A comparison of 252Cf and 238Pu, Be neutron sources for partial-body in vivo activation analysis

Monte Carlo simulation of neutron irradiation facility developed for accelerator based in vivo neutron activation measurements in human hand bones

The neutron irradiation facility developed at the McMaster University 3 MV Van de Graaff accelerator was employed to assess in vivo elemental content of aluminum and manganese in human hands. These measurements were carried out to monitor the long-term exposure of these potentially toxic trace elements through hand bone levels. The dose equivalent delivered to a patient during irradiation procedure is the limiting factor for IVNAA measurements. This article describes a method to estimate the average radiation dose equivalent delivered to the patient's hand during irradiation. The computational method described in this work augments the dose measurements carried out earlier [Arnold et al., 2002. Med. Phys. 29(11), 2718-2724]. This method employs the Monte Carlo simulation of hand irradiation facility using MCNP4B. Based on the estimated dose equivalents received by the patient hand, the proposed irradiation procedure for the IVNAA measurement of manganese in human hands [Arnold et al., 2002. Med. Phys. 29(11), 2718-2724] with normal (1 ppm) and elevated manganese content can be carried out with a reasonably low dose of 31 mSv to the hand. Sixty-three percent of the total dose equivalent is delivered by non-useful fast group (> 10 keV); the filtration of this neutron group from the beam will further decrease the dose equivalent to the patient's hand.

Of mermaids and mountains. Three decades of prompt activation in vivo

During 1966 to 1972, several laboratories demonstrated the feasibility of measuring the major body elements H, N, Ca, and Cl by prompt gamma in vivo neutron activation analysis (PGIVNA). The MERMAID facility in Birmingham, England used a cyclotron-produced pulsed neutron beam, but other groups in the United Kingdom, United States, Canada, and New Zealand subsequently developed systems based on radioisotope neutron sources that could measure body nitrogen with a precision of a margin of error of a few percentage points. The accuracy of N measurement was greatly enhanced by Vartsky's internal standardization, using prompt-gamma H as the marker and total body hydrogen (based on total body water and skinfolds) as the reference. Chlorine and extracellular water volume were used in a similar way by the Swansea group to calibrate the prompt-gamma analysis of total body calcium. The PGIVNA technique is most valuable in assessing nutritional status, particularly in relation to body protein.

A 252Cf-based instrument for in vivo body protein monitoring in cancer patients

A hospital-based facility for in vivo prompt gamma neutron activation analysis of nitrogen for body protein determination is described. The patient is laid on a movable couch and is scanned with a vertically collimated neutron beam from a 252Cf neutron source (the amount of Cf varying from 120 to 40 microg due to the physical decay) positioned below the patient. Four large NaI(Tl) detectors are used to measure the 10.8 MeV gamma-rays from nitrogen. To check the long-term stability of the system, a solid phantom simulating the geometry of the adult human trunk, having similar elemental composition as tissue, was constructed. Repeated phantom measurements over 6 months gave a reproducibility in nitrogen determination of 2.9% (1 SD). Duplicate patient measurements carried out within a week showed a reproducibility of 5% (1 SD). A calibration method for absolute protein measurements in patients is presented. Patients are normally measured for 40 min; giving a mean whole-body equivalent dose of 0.25 mSv. Results from measurements on 13 cancer patients are presented.

A review of in vivo experimental methods to determine the composition of the human body

This review of experimental methods employed in the measurement of the composition of the human body covers the developments that have occurred over the past 30 years. Early methods such as hydrodensitometry and skinfold anthropometry have been superseded by dual-energy x-ray absorptiometry and bioelectrical impedance spectroscopy. The measurement of the whole-body abundance of certain elements by isotopic dilution, neutron activation analysis and x-ray fluorescence can give important information of clinical significance, but neutron activation facilities remain available in only a few centres worldwide. The relatively simple, rapid and risk-free electrical methods such as multifrequency bioelectrical impedance analysis, which can be employed at the bedside, have been found to be more complicated in their interpretation. Electromagnetic methods may only measure the composition of the human body at its surface. X-ray computed tomography and magnetic resonance imaging have not yet been employed much in body composition measurements. Some models for the composition of the human body are reviewed.

