influenced by total clonogen numbers and/or proliferation rates.

We have examined the neutron energy dependency of cell killing and mutation induction at the hprt locus in Chinese hamster V79 cells. Monoenergetic neutrons at 0.32, 0.57, and 1.2 MeV were generated at the Hiroshima University Radiobiological Research Accelerator (HIRRAC) Facility, and were used to irradiate cells. The variation in RBE with neutron energy for the end points of cell survival and hprt mutation induction was observed. When compared to 137Cs gamma-rays, all neutron energies were more effective at both cell killing and induction of mutation. Over the range of the neutron energies examined, we found that cytotoxicity increased as the energy decreased from 1.2 to 0.32 MeV. In comparison to gamma-rays, RBEs for cell lethality at 10% survival were 5.7, 6.7, and 7.6 for 1.2, 0.57, and 0.32 MeV, respectively. Mutation induction, on the other hand, was highest at 0.57 MeV with a gradual decrease at 1.2 and 0.32 MeV. RBEs for mutation induction were 9.7, 19.4, and 13.9 for 1.2, 0.57, and 0.32 MeV neutrons. We isolated independent V79 cell mutants at the hprt locus from untreated and neutron-exposed cells and determined the genetic changes underlying the mutation by multiplex polymerase chain reaction (PCR)-based exon deletion analysis. Preliminary results are suggestive of a specific relationship between deletion pattern and neutron energy.

Previous studies showed that a 6-week pretreatment of rats with testosterone plus estradiol enhanced the recovery of spermatogenesis 9 weeks after gamma irradiation, resulting in a dose-modifying factor (DMF) of about 2. To test whether the effect of the hormone treatment was mediated through changes in oxygen tension, thiol levels or DNA repair, we irradiated the testes of rats with neutrons, which depend less on these factors than does low-LET radiation for their cytotoxic action. Control rats and rats treated with testosterone plus estradiol were irradiated with 0.7-2.7 Gy of cyclotron-generated high-energy neutrons. The recovery of spermatogenesis was assessed 9 weeks after irradiation by testis weights, sperm counts and the tubule repopulation indices. Greater recovery of spermatogenesis was observed for all end points, with a DMF of about 2 for rats treated with testosterone plus estradiol compared to the irradiated, cholesterol-treated rats. The equal protection factors for neutrons and gamma rays indicate that oxygen, thiols and repair of DNA damage are unlikely to be involved in the protective effect of the hormone treatment.

The risk of induction of a second primary cancer after a therapeutic irradiation with conventional photon beams is well recognized and documented. However, in general, it is totally overwhelmed by the benefit of the treatment. The same is true to a large extent for the combinations of radiation and drug therapy. After fast neutron therapy, the risk of induction of a second cancer is greater than after photon therapy. Neutron RBE increases with decreasing dose and there is a wide evidence that neutron RBE is greater for cancer induction (and for other late effects relevant in radiation protection) than for cell killing. Animal data on RBE for tumor induction are reviewed, as well as other biological effects such as life shortening, malignant cell transformation in vitro, chromosome aberrations, genetic effects. These effects can be related, directly or indirectly, to cancer induction to the extent that they express a "genomic" lesion. Almost no reliable human epidemiological data are available so far. For fission neutrons a RBE for cancer induction of about 20 relative to photons seems to be a reasonable assumption. For fast neutrons, due to the difference in energy spectrum, a RBE of 10 can be assumed. After proton beam therapy (low-LET radiation), the risk of secondary cancer induction, relative to photons, can be divided by a factor of 3, due to the reduction of integral dose (as an average). The RBE of heavy-ions for cancer induction can be assumed to be similar to fission neutrons, i.e. about 20 relative to photons. However, after heavy-ion beam therapy, the risk should be divided by 3, as after proton therapy due to the excellent physical selectivity of the irradiation. Therefore a risk 5 to 10 times higher than photons could be assumed. This range is probably a pessimistic estimate for carbon ions since most of the normal tissues, at the level of the initial plateau, are irradiated with low-LET radiation.

