Search PubMed⌕ Search

SEARCH · Search PubMed

Results for “NEUTRONS”

Search indexed PubMed citations on genomics, clinical trials, systematic reviews and public health. Explore titles, authors and supplied subject terms, then open the PubMed record.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 181 records · Page 10Linked to original sources
PubMed1993

RBE in fast neutron therapy and in boron neutron capture therapy. A useful concept or a misuse?

In high-LET radiation therapy, radiation quality and radiation quality differences have to be taken into account and specified. In fast neutron therapy, an operational approach has been adopted which is based on the concept of "clinical RBE". The paper discusses the quantities of RBE (relative biological effectiveness), reference RBE and clinical RBE and their relationship and significance in radiation therapy. In particular, the difference between the well defined RBE in radiation biology and the clinical RBE which is based on the judgement of radiotherapists is elucidated and emphasized. The clinical RBE is based on the reference RBE and implicitly includes differences in physical selectivity of the irradiation beams and clinical experience. The particular aspects of radiation quality in boron neutron capture therapy (BNCT) are due to the poor penetration of the primary beam, the inhomogeneity of the spatial distribution of 10B nuclides in the irradiated tissue and the short range of the alpha-particles emitted after neutron capture in 10B. The related problems in accounting for radiation quality in BNCT and in the applicability of the clinical RBE concept are discussed.

Boron Neutron Capture Therapy↗
PubMed1990

Monte Carlo methods of neutron beam design for neutron capture therapy at the MIT Research Reactor (MITR-II).

Monte Carlo methods of coupled neutron/photon transport are being used in the design of filtered beams for Neutron Capture Therapy (NCT). This method of beam analysis provides segregation of each individual dose component, and thereby facilitates beam optimization. The Monte Carlo method is discussed in some detail in relation to NCT epithermal beam design. Ideal neutron beams (i.e., plane-wave monoenergetic neutron beams with no primary gamma-ray contamination) have been modeled both for comparison and to establish target conditions for a practical NCT epithermal beam design. Detailed models of the 5 MWt Massachusetts Institute of Technology Research Reactor (MITR-II) together with a polyethylene head phantom have been used to characterize approximately 100 beam filter and moderator configurations. Using the Monte Carlo methodology of beam design and benchmarking/calibrating our computations with measurements, has resulted in an epithermal beam design which is useful for therapy of deep-seated brain tumors. This beam is predicted to be capable of delivering a dose of 2000 RBE-cGy (cJ/kg) to a therapeutic advantage depth of 5.7 cm in polyethylene assuming 30 micrograms/g 10B in tumor with a ten-to-one tumor-to-blood ratio, and a beam diameter of 18.4 cm. The advantage ratio (AR) is predicted to be 2.2 with a total irradiation time of approximately 80 minutes. Further optimization work on the MITR-II epithermal beams is expected to improve the available beams.

Brain Neoplasms↗
PubMed2004

Moderated 252Cf neutron energy spectra in brain tissue and calculated boron neutron capture dose.

While there is significant clinical experience using both low- and high-dose (252)Cf brachytherapy, combination therapy using (10)B for neutron capture therapy-enhanced (252)Cf brachytherapy has not been performed. Monte Carlo calculations were performed in a brain phantom (ICRU 44 brain tissue) to evaluate the dose enhancement predicted for a range of (10)B concentrations over a range of distances from a clinical (252)Cf source. These results were compared to experimental measurements and calculations published in the literature. For (10)B concentrations </=50 microg/g, the (10)B neutron capture dose enhancement was small in comparison to the (252)Cf fast neutron dose.

Boron Neutron Capture Therapy↗
PubMed2001

Optimal timing of neutron irradiation for boron neutron capture therapy after intravenous infusion of sodium borocaptate in patients with glioblastoma.

