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W E Bolch

Publications and source records attributed to W E Bolch.

At least 37 records · Page 2Linked to original sources
PubMed2001

Comparison of angular free-in-air and tissue-equivalent phantom response measurements in p-MOSFET dosimeters.

Metal Oxide Semiconductor Field Effect Transistor (MOSFET) radiation dosimeters have found recent application in providing real-time measurement in diagnostic radiology as well as in radiotherapy. Due to the design of the MOSFET dosimeter, the response is dependent on both energy and angulation with respect to the direction of primary radiation. The axial angular dependence has been characterized for both free-in-air and for tissue-equivalent phantoms. However, neither the angular dependence normal (90-degree) to the axial rotation, nor the effects of various tissue compositions on angular dependence, have been investigated for radiation energies in the diagnostic range. To characterize the angular dependence normal to the axial rotation, we exposed three "high sensitivity" MOSFET dosimeters simultaneously to x-rays from a medical diagnostic x-ray unit over a 360-degree rotation, at 22.5-degree increments, for both free-in-air and in lung, skeletal, and soft tissue-equivalent phantoms. The MOSFET dosimeters clearly showed an angular dependence in the orientation normal-to-axial as well as in the axial rotation, both for free-in-air and in tissue-equivalent phantoms. Significant variations in response occurred when the MOSFETs were exposed at incident angles between 90 degrees and 180 degrees normal-to-axial, as compared to the normal position (i.e., the zero-degree position with the bubble-side of the MOSFETs facing the radiation source). A maximum decrease in response to 32% of normal was observed when the distal ends (end opposite the wire lead) of the dosimeters were pointing directly away from the x-ray source (270-degree position). To avoid significant errors in MOSFET dosimeter readings, placement of the dosimeters should be consistent, and care should be taken to avoid orienting the dosimeter with its sensitive region (bubble side) facing away from the source of primary radiation at particular angles.

Calibration↗
PubMed2001

Influences of parameter uncertainties within the ICRP 66 respiratory tract model: particle deposition.

Risk assessment associated with the inhalation of radioactive aerosols requires as an initial step the determination of particle deposition within the various anatomic regions of the respiratory tract. The model outlined in ICRP Publication 66 represents to date one of the most complete overall descriptions of not only particle deposition, but of particle clearance and local radiation dosimetry of lung tissues. In this study, a systematic review of the deposition component within the ICRP 66 respiratory tract model was conducted in which probability density functions were assigned to all input parameters. These distributions were subsequently incorporated within a computer code LUDUC (LUng Dose Uncertainty Code) in which Latin hypercube sampling techniques are used to generate multiple (e.g., 1,000) sets of input vectors (i.e., trials) for all of the model parameters needed to assess particle deposition within the extrathoracic (anterior and posterior), bronchial, bronchiolar, and alveolar-interstitial regions of the ICRP 66 respiratory tract model. Particle deposition values for the various trial simulations were shown to be well described by lognormal probability distributions. Geometric mean deposition fractions from LUDUC were found to be within approximately +/- 10% of the single-value estimates from the LUDEP computer code for each anatomic region and for particle diameters ranging from 0.001 to 50 microm. In all regions of the respiratory tract, LUDUC simulations for an adult male at light exertion show that uncertainties in particle deposition fractions are distributed only over a range of about a factor of approximately 2-4 for particle sizes between 0.005 to 0.2 microm. Below 0.005 microm, uncertainties increase only for deposition within the alveolar region. At particle sizes exceeding 1 microm, uncertainties in the deposition fraction within the extrathoracic regions are relatively small, but approach a factor of 20 for deposition in the bronchial region. Deposition fractions for particles above 1 microm become very uncertain within the deeper regions of the lungs (bronchiolar and alveolar-interstitial).

Body Height↗
PubMed2001

Chord distributions across 3D digital images of a human thoracic vertebra.

Radiation dose estimates to the trabecular region of the skeleton are of primary importance due to recent advancements in nuclear medicine. Establishing methods for accurately calculating dose in these regions is difficult due to the complex microstructure of this anatomic site and the typical ranges of beta-particles in both bone and marrow tissues. At the present time, models of skeletal dosimetry used in clinical medicine rely upon measured distributions of straight-line path lengths (chord lengths) through bone and marrow regions. This work develops a new three-dimensional, digital method for acquiring these distributions within voxelized images. In addition, the study details the characteristics of measuring chord distributions within digital images and provides a methodology for avoiding undesirable pixel or voxel effects. The improved methodology has been applied to a digital image (acquired via NMR microscopy) of the trabecular region of a human thoracic vertebra. The resulting chord-length distributions across both bone trabeculae and bone marrow cavities were found to be in general agreement with those measured in other studies utilizing different methods. In addition, this study identified that bone and marrow space chord-length distributions are not statistically independent, a condition implicitly assumed within all current skeletal dosimetry models of electron transport. The study concludes that the use of NMR microscopy combined with the digital measurement techniques should be used to further expand the existing Reference Man database of trabecular chord distributions to permit the development of skeletal dosimetry models which are more age and gender specific.