The conditions for safe and effective conformal neutron radiotherapy have been established at Wayne State University.

The depth profile of 152Eu activity induced in a large granite stone pillar by Hiroshima atomic bomb neutrons was calculated by a Monte Carlo N-Particle Transport Code (MCNP). The pillar was on the Motoyasu Bridge, located at a distance of 132 m (WSW) from the hypocenter. It was a square column with a horizontal sectional size of 82.5 cm x 82.5 cm and height of 179 cm. Twenty-one cells from the north to south surface at the central height of the column were specified for the calculation and 152Eu activities for each cell were calculated. The incident neutron spectrum was assumed to be the angular fluence data of the Dosimetry System 1986 (DS86). The angular dependence of the spectrum was taken into account by dividing the whole solid angle into twenty-six directions. The calculated depth profile of specific activity did not agree with the measured profile. A discrepancy was found in the absolute values at each depth with a mean multiplication factor of 0.58 and also in the shape of the relative profile. The results indicated that a reassessment of the neutron energy spectrum in DS86 is required for correct dose estimation.

Background: Nausea and vomiting produced by sub-lethal doses of X- or gamma-rays can be ameliorated by serotonin subtype-three (5-hydroxytryptamine; 5-HT3) receptor antagonists. The effectiveness of these anti-emetics on blocking the emetic responses induced by fission neutron or proton radiation exposure was evaluated in the ferret animal model., Hypothesis: 5-HT3 receptor antagonists or bilateral vagotomy will ameliorate that emesis evoked by fission neutrons or protons., Methods: Groups of ferrets were exposed to whole-body or head-shielded radiations of varying qualities: fission spectrum neutons, high-energy protons, or gamma-rays. Prior to that exposure, some groups were either vagotomized or received subcutaneous (s.c.) or oral (p.o.) treatment with various doses of the 5-HT3 receptor antagonist antiemetics eusatron and ondansetron., Results: We demonstrated that both eusatron and ondansetron effectively abolished the emesis normally induced by 2-Gy doses of either 60Co gamma or neutron:gamma, mixed-field irradiation, the latter with a neutron-to-total dose ratio (Dn/Dt) of 0.9+/-2% (%SD). Different routes of delivery of the anti-emetics yielded different degrees of inhibition of the emetic responses; p.o. treatment was less efficacious than s.c. treatment for the emesis to fission neutrons. Eusatron was significantly more effective than ondansetron on a mg x kg(-1) basis. Bilateral vagotomy also attenuated or abolished the emetic responses to the mixed-field neutron exposures. Furthermore, emesis induced by exposure to 2.5 Gy of 200-MeV protons was effectively abolished by ondansetron., Conclusion: These results are consistent with the concept that similar physiological and pharmacological mechanisms underlie the emetic responses to different qualities of radiation.