Prompt-gamma neutron activation facility for measuring body nitrogen in vivo in small animals

We have designed a prompt-gamma neutron activation facility for in vivo measurements of total body N in small animals. The facility incorporates a 252C neutron source with an emission rate of 3.2 x 10(8) n s-1 (140 micrograms), and a heavy-water neutron collimator-moderator assembly, together providing an optimum thermal flux-to-dose ratio for a 0.25-0.5 kg animal. Using two NaI(Tl) detectors we can attain a fractional statistical error of measurement of 3.5% for a dose equivalent of approx 50 mSv, sufficiently low that serial measurements can be made on the same animal.

Design studies related to an in vivo neutron activation analysis facility for measuring total body nitrogen

Design studies relating to an in vivo prompt capture neutron activation analysis facility measuring total body nitrogen are presented. The basis of the design is a beryllium-graphite neutron collimator and reflector configuration for (alpha, n) type radionuclide neutron sources (238PuBe or 241AmBe), so as to reflect leaking, or out-scattered, neutrons towards the subject. This improves the ratio of thermal neutron flux to dose and the spatial distribution of thermal flux achieved with these sources, whilst retaining their advantage of long half-lives as compared to 252Cf based systems. The common problem of high count-rate at the detector, and therefore high nitrogen region of interest background due to pile-up, is decreased by using a set of smaller (5.1 cm diameter x 10.2 cm long) NaI(Tl) detectors instead of large ones. The facility described presents a relative error of nitrogen measurement of 3.6% and a nitrogen to background ratio of 2.3 for 0.45 mSv skin dose (assuming ten 5.1 cm x 10.2 cm NaI(Tl) detectors).

A total body nitrogen facility for paediatric use

The design, calibration and evaluation of a facility for in vivo prompt gamma neutron capture analysis of total body nitrogen in children is described. The patient is scanned in both supine and prone positions, across a vertically collimated beam from a 1 GBq 252Cf fission source. Two NaI(T1) detectors are placed on either side of the patient, perpendicular to both the neutron beam and the scanning direction. The effective dose equivalent delivered to a child during an 840 s scan is approximately 0.14 mSv (QF = 10). Correction factors for nitrogen background (width-dependent), hydrogen background (1-4% of hydrogen gamma ray peak) and the differential attenuation of nitrogen and hydrogen gamma rays (width-dependent) can be applied to the measured nitrogen-to-hydrogen gamma ray counts ratio. By using the mass of hydrogen (based on body mass and fat mass) as an internal standard, the nitrogen mass can then be determined. Measurements with a urea-containing box phantom show that the current precision (CV) of the net nitrogen counts and of the nitrogen-to-hydrogen counts ratio is +/- 2.0% and +/- 1.5%, respectively. Using small anthropomorphic and other phantoms, estimation of the mass of nitrogen has a precision of +/- 1.4 to 5.4% and an accuracy of 97.1 to 101.5%.

An improved in vivo neutron activation system for measuring kidney cadmium

An in vivo neutron activation system for measuring kidney cadmium has been redesigned, firstly to reduce ambient dose levels and, secondly, to improve the cadmium signal to neutron dose ratio by modifying the neutron spectrum from 238Pu/Be, by interposing a beryllium premoderator. The ambient dose was reduced by a factor of seven. The overall system performance (lower limit of detection for a given dose) was improved by 40-50%. This 238Pu/Be based system now performs as well as or better than analogous 252Cf systems, without the drawback of the relatively short half life of 252Cf.

Measurements of total body calcium by prompt-gamma neutron activation analysis using a 252Cf source

A clinical neutron activation instrument has been developed for in vivo elemental analysis. Utilizing the prompt-capture gamma ray technique, simultaneous total body (TB) measurements of primarily Ca, but also Cl, N, C, and H are routinely performed. This paper describes a technique for the measurement of TBCa (g) that relies on the use of TBCl as an internal standard. The method has been tested with four anthropomorphic phantoms covering a range of body habitus. The mean discrepancy between the measured and known Ca contents was 3.6%. The technique has been applied to two patient groups, and encouraging results were obtained.

