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Human lymphocytes were irradiated in vitro during G0 stage by graded doses of thermal neutrons and of neutrons with mean energy of 0.04; 0.09; 0.35; 0.85 and 14.7 MeV as well as by 60Co gamma-rays. The data were fitted to the linear and linear-quadratic relations. The neutrons of low and intermediate energies showed the linear dependence on the dose, 14.7 MeV neutrons and gamma-rays--a linear-quadratic one, whereas the data obtained with 0.85 MeV neutrons fitted well the both models. Terminal and interstitial deletions produced by both gamma-rays and neutrons showed different dependencies upon the dose. Some qualitative pecularities of aberration spectra were found in the experiments with neutrons as compared with the data on gamma-irradiation: the ratio of exchanges to fragments was greater, and aberrations of chromatid type were produced. The specially designed experiments and calculations showed that the last effect was not connected with induced radioactivity.
Neutron energy spectra and yields produced by the bombardment of thick lithium targets by deuterons and protons have been measured using the time-of-flight method. Measurements were made at angles up to 45 degrees for deuteron energies of 8, 12 and 15 MeV and a proton energy of 15 MeV. The average neutron energy of the (d, n) reactions is shown to vary approximately as 0.44Ed. The (p, n) reaction has En = 4.7 MeV. The tissue penetration of neutron therapy beams is dependent on their average neutron energy and thus the low average neutron energy for these reactions appears to preclude their use for practical neutron therapy at these incident particle energies.
In this report is specified which accuracies must now be achieved in the determination of dose components for neutron therapy of tumors and for evaluation of RBE's after neutron irradiations of various organs from mammals or men. After these introductory remarks the reasons are summarized why the errors in ionimetric measurements of neutron doses are considerably higher than those of gamma-doses. In detail the concept and the errors of the Rossendorf neutron dosimeter system are represented. The latter consists of two spherical homogeneous ionization chambers, each of which is connected to a commercial dosimeter. The results of an intercomparison between our neutron dosimeter and that of DR. Bewley (MRC Cyclotron Unit, Hammersmith Hospital London) carried out at the Rossendorf neutron therapy facility are reported.
Methods of assessing the uniformity of thermal and fast neutron fluence in relation to total body in vivo neutron activation analysis are described. Results are presented for 14 MeV neutrons emitted by sealed tube generators housed in a massive concrete shield, representing a substantial source of neutrons degraded in energy. Optimisation of conditions for patient irradiations is discussed and it is shown that acceptable uniformity of fluence can be achieved with little or no premoderation of the incident neutrons.
Human lymphocytes were irradiated in vitro during Go stage by graded doses of thermal neutrons and neutrons having an average energy of 0.04; 0.09; 0.35; 0.85 and 14,7 MeV as well as by 60Co gamma rays, and RBE of neutrons relative to gamma-rays was calculated for the frequency of total and different types of aberrations. It was found that the RBE has the most value at the low doses and decreases when the exposition dose increases. 0.35 MeV neutrons have the maximum RBE in comparison with neutrons having other energies. When comparing the RBE values calculated for different types of chromosome aberrations, it was found out that dicentrics and dicentrics plus centric rings had more RBE than acentric aberrations (pair fragments and minutes).
Mice were whole-body-irradiated with 5 fractions of roentgen rays in 5 days, 5 fractions of cyclotron neutrons in 5 days, or with mixed neutron-photon fractionated radiation, in the sequence n-n-x-x-x or n-x-x-x-n. The LD50/4 day values were determined. Roentgen rays and neutrons interact in the additive manner in the mixed fractionation schemes: effective dose per fraction is as predicted from the roentgen ray-only and neutron-only experiments. This essentially agrees with HENDRY et coll. (1976). However, no trend was found towards a less-than -additive effect which was observed by those authors and has also been suggested in skin response to mixed schemes (NELSON et coll. 1975).
Zero-degree neutron energy spectra for the p(41)-Be and d(49)-Be reactions were measured by time-of-flight for neutrons with energies above 1.9 and 1.4 MeV, respectively. Spectral changes resulting from the addition of copper, aluminum, and polyethylene filters to unfiltered beams were determined. Integral yields, average energies, filter material attenuation coefficients, and kerma fractions were computed for these spectra. Calculated spectra for neutron beams filtered by various thicknesses of polyethylene compared favorably with experimental results
In this report the physical and technical bases for the realization of neutron therapy in the GDR are summarized. As neutron source a thick beryllium target which is bombarded by 13.5 MeV deuterons from the Rossendorf cyclotron is used. Dose components are measured by paired homogeneous spherical ionization chambers of polythene and graphite. The arrangement of the whole irradiation plant is resumed.
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