Background: To evaluate alternative treatment regimen e.g. neutron therapy determination of treatment efficacy as well as side effects is important. Sensitivity of computed tomography (CT) in detecting changes of connective tissue after neutron therapy was examined., Patients and Methods: In the course of their follow-up period (median 45 months) 12 patients with malignant salivary gland tumors who had postoperatively received neutron (1/12) or photon/neutron therapy (11/12) were examined by means of CT densitometry on 3 representative scans in the area of radiotherapy. In 3 ROI (regions of interest) in subcutaneous fatty tissue the density at the irradiated and the non-irradiated side was determined according to Hounsfield units (HU) and the average density was calculated. The average density of both sides was compared and correlated with the clinical grade of fibrosis according to LENT SOMA., Results: All CT measurements (216 ROI, 18 ROI per patient) showed higher density levels on the irradiated side than on the non-irradiated side. The average density on the irradiated side was -57.7 +/- 4.7 HU and on the non-irradiated side -69.4 +/- 5.8 HU (p = 0.002). In 3/12 patients a clinical fibrosis was not seen; however, the relative density measured on the irradiated and non-irradiated side deviated by up to 8%. This could have been caused by minimal changes not being noticed by either patient and examiner. In patients with determined fibrosis Grade 1 (8/12) the relative density deviation was 4 to 39%. In 1/12 patients with determined fibrosis Grade 2 the relative density deviation was 50% (Figures 1a and 1b). Fibrosis Grade 3 and 4 did not occur (Table 1)., Conclusions: Fibrosis is correlated with an increasing value of HU of the tissue density in CT. With the described method it is possible to graduate radiation induced subcutaneous fibrosis in correlation to the clinical fibrosis grade according to LENT SOMA. In the patients we examined subcutaneous fibroses after photon/neutron therapy were moderate. Especially in characterising subclinical or slight changes of connective tissue after radiotherapy computed tomography is of value.

Using atomic force microscopy (AFM), we have investigated neutron-induced DNA double-strand breaks in plasmids in aqueous solution. AFM permits direct measurement of individual DNA molecules with an accuracy of a few nanometers. Furthermore, the analysis of the DNA fragment size distribution is non-parametric, whereas other methods are dependent on the model. Neutron irradiation of DNA results in the generation of many short fragments, an observation not made for damage induced by low-LET radiation. These data provide clear experimental evidence for the existence of clustered DNA double-strand breaks and demonstrate that short DNA fragments may be produced by such radiations in the absence of a nucleosomal DNA structure.

Purpose: The relationship between different forms of persistent radiation damage in irradiated cells was investigated in order to identify a common underlying mechanism., Material and Methods: V-79 Chinese hamster cells were irradiated with different doses of X-rays, neutrons and alpha-particles. In the progeny of surviving cells, up to 4 weeks after irradiation, delayed reproductive death, delayed micronuclei, delayed appearance of dicentric chromosomes and delayed apoptosis were investigated in parallel., Results: A similar dose-response relationship was found for all endpoints, with a steep rise at low doses to a plateau at doses > 3 Gy. The target for inducing genomic instability by alpha-particles is larger than the nucleus. All chromosomes are equally involved in delayed breakage reunion events., Conclusion: The results indicate that non-lethal radiation damage to an extranuclear target leads to a persistent increase in clastogenic activity in the surviving irradiated cells.

Purpose: To investigate the LET dependence of various yield ratios of intra- and interchromosomal aberrations in order to quantify proximity effects for illegitimate rejoining of chromosome breaks., Materials and Methods: Calculations are based on 13 human lymphocyte data sets obtained from in vitro irradiation experiments with various radiation qualities covering an LET range of 0.5 to 150keV/microm. A total of 93000 first-division metaphases was analysed for all categories of chromosome-type aberrations., Results: No dose dependence was found for the various yield ratios of chromosomal aberrations. No LET dependence became apparent for the yield ratio of inter- to intrachromosomal exchange-type aberrations (dicentrics/centric rings = F value). However, a clear LET dependence was found for the yield ratio of intra-arm intrachanges to inter-arm intrachanges (interstitial deletions/centric rings = G ratio) and for the yield ratio of intra-arm intrachanges to interchromosomal exchanges (interstitial deletions/dicentrics = H ratio)., Conclusion: Measurements of intrachanges are informative for interpretation and quantification of proximity effects in the formation of radiation-induced chromosome aberrations. In particular, yield ratios for intra-arm intrachanges are likely to have a high potential as an indicator of high-LET radiations.