Bone Marrow↗
PubMed2001

Beta-particle dosimetry of the trabecular skeleton using Monte Carlo transport within 3D digital images.

Presently, skeletal dosimetry models utilized in clinical medicine simulate electron path lengths through skeletal regions based upon distributions of linear chords measured across bone trabeculae and marrow cavities. In this work, a human thoracic vertebra has been imaged via nuclear magnetic resonance (NMR) spectroscopy yielding a three-dimensional voxelized representation of this skeletal site. The image was then coupled to the radiation transport code EGS4 allowing for 3D tracing of electron paths within its true 3D structure. The macroscopic boundaries of the trabecular regions, as well as the cortex of cortical bone surrounding the bone site, were explicitly considered in the voxelized transport model. For the case of a thoracic vertebra, energy escape to the cortical bone became significant at source energies exceeding approximately 2 MeV. Chord-length distributions were acquired from the same NMR image, and subsequently used as input for a chord-based dosimetry model. Differences were observed in the absorbed fractions given by the chord-based model and the voxel transport model, suggesting that some of the input chord distributions for the chord-based models may not be accurate. Finally, this work shows that skeletal mass estimates can be made from the same NMR image in which particle transport is performed. This feature allows one to determine a skeletal S-value using absorbed fraction and mass data taken from the same anatomical tissue sample. The techniques developed in this work may be applied to a variety of skeletal sites, thus allowing for the development of skeletal dosimetry models at all skeletal sites for both males and females and as a function of subject age.

Age Factors↗
PubMed2001

Dosimetric effect of source centering and residual plaque for beta-emitting catheter based intravascular brachytherapy sources.

Catheter-based radiation delivery systems employing both beta-particle and gamma-ray emitters are currently being investigated for their efficacy in addressing restenosis following percutaneous coronary intervention (PCI). The dosimetric consequences of source centering within the arterial lumen and presence of residual plaque are potentially important issues for the uniform delivery of dose to the arterial tissue. In this study, we have examined the effect of source centering on the resulting dose to the arterial wall from clinical intravascular brachytherapy sources containing 32P and 90Sr/Y90. Monte Carlo simulations using the MCNP code were performed for these catheter-based sources with offsets of 0.5 mm and 1 mm from the center of the arterial lumen in homogenous water medium as well as in the presence of residual plaque. Three different positions were modeled and the resulting dose values were analyzed to assess their impact on the resulting dose distribution. The results indicate a variation ranging from -40% to +70% for 32P source and -30% to +50% for 90Sr/90Y at a radial distance of 2 mm from the center of the coronary artery, relative to the dose from a centered source, for a 0.5 mm offset. The variation for a 1 mm offset ranges from -65% to +182% for 32P source and to -50% to +140% for 90Sr/90Y. A concentric residual plaque layer was also modeled so as to assess the combined influence of offset and residual plaque on the dosimetry. Finally the effect of cardiac motion and its potential impact on catheter position and hence the dose distribution is also examined by considering two separate cases of catheter displacement. The results indicate that dose variations range between -28% to +91% when it is assumed that cardiac motion causes catheter movement during coronary lesion irradiation.

Beta Particles↗
PubMed2000

Voxel size effects in three-dimensional nuclear magnetic resonance microscopy performed for trabecular bone dosimetry.