Calibration and evaluation of a 252Cf-based neutron activation analysis instrument for the determination of nitrogen in vivo

A novel clinical instrument for multi-element in vivo neutron activation analysis has been recently constructed in Swansea. The instrument is intended primarily for prompt gamma measurement of total and partial body calcium, total body nitrogen and partial body cadmium. For the measurement of nitrogen the subject is scanned both prone and supine across a vertical collimated neutron beam from a 4 GBq 252Cf source. Two shielded Nal(TI) detectors, each of volume 2760 cm3, are placed above the subject on the opposite side to that irradiated. The prompt gamma ray spectrum contains prominent peaks from hydrogen, nitrogen, chlorine and carbon. The optimisation, calibration and evaluation of the instrument for the measurement of nitrogen, by the reaction 14N(n, gamma)15N, is described. The calibration corrects the ratio of nitrogen-to-hydrogen counts measured from the subject for background gamma rays and the effects of body habitus. Body hydrogen is use as as internal standard. Repeated measurements of a homogeneous anthropomorphic phantom indicate that the ratio of nitrogen-to-hydrogen counts may be determined by a coefficient of variation of 1.6% for a neutron dose equivalent incident on the phantom of 0.45 mSv (QF = 10). The accuracy of the calibration was assessed by measuring three anthropomorphic phantoms (weight range: 41.4-110 kg) containing simulated skeletons and the major organs of the body. For these phantoms the mean discrepancy of the measured to the known nitrogen content was +4.9%. The simultaneous measurement of chlorine and carbon is discussed.

Apparatus for the measurement of total body nitrogen using prompt neutron activation analysis with californium-252

Details of clinical apparatus designed for the measurement of total body nitrogen (as an indicator of body protein), suitable for the critically ill, intensive-care patient are presented. Californium-252 radio-isotopic neutron sources are used, enabling a nitrogen measurement by prompt neutron activation analysis to be made in 40 min with a precision of +/- 3.2% for a whole body dose equivalent of 0.145 mSv. The advantages of Californium-252 over alternative neutron sources are discussed. A comparison between two irradiation/detection geometries is made, leading to an explanation of the geometry adopted for the apparatus. The choice of construction and shielding materials to reduce the count rate at the detectors and consequently to reduce the pile-up contribution to the nitrogen background is discussed. Salient features of the gamma ray spectroscopy system to reduce spectral distortion from pulse pile-up are presented.

A clinical instrument for multi-element in vivo analysis by prompt, delayed and cyclic neutron activation using 252Cf

The design and construction of a versatile clinical instrument for multi-element in vivo neutron activation analysis of major and minor body elements is described. A 200 micrograms (4 GBq) 252Cf neutron source is stored below ground level and pneumatically propelled to one of two irradiation ports. These deliver collimated beams of fast neutrons either to a localised volume such as the liver or kidney, or across the width of a patient for a head-to-toe scanning whole-body measurement. The source control system allows selection of either a continuous or cyclic mode of activation. The instrument is intended primarily for measurement, by the prompt-gamma technique, of total and partial body calcium, total body nitrogen and partial body cadmium. The potential of the instrument for determination of these three elements has been established. Phantom results suggest that total body calcium can be measured with a precision of +/- 2.6% (CV) for an average whole-body skin dose equivalent of 6.4 mSv; total body nitrogen with a precision of +/- 2.0% for an average whole-body skin dose equivalent of less than 0.4 mSv; and a detection limit (2 SD of the background) of 2.4 mg of cadmium in the kidney has been obtained for a radiation dose equivalent to the skin of 3 mSv (QF = 10). The suitability of this instrument for the measurement of other elements is also discussed.

Effect of collimator and depth in a phantom on the neutron spectrum from a 238Pu,Be neutron source

A study has been made of some factors influencing the fast neutron spectrum emerging from the aperture of a collimated 238Pu,Be source, and influencing the spectrum at a depth in a water phantom, using a miniature liquid scintillator fast neutron spectrometer. The greatest changes in the spectrum emerging from the aperture were produced by changes in the length of the collimator and the field size of the collimator. No difference between the source spectrum above 1.5 MeV of 370 GBq (10 Ci) and 740 GBq (20 Ci) 238Pu,Be sources and a 37 GBq (1 Ci) 241Am,Be source was observed. Graphite was found to be a slightly more efficient reflector than steel or lead, and much better than wax. The mean energy and the proportion of the total neutron fluence with an energy between 1.5 MeV and 3.5 MeV reached a minimum and a maximum value respectively with increase in depth in the phantom. With further increase in depth, the two parameters increased and decreased respectively. The depth at which these minimum and maximum values occurred increased with field size. The overall changes through 15 cm depth in the mean energy and in the low energy fluence proportion were small (less than or equal to +/- 5%). No significant changes were detected in the spectral shape after the neutron beam traversed an air cavity or a bovine tibia in the phantom.