Purpose: Recent studies have shown that chemical carcinogens induce a high frequency of point mutations in the K-ras oncogene from mouse lung tumours at codons 12, 13 and 61. These experiments were performed to identify K-ras mutations in tissues from control and radiation-exposed mice., Materials and Methods: By modifying the technique of the 'enriched' polymerase chain reaction (PCR), it was possible to detect point mutations at codon 12 of the K-ras oncogene from 25-year-old paraffin-embedded normal lungs and lung adenocarcinomas from mice exposed to radiation. Together, a total of 120 lung tissues were screened for point mutations at codon 12 of the K-ras oncogene in this study., Results: A significant increase in K-ras codon 12 point mutations was observed in the normal lungs from mice exposed to 24 once-weekly neutron irradiations (100%), compared with normal lungs from mice with sham-irradiation (50%) (p<0.05). Lung adenocarcinomas from mice receiving 24 once-weekly neutron irradiations also had a significantly higher frequency of K-ras codon 12 point mutations (100%) than the lung adenocarcinomas of mice receiving 24 or 60 once-weekly gamma-ray irradiations (50%), but the higher frequency was not significantly different from that in spontaneous lung adenocarcinomas from mice (75%; p > 0.05). The validity of the technique was confirmed by sequencing two of the mutants. In doing so, a K-ras 13(Asp) point mutation was observed., Conclusions: The data suggest that high-linear energy transfer (LET) neutron radiation was more effective than low-LET gamma-rays in inducing K-ras point mutations at codon 12 in the lungs of B6CF1 mice.

The risk of secondary cancer induction after a therapeutic irradiation with conventional photon beams is well recognised and documented. However, in general, it is totally overwhelmed by the benefit of the treatment. The same is true to a large extent for the combinations of radiation and drug therapy. After fast neutron therapy, the risk of secondary cancer induction is greater than after photon therapy. This can be expected from the whole set of radiobiological data, accumulated so far, which shows systematically a greater relative biological effectiveness (RBE) for neutrons for all the biological systems which have been investigated. Furthermore, the neutron RBE increases with decreasing dose and there is extensive evidence that neutron RBE is greater for cancer induction and for other late effects relevant in radiation protection than for cell killing at high doses as used in therapy. Almost no reliable human epidemiological data are available so far, and the aim of this work is to derive the best risks estimate for cancer induction after neutron irradiation and in particular fast neutron therapy. Animal data on RBE for tumour induction are analysed. In addition, other biological effects are reviewed, such as life shortening, malignant cell transformation in vitro, chromosome aberrations, genetic effects. These effects can be related, directly or indirectly, to cancer induction to the extent that they express a "genomic" lesion. Since neutron RBE depends on the energy spectrum, the radiation quality has to be carefully specified. Therefore, the microdosimetric spectra are reported each time they are available. Lastly, since heavy-ion beam therapy is being developed at several centres worldwide, the available data on RBE at low doses are reviewed. It can be concluded from this review that the risk of induction of a secondary cancer after fast neutron therapy should not be greater than 10-20 times the risk after photon beam therapy. For heavy ions, and in particular for carbon ions, the risk estimate should be divided by a factor of about 3 due to the reduced integral dose. The risk has to be balanced against the expected improvement in cure rate when the indication for high-LET therapy has been correctly evaluated in well-selected patient groups.