PURPOSE: A cooperative study in Europe and Japan was conducted to determine the pharmacokinetics and boron uptake of sodium borocaptate (BSH: Na(2)B(12)H(11)SH), which has been introduced clinically as a boron carrier for boron neutron capture therapy in patients with glioblastoma. METHODS AND MATERIALS: Data from 56 patients with glioblastoma who received BSH intravenous infusion were retrospectively reviewed. The pharmacokinetics were evaluated in 50 patients, and boron uptake was investigated in 47 patients. Patients received BSH doses between 12 and 100 mg/kg of body weight. For the evaluation, the infused boron dose was scaled linearly to 100 mg/kg BSH. RESULTS: In BSH pharmacokinetics, the average value for total body clearance, distribution volume of steady state, and mean residence time was 3.6 +/- 1.5 L/h, 223.3 +/- 160.7 L, and 68.0 +/- 52.5 h, respectively. The average values of the boron concentration in tumor adjusted to 100 mg/kg BSH, the boron concentration in blood adjusted to 100 mg/kg BSH, and the tumor/blood boron concentration ratio were 37.1 +/- 35.8 ppm, 35.2 +/- 41.8 ppm, and 1.53 +/- 1.43, respectively. A good correlation was found between the logarithmic value of T(adj) and the interval from BSH infusion to tumor tissue sampling. About 12-19 h after infusion, the actual values for T(adj) and tumor/blood boron concentration ratio were 46.2 +/- 36.0 ppm and 1.70 +/- 1.06, respectively. The dose ratio between tumor and healthy tissue peaked in the same interval. CONCLUSION: For boron neutron capture therapy using BSH administered by intravenous infusion, this work confirms that neutron irradiation is optimal around 12-19 h after the infusion is started.

Adult↗
PubMed1998

Boron neutron-capture therapy (BNCT) for glioblastoma multiforme (GBM) using the epithermal neutron beam at the Brookhaven National Laboratory.

OBJECTIVE: Boron neutron-capture therapy (BNCT) is a binary form of radiation therapy based on the nuclear reactions that occur when boron (10B) is exposed to thermal neutrons. Preclinical studies have demonstrated the therapeutic efficacy of p-boronophenylalanine (BPA)-based BNCT. The objectives of the Phase I/II trial were to study the feasibility and safety of single-fraction BNCT in patients with GBM. MATERIALS AND METHODS: The trial design required (a) a BPA biodistribution study performed at the time of craniotomy; and (b) BNCT within approximately 4 weeks of the biodistribution study. From September 1994 to July 1995, 10 patients were treated. For biodistribution, patients received a 2-hour intravenous (i.v.) infusion of BPA-fructose complex (BPA-F). Blood samples, taken during and after infusion, and multiple tissue samples collected during surgical debulking were analyzed for 10B concentration. For BNCT, all patients received a dose of 250 mg BPA/kg administered by a 2-hour i.v. infusion of BPA-F, followed by neutron beam irradiation at the Brookhaven Medical Research Reactor (BMRR). The average blood 10B concentrations measured before and during treatment were used to calculate the time of reactor irradiation that would deliver the prescribed dose. RESULTS: 10B concentrations in specimens of scalp and tumor were higher than in blood by factors of approximately 1.5 and approximately 3.5, respectively. The 10B concentration in the normal brain was < or = that in the blood; however, for purposes of estimating radiation doses to normal brain endothelium, it was always assumed to be equal to blood. BNCT doses are expressed as gray-equivalent (Gy-Eq), which is the sum of the various physical dose components multiplied to appropriate biologic effectiveness factors. The dose to a 1-cm3 volume where the thermal flux reached a maximum was 10.6 +/- 0.3 Gy-Eq in 9 patients and 13.8 Gy-Eq in 1 patient. The minimum dose in tumor ranged from 20 to 32.3 Gy-Eq. The minimum dose in the target volume (tumor plus 2 cm margin) ranged from 7.8 to 16.2 Gy-Eq. Dose to scalp ranged from 10 to 16 Gy-Eq. All patients experienced in-field alopecia. No CNS toxicity attributed to BNCT was observed. The median time to local disease progression following BNCT was 6 months (range 2.7 to 9.0). The median time to local disease progression was longer in patients who received a higher tumor dose. The median survival time from diagnosis was 13.5 months. CONCLUSION: It is feasible to safely deliver a single fraction of BPA-based BNCT. At the dose prescribed, the patients did not experience any morbidity. To further evaluate the therapeutic efficacy of BNCT, a dose-escalation study delivering a minimum target volume dose of 17 Gy-Eq is in progress.

Aged↗
PubMed1997

Neutron Laue diffractometry with an imaging plate provides an effective data collection regime for neutron protein crystallography.

