ABSTRACT
The evaluation of possible improvement in the use of Gd in cancer therapy, in reference to gadolinium in cancer therapy (GdNCT), has been analysed. At first the problem of the gadolinium compounds toxicity was reviewed identifying the Motexafin Gadolinium as the best. Afterwards, the spectrum of IC and Auger electrons was calculated using a special method. Afterwards, this electron source has been used as input of the PENELOPE code and the energy deposit in DNA was well defined. Taking into account that the electron yield and energy distribution are related to the neutron beam spectrum and intensity, the shaping assembly architecture was optimised through computational investigations. Finally the study of GdNCT was performed from two different points of view: macrodosimetry using MCNPX, with calculation of absorbed doses both in tumour and healthy tissues, and microdosimetry using PENELOPE, with the determination of electron RBE through the energy deposit. The equivalent doses were determined combining these two kinds of data, introducing specific figures of merit to be used in treatment planning system (TPS). According to these results, the GdNCT appears to be a fairly possible tumour therapy.
Subject(s)
Gadolinium/therapeutic use , Neoplasms/radiotherapy , Neutron Capture Therapy/methods , Radiation-Sensitizing Agents/therapeutic use , Gadolinium/pharmacokinetics , Gadolinium/toxicity , Humans , Isotopes/pharmacokinetics , Isotopes/therapeutic use , Isotopes/toxicity , Monte Carlo Method , Neutron Capture Therapy/statistics & numerical data , Neutron Capture Therapy/trends , Radiation-Sensitizing Agents/pharmacokinetics , Radiation-Sensitizing Agents/toxicity , Radiotherapy Planning, Computer-Assisted/statistics & numerical dataABSTRACT
The management of radioactive waste is a key issue for the present and future use of nuclear energy. In this frame, high temperature reactors (HTRs) have, among others, the capability to burn actinides. After a short introduction on HTRs, the performances of two MC-based burnup codes (Monte Carlo continuous energy burnup and MONTEBURNS) in assessing the ability of these reactors to burn actinides are compared. These codes are necessary for performing ultra-high burnup calculations on HTRs. The best one, in this specific case, results to be MONTEBURNS. It was analysed using HTRs loaded with the following: (1) 1st generation Pu, 600 equivalent full power days; (2) 2nd generation Pu, 645 equivalent full power days; and (iii) 33% 1st generation Pu and 67% Th, 705 equivalent full power days. Finally, it is possible to conclude that HTRs can reduce time when the waste is considered dangerous. Even if the amount of reduction does not solve the whole problem, it represents an important step in the management of radioactive waste.
Subject(s)
Industrial Waste/prevention & control , Nuclear Reactors , Radiation Monitoring/methods , Radiation Protection/instrumentation , Radioisotopes/analysis , Radioisotopes/chemistry , Refuse Disposal/instrumentation , Computer Simulation , Equipment Failure Analysis/methods , Half-Life , Hot Temperature , Models, Chemical , Models, Statistical , Radiation Dosage , Radiation Protection/methods , Radioisotopes/toxicity , Risk Assessment/methods , Risk FactorsABSTRACT
Gadolinium has been recently proposed, as neutron capture agent in NCT (Neutron Capture Therapy), due to both the nuclide high neutron capture cross section, and the remarkable selective uptake inside tumour tissue that Gd-loaded compounds, can provide. When a neutron external source is supplied, different Gd nuclear reactions, and the generated Auger electrons in particular, cause a high local energy deposition, which results in a tumour cell inactivation. Preliminary micro- as well as macrodosimetric Monte Carlo computational investigations show that the tumour-to-healthy tissue biological damage ratio is in close relation to the neutron beam energy spectrum. The results points out that the optimum neutron spectrum, to be used for Gd-NCT, seems to lie in the 1 to 10 keV energy range. In order to 'tailor' such spectra, an original, accelerator-driven, neutron source and spectrum shaping assembly for hospital-based Gd-NCT are presented and preliminary results are reported.