An important approach to understanding the role of the various DNA repair pathways in the cellular response to DNA-damaging agents is through the study of repair-deficient mutant cell lines. In the present study we used this strategy to assess the relative importance of four of these pathways for the repair of DNA damage induced by low-linear energy transfer (LET) gamma rays and intermediate-LET 42 MeV (p-->Be+) fast neutrons. The panel of hamster cell mutants that we characterized for their relative sensitivity to fast neutrons and gamma rays includes cell lines with defects in the nucleotide excision repair pathway; these can be further subdivided into mutants which are defective in nucleotide excision repair alone [UV5 (ERCC2-), UV24 (ERCC3-), UV135 (ERCC5-) and UV61 (ERCC6-)] compared to those which have an associated defect in the distinct but overlapping pathway for the repair of DNA crosslinks [UV20 (ERCC1-) and UV41 (ERCC4-)]. We also examined mutants with defects in the base excision repair pathway [EM9 (XRCC1-)] and the DNA-dependent protein kinase (DNA-PK)-mediated DNA double-strand break (DSB) repair pathway [xrs5 (XRCC5-)]. None of the mutants defective in nucleotide excision repair was differentially sensitized to fast neutrons or gamma rays; in fact, the slight radiosensitivity of these mutants under aerated conditions may be secondary to their defect in nucleotide excision repair. In contrast, deficiency in the base excision repair pathway resulted in a significant primary sensitization to both types of radiation (1.95-fold to gamma rays and 1.79-fold to neutrons). Deficiency in the DSB repair pathway mediated by DNA-PK resulted in a marked, but again similar, primary sensitization to gamma rays (4.2-fold) and neutrons (5.1-fold). Thus none of the repair pathways examined here exhibited a preferential role for the repair of damage induced by low-LET compared to intermediate-LET radiations; this resulted in an essentially constant relative biological effectiveness (RBE) of approximately 2 among the cell lines studied, independent of their DNA repair proficiency. However, consideration of these data along with data published previously for high-LET alpha particles suggests that, whereas the DNA-PK pathway is important for the repair of DSBs induced by low- and intermediate-LET radiations, it becomes less important as the LET increases beyond 100 keV/microm; thus this pathway may not be involved in repairing the more complex lesions induced by densely ionizing high-LET particles.

CHO cells were exposed to thermal neutrons and their mutation frequency was determined. The Kyoto University Research Reactor (KUR), which has a very low level of contamination by gamma-rays and fast neutrons was used as a thermal neutron source. Cells were irradiated in the presence or absence of boric acid to determine mutation frequency and cell survival. Thermal neutron irradiation was 2.5 times as mutagenic as gamma-irradiation without boron. In the presence of boron, however, thermal neutron irradiation was from 4.2 to 4.5 times as mutagenic as gamma-irradiation. When the mutation frequency was plotted against the survival fraction, a higher degree of mutagenicity was observed in the presence than in the absence of boron. These results suggest that the enhancement of thermal neutron-induced mutation with boron is strongly associated with alpha-particles released by 10B(n, alpha)7 Li reaction.

While it is recognized that neutrons contributed to the excess cancer incidence and mortality among the atomic bomb survivors in Hiroshima, there is no possibility to deduce the magnitude of this contribution from the data. This remains true even if the neutron doses in the dosimetry system DS86 are corrected upwards in line with recent neutron activation measurements. In spite of this fact, important information can be obtained in the form of an inverse relation of the risk coefficients for gamma-rays and neutrons. Such an interrelation must apply because the observed excess incidence or mortality is made up of a gamma-ray and a neutron component; increased attribution to neutrons decreases the attribution to photons. Computations with the uncorrected and the corrected DS86 are performed for the mortality and the incidence of solid tumors combined. They refer to doses up to 2 Gy and employ the constant relative risk model and a linear-quadratic dose dependence with variable ratio-the neutron relative biological effectiveness (RBE) at low doses-of the linear component for neutrons and gamma-rays. In line with past analyses, no quadratic component is obtained with the uncorrected DS86. but it is seen, even in these calculations, that the assumption of increased neutron RBEs does not translate into proportional increases of the risk coefficients of neutrons, because it leads to substantially reduced risk estimates for gamma-rays. Calculations with the corrected dosimetry bring out this reciprocity even more clearly. High values of the neutron RBE reduce-in line with recent suggestions by Rossi and Zaider-the risk estimates for gamma-rays substantially. Even a purely quadratic dose relation for gamma-rays is consistent with the data; it requires no major increase of the nominal risk coefficients for neutrons over the currently assumed values. The cancer data from Hiroshima can still provide 'prudent' risk estimates for photons, but with the corrected DS86, they do not prove that there is a linear component in the dose dependence for photons.