Neutron quasi-Laue diffraction data (2 A resolution) from tetragonal hen egg-white lysozyme were collected in ten days with neutron imaging plates. The data processing Laue software, LAUEGEN, developed for X-ray Laue diffractometry, was adapted for neutron diffractometry with a cylindrical detector. The data analysis software, X-PLOR, was modified and used for the refinement of hydrogen atoms, and the positions of 960 hydrogen atoms in the protein and 157 bound water molecules, were determined. Several examples are given of the methods used to identify hydrogen atoms and water molecules.

Animals↗
PubMed2004

The use of passive personal neutron dosemeters to determine the neutron dose equivalent component of radiation fields in spacecraft.

For the altitude range and inclination of the International Space Station (ISS), secondary neutrons can be a major contributor to dose equivalent inside a spacecraft. The exact proportion is very dependent on the amount of shielding of the primary galactic cosmic radiation and trapped particles, but is likely to lie in the range of 10-50%. Personal neutron dosemeters of simple design, processed using simple techniques developed for personal dosimetry, may be used to estimate this neutron component.

Body Burden↗
PubMed2004

Neutron detection and neutron dosimetry.

A review is presented on the research and development of inorganic scintillators for position-sensitive thermal neutron detectors to be used at new spallation neutron sources. Furthermore some recent developments in the field of fast-neutron dosimetry will be discussed.

Equipment Design↗
PubMed2005

Characteristics of high-energy neutrons estimated using the radioactive spallation products of Au at the 500-MeV neutron irradiation facility of KENS.

We carried out a shielding experiment of high-energy neutrons, generated from a tungsten target bombarded with primary 500-MeV protons at KENS, which penetrated through a concrete shield in the zero-degree direction. We propose a new method to evaluate the spectra of high-energy neutrons ranging from 8 to 500 MeV. Au foils were set in a concrete shield, and the reaction rates for 13 radionuclides produced by the spallation reactions on the Au targets were measured by radiochemical techniques. The experimental results were compared with those obtained by the MARS14 Monte-Carlo code. A good agreement (between them) was found for energies beyond 100 MeV. The profile of the neutron spectrum, ranging from 8 to 500 MeV, does not depend on the thickness of the concrete shield.

Algorithms↗
PubMed1992

Detection system for measuring dose equivalent from fast neutrons in mixed gamma-neutron fields.

A hybrid detector for measuring fast neutrons in mixed gamma-neutron fields is discussed in this paper. The detector consists of an ionization chamber with components made from a plastic scintillator. Its operation is based on the two detection systems thus combined. Its parameters and domain of applicability are explained. This paper proposes a rapid integral method for measuring the neutron-dose equivalent based on this detector, which allows a good separation of the gamma component.

Fast Neutrons↗
PubMedDate not supplied

Neutron energy spectra of d(49)-Be and p(41)-Be neutron radiotherapy sources.

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

Fast Neutrons↗
PubMedDate not supplied

Determination of the neutron and photon spectra of a clinical fast neutron beam.

A simple technique to determine the neutron and photon spectra of a clinical fast neutron beam is described. This technique involves making narrow beam attenuation measurements with a pair of ionization chambers and an iterative fitting program to analyze the data. A method is also described for determining the first-guess neutron spectrum for input into the iterative program. The results of the analysis yield spectra suitable for use in dose calculation algorithms and dosimetry protocols. Presented here is the first-known published photon spectrum from a clinical machine.

Humans↗
PubMed2002

Measurement of residual 60Co activity induced by atomic-bomb neutrons in Nagasaki and background contribution by environmental neutrons.

Residual 60Co activity in five steel samples induced by neutrons from the Nagasaki atomic bomb has been measured within about 1000 m from the hypocenter. The chemical separation of cobalt and nickel from steel samples was performed, and cobalt-enriched samples were prepared for all samples. Gamma-ray measurements were carried out with a low-background well-type germanium detector. The gamma-ray spectra for five samples were compared with the spectrum of a control sample to ensure that the observed 60Co was actually induced by A-bomb neutrons. The activation of cobalt by environmental neutrons was also investigated. It has been shown that the present 60Co data are consistent with earlier Hashizume's data.

Background Radiation↗
PubMed2003

Measurement of residual 152Eu activity induced by atomic bomb neutrons in Nagasaki and the contribution of environmental neutrons to this activity.