An important problem in internal dosimetry is the assessment of energy deposition by beta particles within trabecular regions of the skeleton. Recent dosimetry methods for trabecular bone are based on Monte Carlo particle transport simulations within three-dimensional (3D) images of real human bone samples. Nuclear magnetic resonance (NMR) microscopy is a 3D imaging technique of choice due to the large signal differential between bone tissue and the water-filled marrow cavities. Image voxel sizes currently used in NMR microscopy are between 50 microm and 100 microm, but the images are time consuming to acquire and can only be performed at present for in vitro samples. It is therefore important to evaluate what resolution is best suitable in order to properly characterize the trabecular microstructure, to adequately predict the tissue dosimetry, and to minimize imaging time. In this work, a mathematical model of trabecular bone, composed of a distribution of spherical marrow cavities, was constructed. The mathematical model was subsequently voxelized with different voxel sizes (16 microm to 1,000 microm) to simulate 3D NMR images. For each image, voxels are assigned to either bone or marrow according to their enclosed marrow fraction. Next, the images are coupled to the EGS4 electron transport code and absorbed fractions to bone and marrow are calculated for a marrow source of monoenergetic electrons. Radionuclide S values are also determined for the voxelized images with results compared to data calculated for the pure mathematical sample. The comparison shows that for higher energy electrons (>400 keV), good convergence of the results is seen even within images of poor resolution. Above 400 keV, a voxel resolution as large as 300 microm results in dosimetry errors below 5%. For low-energy electrons and high-resolution images, the self-dose to marrow is also determined to within 5% accuracy. Nevertheless, increased voxelization of the image overestimates the surface area of the bone-marrow interface leading to errors in the cross-dose to bone as high as 25% for some low-energy beta emitters.

Bone Marrow↗
PubMed2000

Protection by DMSO against cell death caused by intracellularly localized iodine-125, iodine-131 and polonium-210.

The mechanisms by which DNA-incorporated radionuclides impart lethal damage to mammalian cells were investigated by examining the capacity of dimethyl sulfoxide (DMSO) to protect against lethal damage to Chinese hamster V79 cells caused by unbound tritium ((3)H(2)O), DNA-incorporated (125)I- and (131)I-iododeoxyuridine ((125)IdU, (131)IdU), and cytoplasmically localized (210)Po citrate. The radionuclides (3)H and (131)I emit low- and medium-energy beta particles, respectively, (125)I is a prolific Auger electron emitter, and (210)Po emits 5.3 MeV alpha particles. Cells were radiolabeled and maintained at 10.5 degrees C for 72 h in the presence of different concentrations of DMSO (5-12.5% v/v), and the surviving fraction compared to that of unlabeled controls was determined. DMSO afforded no protection against the lethal effects of the high-LET alpha particles emitted by (210)Po. Protection against lethal damage caused by unbound (3)H, (131)IdU and (125)IdU depended on the concentration of DMSO in the culture medium. Ten percent DMSO provided maximum protection in all cases. The dose modification factors obtained at 10% DMSO for (3)H(2)O, (131)IdU, (125)IdU and (210)Po citrate were 2.9 +/- 0.01, 2.3 +/- 0.5, 2.6 +/- 0.2 and 0.95 +/- 0.07, respectively. These results indicate that the toxicity of Auger electron and beta-particle emitters incorporated into the DNA of mammalian cells is largely radical-mediated and is therefore indirect in nature. This is also the case for the low-energy beta particles emitted by (3)H(2)O. In contrast, alpha particles impart lethal damage largely by direct effects. Finally, calculations of cellular absorbed doses indicate that beta-particle emitters are substantially more toxic when incorporated into the DNA of mammalian cells than when they are localized extracellularly.

Animals↗
PubMed2000

S values for radionuclides localized within the skeleton.

UNLABELLED: Calculations of radiation absorbed dose to the active marrow are important to radionuclide therapies such as radioimmunotherapy and bone pain palliation. In diagnostic nuclear medicine, calculations of the effective dose for radiopharmaceutical procedures also require the assessment of radiation dose to the skeletal endosteum. We have previously reported the development of 2 3-dimensional electron transport models for assessing absorbed fractions to both marrow and endosteum in trabecular and cortical bone, respectively. Here, we extend these calculations to the assignment of radionuclide S values. METHODS: Data published in International Commission on Radiological Protection Publication 70 were used to develop tables of masses for total marrow space, active and inactive marrow, endosteum, and bone matrix within 22 skeletal sites in the adult. Using our site-specific tissue masses, along with electron absorbed fractions given by our 3-dimensional transport models, radionuclide S values (electron and beta particle components only) were subsequently calculated using the MIRD schema for 32P, 33P, 89Sr, 90Sr, 90Y, 117mSn, 153Sm, 169Er, 177Lu, and 186Re. Specific consideration was given to the trabecular active marrow as both a source and a target region. RESULTS: Site-specific radionuclide S values are reported for 22 skeletal sites, for 9 source-target tissue combinations within trabecular bone, and for 6 source-target tissue combinations within cortical bone. Skeletal-averaged S values are also provided. CONCLUSION: A fully documented model is presented for the adult for use in radionuclide dosimetry of the skeleton. The model is based on both the latest international recommendations for skeletal tissue masses and results from three-dimensional electron transport calculations within the skeleton. Comparisons are additionally made against the radionuclide S values published in MIRD Pamphlet No. 11 and those calculated using the MIRDOSE2 and MIRDOSE3 computer codes. Differences in these datasets vary with the source-target combination considered and may be attributed to 1 of 3 causes: (a) assumptions on reference target masses, (b) transport models used to assign absorbed fractions, and (c) implicit assumptions made in considering the trabecular active marrow as both a source and a target tissue.

