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[Dosimetry of fast neutrons in 1W nuclear reactor with plastic nuclear-track detectors].

A nuclear reactor at Kinki University is operated at the maximum of 1W. It produces fission neutrons as much as gamma-rays. To facilitate its use for neutron radiobiology, fast neutrons inside the reactor were measured with nuclear-track detectors TS 16 N and a pair of ion chambers. The angular dependence of TS 16 N response, an anisotropy of fast neutron fluxes in the reactor and misuse of the kerma factor assumed for radiation protection business are the major causes of discrepancy is measured doses by the two methods. Correction factors for the three causes are proposed. After correction, neutron doses estimated with TS 16 N and chambers agree within 5%. The dose-rate at the reactor's center is about 20 tissue-cGy/h. This is the first in situ dosimetry of fast neutrons in a reactor with track detectors attached to biologic samples. Our routine usage has demonstrated that, if used with caution, TS 16 N elements are handy, reliable monitors for fast neutron dosimetry as they are insensitive to contaminated gamma-rays and small enough to be attached to biologic samples.

Fast Neutrons↗

Determination of the thermal neutron flux in a fast neutron beam by use of a boron-coated ionization chamber.

The thermal neutron distribution in slow and fast neutron beams is usually determined using the foil activation method. In this work a small magnesium walled ionization chamber, in which the inner surface of the wall has been coated with 10B to increase the sensitivity for thermal neutrons, is used to estimate the thermal neutron component of the beam. After calibration and determination of the directional response in a thermal neutron beam a comparison with foil activation at different depths in water was performed to investigate the reliability of the ionization measurements. The chamber was used in a computer controlled water phantom to measure the depth and lateral distribution of the thermal neutron dose. With this arrangement two-dimensional scans of the thermal neutrons could be performed quickly and with high accuracy.

Biophysical Phenomena↗

[Pathomorphosis of laryngeal cancer after neutron and gamma-neutron therapy using fast neutrons of the reactor].

Studies of tumours and adjacent tissue were carried out in 29 patients with carcinoma of the larynx after preoperative irradiation with fast neurons at a total focal dose 5.6 Gy alone or in combination with gamma therapy. Pronounced pathomorphosis was established in all the cases, up to a full disappearance of the tumor in 2 patients, the degree of pathomorphosis did not depend on location, macroscopic form of growth, degree of dissemination. No changes were found in the wall of the larynx outside the tumor.

Combined Modality Therapy↗

Beam collimation and bolusing material optimizations for 10boron neutron capture enhancement of fast neutron (BNCEFN): definition of the optimum irradiation technique.

PURPOSE: In boron-10 neutron capture enhancement of fast neutron irradiation (BNCEFN), the dose enhancement is correlated to the 10B concentration and thermal neutron flux. A new irradiation technique is presented to optimize the thermal neutron flux. METHODS AND MATERIALS: The coupled FLUKA and MCNP-4A Monte Carlo codes were used to simulate the neutron production and transport for the Nice and Orleans facilities. RESULTS: The new irradiation technique consists of a 20-cm lead blocks additional collimator, placed close to the patient's head, which is embedded in a pure graphite cube. A 24-fold thermal neutron flux increase is calculated between a 5 x 5 cm2 primary collimated field, with the patient's head in the air, and the same field size irradiated with the optimum irradiation technique. This increase is more important for the p(60)+Be Nice beam than for the p(34)+Be Orleans one. The thermal neutron flux is 2.1 x 10(10) n(th)/Gy for each facility. Assuming a 100 microg/g 10B concentration, a physical dose enhancement of 22% is calculated. Moreover, the thermal neutron flux becomes independent of the field size and the phantom head size. CONCLUSION: This technique allows conformal irradiation of the tumor bed, while the thermal neutron flux is enhanced, and spreads far around the tumor.

Boron Neutron Capture Therapy↗

Microdosimetric investigations on collimated fast-neutron beams for radiation therapy: I. Measurements of microdosimetric spectra and particle dose fractions in a water phantom for fast neutrons from 14 MeV deuterons on beryllium.

Lineal energy spectra of fast neutrons, produced by bombarding a thick beryllium target with 14 MeV deuterons, were measured with a proportional counter simulating a sensitive diamter of 2 micrometers. The mean neutron energy of the collimated beam was 6 MeV. The total lineal energy spectra, measured at different positions within a water phantom were separated into three different components: the gamma component, the recoil-proton component, and the component of heavier recoil ions. It is shown mathematically that the components of a linear energy spectrum thus derived allow the calculation of their fractional dose contributions. These dose fractions i.e. the gamma dose, the recoil-proton dose, and the dose fraction of heavier recoil ions, are shown as a function of the spatial position in the phantom.