Residual 152Eu activities induced by neutrons from the Nagasaki atomic bomb were measured for nine mineral samples located up to 1,061 m in the slant range and one control sample at 2,850 m from the hypocenter. A chemical separation to prepare europium-enriched samples was performed for all samples, and gamma ray measurements were carried out with a low background well-type germanium detector. In this paper, the measured specific activities of 152Eu are compared with activation calculations based on the DS86 neutron fluence and the 93Rev one. The calculated-to-measured ratios are also compared with those of 60Co and 36Cl. The present results indicate that the measurements agree to the calculation within a factor of three as observed in the nuclear tests at Nevada. The activation level of environmental neutrons and the detection limit for 152Eu are also discussed.

Background Radiation↗
PubMed1986

[Shielding design and detection of neutrons from medical and industrial electron accelerators--accuracy evaluation of simple calculation method by neutron measurement].

The accuracy of new simple method of design calculation for neutron shielding in medical and industrial electron accelerator facilities, described in the preceding paper, is investigated in this work by comparing with the measured data in the actual facilities. For this comparison, several published data which have been measured in medical electron accelerator facilities were used, and in industrial facilities the measurement was performed in this work with a neutron dose equivalent meter. From the comparison of measured and calculated neutron dose equivalents, it was confirmed that this simple design method has sufficiently good accuracy.

Electrons↗
PubMed1992

Assessment of ideal neutron beams for neutron capture therapy.

The discrete-ordinates transport computer code DORT has been used to develop a two-dimensional cylindrical phantom model for use as a tool to assess beam design and dose distributions for boron neutron capture therapy. The model uses an S8 approximation for angular fluxes and a P3 Legendre approximation for scattering cross sections. A one-dimensional discrete-ordinates model utilizing the computer code ANISN was used to validate the energy-group structure used in the two-dimensional calculations. In the two-dimensional model the effects of varying basic parameters such as aperture width, neutron source energy, and tissue composition have been studied. Identical results were obtained when comparing narrow beam calculations to fine-mesh higher-order Sn treatments (up to S32), and with P5 cross sections. It is shown that, when the correct assessment volume is used, narrow beams will give little or no advantage for therapy even with an optimum-energy ideal neutron beam.

Boron Neutron Capture Therapy↗
PubMed1991

[Boron neutron capture therapy of human gastric cancer by boron-containing immunoliposomes under thermal neutron irradiation].

Boron neutron capture therapy (BNCT) is based on the nuclear reaction yielding high LET Li-7 and alpha particles when boron-10 is irradiated with thermal neutrons. (Et4N)2(10)B10H10 was entrapped in 40 nm liposomes coating the monoclonal antibody, MGb 2, against human gastric cancer. There were 1.4 x 10(4) 10B atoms encapsulated and 20 molecules of MGb 2 incorporated per liposomes ELISA indicated that the immunoreactivity of antibodies on liposomes retained 80%. Preferred binding to human gastric cancer cell line SGC-7901 was observed as many as 15.1 x 10(9) 10B atoms/tumor cell, 38-fold more than that to normal human embryonic lung cell line SL 7. The fluorescent immunoliposome-stained tumor cells showed membrane-fluorescence while SL 7 cells showed no obvious fluorescence. Irradiated with thermal neutrons (0.025 eV, 3.12 x 10(11)n/cm2, gamma-ray 0.84 Gy), 10B-containing immunoliposomes pretreated SGC-7901 cells survived 27%, significantly lower than non-irradiated cells or non-pretreated cells with irradiation (P less than 0.001). The results demonstrated that boron-containing immunoliposomes could bind selectively and deliver sufficient amount of boron-10 to the target tumor cells.

Alpha Particles↗
PubMed1985

[Principle of the 2-peak thermoluminescent dosimetry method for the simultaneous determination of neutron-gamma energy doses in mixed neutron-photon radiation fields].

The LET dependence of the response of different glow-peaks of CaF2 : Tm (TLD-300) detectors can be used for separate simultaneous determination of neutron and gamma-ray absorbed doses in mixed neutron-photon radiation fields. The principle the pre-conditions of this "two-peak TLD method" are explained using experimental results with d(14) + Be neutrons (EN = 5,8 MeV).

Fast Neutrons↗