Adult↗
PubMed2000

Considerations in the selection of radiopharmaceuticals for palliation of bone pain from metastatic osseous lesions.

UNLABELLED: Bone pain is a common complication for terminal patients with bone metastases from prostate, lung, breast, and other malignancies. A multidisciplinary approach in treating bone pain is generally required, 1 which includes a combination of analgesic drug therapy, radiation therapy, hormonal therapy, and chemotherapy. Over the years, treatment of bone pain using bone-seeking radiopharmaceuticals has been explored extensively. Pharmaceuticals labeled with energetic 1-particle emitters such as 32p, 89Sr, 153Sm, and 186Re, in addition to the low-energy electron emitter 117mSn, have been studied for this purpose. Bone-marrow toxicity as a consequence of chronic irradiation by the energetic , particles is a general problem associated with this form of treatment. It is therefore desirable to identify radiochemicals that minimize the dose to the bone marrow and at the same time deliver therapeutic doses to the bone. METHODS: New S values (mean absorbed dose per unit cumulated activity) for target regions of human bone and marrow were used to ascertain the capacity of various radiochemicals to deliver a high bone dose while minimizing the marrow dose. The relative dosimetric advantage of a given radiopharmaceutical compared with a reference radiochemical was quantitated as a dosimetric relative advantage factor (RAF). Several radionuclides that emit energetic 1 particles (32p, 89Sr, 153Sm, 186Re, and 177Lu) and radionuclides that emit low-energy electrons or beta particles (169Er, 117mSn, and 33p) were evaluated. For these calculations, ratios of the cumulated activity in the bone relative to cumulated activity in the marrow alpha equal to 10 and 100 were used. RESULTS: When the radiopharmaceutical was assumed to be uniformly distributed in the endosteum and alpha was taken as 100 for both the reference and test radiochemicals, the RAF values compared with the reference radionuclide 32p were 1.0, 1.2, 1.4, 1.6, 1.7, 1.9, and 2.0 for 89Sr, 186Re, 153Sm, 177Lu, 169Er, 117mSn, and 33P, respectively. In contrast, when the radiopharmaceutical is assumed to be uniformly distributed in the bone volume, the RAF values for these 7 radionuclides were 1.1, 1.5, 2.4, 3.2, 4.5, 5.1, and 6.5, respectively. CONCLUSION: These results suggest that low-energy electron emitters such as 117mSn and 33P are more likely to deliver a therapeutic dose to the bone while sparing the bone marrow than are energetic beta emitters such as 32p and 89Sr. Therefore, radiochemicals tagged with low-energy electron or beta emitters are the radiopharmaceuticals of choice for treatment of painful metastatic disease in bone.

Bone Marrow↗
PubMed2000

Marrow toxicity of 33P-versus 32P-orthophosphate: implications for therapy of bone pain and bone metastases.