Beryllium↗

The influence of hypoxia on the relative sensitivity of human tumor cells to 62.5 MeV (p-->Be) fast neutrons and 4 MeV photons.

Fast neutrons have been used in the clinical radiation therapy of tumors largely because of experimental evidence that their cytotoxic effects are much less dependent on oxygen levels than those of low-LET photons. The potential therapeutic advantage of fast neutrons based on hypoxia alone can be calculated as the "hypoxic gain factor", which is the ratio of the OERs for the fast-neutron compared to the photon beams. The hypoxic gain factor that is generally anticipated based on studies with established mammalian cell lines is about 1.6. However, surprisingly few studies have examined the influence of hypoxia on the fast-neutron radiosensitivity of human tumor cells of different histological types. For this reason, we have determined the OERs of five human tumor cell lines exposed to 62.5 MeV (p-->Be) cyclotron-generated fast neutrons or 4 MeV photons from a clinical linear accelerator. The OERs for four chemotherapy-naive cell lines, HT29/5, Hep2, HeLa and RT112, were invariably greater for photons than for neutrons, but all of these values were lower than expected on the basis of the previous literature. Despite their low OERs, these cell lines showed hypoxic gain factors that were within the range of 1.31-1.63, indicating that such effects cannot entirely explain the disappointing clinical results obtained with fast neutrons. In contrast, comparison of the surviving fractions at clinically relevant doses (1.6 Gy of neutrons and 2.0 Gy of photons) for these four tumor cell lines suggested that little benefit should result from neutron treatment. Only the cisplatin-resistant OAW42-CP line showed a significant hypoxic gain factor by this method of analysis. We conclude that, at the dose fractions used in clinical radiation therapy, there may not be a radiobiological precedent for higher local control rates after fast-neutron irradiation of hypoxic tumor cells.

Animals↗

Reverse genetics by fast neutron mutagenesis in higher plants.

Fast neutron mutagenesis has long been used for forward genetic studies in plants. Only recently has it been used for reverse genetics. By combining fast neutron mutagenesis and high throughput PCR screening, a new knockout methodology, Deleteagene (Delete-a-gene), was developed in Arabidopsis and rice to obtain deletion mutants for target genes. Since fast neutron is a highly efficient mutagen that produces deletion mutations easily detectable by PCR, this method has the potential to enable reverse genetic screens in most plant species. In this review, we will discuss the use of fast neutron as a mutagen for creating deletion mutations, and strategies for successful application of Deleteagene in other plant species.

Arabidopsis↗

DNA radiolysis by fast neutrons.

The effects of fast neutron irradiation on DNA were studied using DNA of the pBR322 plasmid (4362 base pairs), and the results compared to those obtained with 60Co gamma rays. Irradiation of the plasmid DNA in solution with a neutrons beam (p34+Be) of the CERI (CNRS Orléans) cyclotron (with a flat energy spectrum from 34 MeV to low energies) results in half the yield of single-strand breaks (ssb), and 1.5 times higher yield of double-strand breaks (dsb) for neutrons as compared to gamma-rays. Possible specificity of the neutron-induced breaks was examined: the scavenging of OH. radicals by 0.1 mol dm-3 ethanol inhibits all neutron-induced ssb, but only 85 per cent of the dsb. For gamma-irradiation, both ssb and dsb are completely inhibited in these conditions. These results suggest at least three different origins for neutron-induced dsb. The occurrence of around 30 per cent of dsb can be explained by a radical transfer mechanism (proposed by Siddiqi and Bothe (1987) for gamma-irradiation). Around 55 per cent of dsb may be due to the non-random distribution of radicals in high-density tracks of the secondary particles of neutrons, which results in a simultaneous attack of the two strands by OH. radicals. These first two processes are both OH.-mediated and thus are sensitive to ethanol. The direct effect of fast neutrons and their secondaries (recoil protons, alpha-particles and recoil nuclei) can account for the remaining 15 per cent of dsb, not inhibited by 0.1 mol dm-3 ethanol.

Cobalt Radioisotopes↗

Fast neutron beams for boron neutron capture therapy?

In view of Boron Neutron Capture Enhanced Fast Neutron Therapy (BNCEFNT) of brain tumours, the spatial distributions of thermal flux and fast neutron plus photon dose were measured in a hydrogenous cylinder phantom under conditions varying with respect to neutron energy, field size, and irradiation technique. The behaviour of the ratio thermal fluence per unit total dose leads to the conclusion that an appreciable dose contribution from the BNC reaction can be expected only with low energies and large fields. Beams from small apertures (< 6 x 6 cm2) produce only marginal BNC dose contributions, and might gain therapeutic relevance only in combination with a very effective tumour-seeking Boron-10 carrier.

Boron Neutron Capture Therapy↗