Two granite and two concrete core samples were obtained within 500 m from the hypocenter of the Hiroshima atomic bomb, and the depth profile of 152Eu was measured to evaluate the incident neutron spectrum. The granite cores were obtained from a pillar of the Motoyasu Bridge located 101 m from the hypocenter and from a granite rock in the Shirakami Shrine (379 m); the concrete cores were obtained from a gate in the Gokoku Shrine (398 m) and from a pillar top of the Hiroshima bank (250 m). The profiles of the specific activities of the cores were measured to a depth of 40 cm from the surface using low background germanium (Ge) spectrometers. According to the measured depth profiles, relaxation lengths of incident neutrons were derived as 13.6 cm for Motoyasu Bridge pillar (granite), 12.2 cm for Shirakami Shrine core (granite), and 9.6 cm for concrete cores of Gokoku Shrine and Hiroshima Bank. In addition, a comparison of the granite cores in Hiroshima showed good agreement with Nagasaki data. Present results indicates that the depth profile of 152Eu reflects incident neutrons not so high but in the epithermal region.

The method of calculation of the effective dose equivalent for external neutron and photon radiation are presented. Adjoint transport Monte-Carlo code ROBOT is used to calculate fluence-to-effective dose conversion function for MIRD phantoms. Two broad neutron and photon beam irradiations were chosen frontally and isotropically. The effective dose conversion functions are presented and good agreement is shown with Monte-Carlo calculation by other authors. The received data can be used in a new rates of radiation safety.

Aim: Further experiments were performed to explain a difference in chromosomal aberration yield found between samples cultivated immediately after fission neutron irradiation and samples which were cultivated with 96 h delay after irradiation., Material and Method: Human peripheral blood samples were irradiated in mixed fission neutron/gamma field (1800 s) and biological effect assessed in the mean of analysis of unstable chromosome aberrations with a time delay in culturing cells of 12, 24, 48, and 96 h. Additional measurements were performed on irradiated and blank blood samples with the aim to detect any increase in alpha and beta activity after fission neutron irradiation. No difference was found. Results were compared to theoretically calculated values of the alpha and beta activity released from natural radioactive isotopes., Result and Conclusion: As a conclusion it is shown that in our experimental conditions the secondary effects resulting from nuclear transformations of natural or induced radioactive isotopes, recoil reactions and accompanying alpha, beta, and gamma radiation are not the reason for the increase observed in chromosomal aberration yield in blood samples cultured with a time delay of at least 24 hours.

Purpose: To evaluate neutron irradiation alone and with chemotherapy to treat inoperable pancreatic cancer., Materials and Methods: Between 1977 and 1994, 173 patients (60 men, 113 women, aged 43-77 years [mean, 59 years]) with unresectable adenocarcinoma of the exocrine pancreas were treated, 106 with neutron irradiation alone and 67 with concomitant chemotherapy (fluorouracil [5-FU]). At follow-up, which was performed at 2-month intervals until death (range, 4-64 months), clinical status was recorded, noting the presence of overt metastasis and the onset of any major complications. Actuarial (Kaplan-Meier) survival tables were computed for both groups., Results: For neutron irradiation alone and neutron irradiation plus chemotherapy, median survival times were 6 months and 9 months, respectively; actuarial survival rates at 3 years were 0 and 7%, respectively; major reactions (grade 3 or higher [scale of the Radiation Therapy Oncology Group and European Organization for Research and Treatment of Cancer]) occurred in 19 (18%) and 17 (25%) patients, respectively; and severe complications (grade 4) occurred in five (5%) and four (6%) patients, respectively. Most deaths were due to metastatic disease rather than to failure of local control., Conclusions: Neutron irradiation obliterated pancreatic adenocarcinoma at the primary site but has no effect on long-term survival. With more effective concomitant chemotherapy to prevent metastasis, local control of pancreatic cancer with neutron irradiation could lead to increased long-term survival.