UNLABELLED: Several bone-seeking radiopharmaceuticals, such as 32P-orthophosphate, 89Sr-chloride, 186Re-1,1 hydroxyethylidene diphosphonate (HEDP), and 153Sm-ethylene diamine tetramethylene phosphonic acid (EDTMP), have been used to treat bone pain. The major limiting factor with this modality is bone marrow toxicity, which arises from the penetrating nature of the high-energy beta particles emitted by the radionuclides. It has been hypothesized that marrow toxicity can be reduced while maintaining therapeutic efficacy by using radionuclides that emit short-range beta particles or conversion electrons. In view of the significant clinical experience with 32P-orthophosphate, and the similarity in pain relief afforded by 32P-orthophosphate and 89Sr-chloride, this hypothesis is examined in this study using 32P- and 33P-orthophosphate in a mouse femur model. METHODS: Survival of granulocyte macrophage colony-forming cells (GM-CFCs) in femoral marrow was used as a biologic dosimeter for bone marrow. 32P- and 33P-orthophosphate were administered intravenously, and GM-CFC survival was determined as a function of time after injection and, at the nadir, as a function of injected activity. The kinetics of radioactivity in the marrow, muscle, and femoral bone were also determined. The biologic dosimeter was calibrated by assessing GM-CFC survival at its nadir after chronic irradiation of Swiss Webster mice with exponentially decreasing dose rates of gamma rays (relative biologic effectiveness equivalent to that of beta particles) from a low-dose rate 137Cs irradiator. Dose-rate decrease half-times (Td) (time required for 137Cs gamma ray dose rate to decrease by one half) of 62, 255, and 425 h and infinity were used to simulate the dose rate patterns delivered by the radiopharmaceuticals as dictated by their effective clearance half-times from the mouse femurs. These data were used to experimentally determine the mean absorbed dose to the femoral marrow per unit injected activity. Finally, a theoretical dosimetry model of the mouse femur was developed, and the absorbed doses to the femoral marrow, bone, and endosteum were calculated using the EGS4 Monte Carlo code. RESULTS: When the animals were irradiated with exponentially decreasing dose rates of 137Cs gamma rays, initial dose rates required to achieve 37% survival were 1.9, 0.98, 0.88, and 0.79 cGy/h for dose rate decrease half-times of 62, 255, and 425 h and infinity, respectively. The D37 values were 144 +/- 15, 132 +/- 12, 129 +/- 3, and 133 +/- 10 cGy, respectively, compared with a value of 103 cGy for acute irradiation. When 32P and 33P were administered, the injected activities required to achieve 37% survival were 313 and 2,820 kBq, respectively. Theoretical dosimetry calculations show that 33P offers a 3- to 6-fold therapeutic advantage over 32P, depending on the source and target regions assumed. CONCLUSION: The low-energy beta-particle emitter 33P appears to offer a substantial dosimetric advantage over energetic beta-particle emitters (e.g., 32p, 89Sr, 186Re) for irradiating bone and minimizing marrow toxicity. This suggests that low-energy beta or conversion electron emitters may offer a substantial advantage for alleviation of bone pain as well as for specifically irradiating metastatic disease in bone.

Animals↗
PubMed2000

Marrow-sparing effects of 117mSn(4+)diethylenetriaminepentaacetic acid for radionuclide therapy of bone cancer.

UNLABELLED: Several bone-seeking radionuclides (32P, 89Sr, 186Re, and 153Sm) have been used to treat bone pain. The limiting factor in this modality is marrow toxicity. Our hypothesis is that marrow toxicity can be reduced while maintaining therapeutic efficacy using radionuclides that emit short-range beta particles or conversion electrons (CEs). A recent study on 47 patients using the short-range CE emitter 117mSn(4+)diethylenetriaminepentaacetic acid (117mSn(4+)DTPA) supports this hypothesis. The hypothesis is now tested using 117mSn(4+)DTPA in a mouse femur model. METHODS: The survival of granulocyte-macrophage colony-forming cells (GM-CFCs) in femoral marrow is used as a biologic dosimeter for bone marrow. The dosimeter is calibrated by irradiating mice with exponentially decreasing dose rates of 137Cs gamma-rays with a dose-rate decrease half-time, Td, equal to the effective clearance half-time of 117mSn(4+)DTPA from the femur (222 h). When Td = 222 h, the mean absorbed dose required to achieve a survival fraction of 37% is 151 cGy. After calibration, 117mSn(4+)DTPA is administered and GM-CFC survival is determined as a function of injected activity. These data are used to experimentally determine the mean absorbed dose to the femoral marrow per unit injected activity. The kinetics of radioactivity in the marrow, muscle, and femoral bone are also determined. Finally, a theoretic dosimetry model of the mouse femur is used, and the absorbed doses to the femoral marrow and bone are calculated. RESULTS: The experimental mean absorbed dose to the femoral marrow per unit injected activity of 117mSn(4+)DTPA is 0.043 cGy/kBq. The theoretic mean absorbed dose to the femoral bone per unit injected activity is 1.07 cGy/kBq. If these data are compared with those obtained previously for 32P-orthophosphate, the radiochemical 117mSn(4+)DTPA yields up to an 8-fold therapeutic advantage over the energetic beta emitter 32P. CONCLUSION: The CE emitter 117mSn offers a large dosimetric advantage over energetic beta-particle emitters for alleviating bone pain, and possibly for other therapeutic applications, while minimizing marrow toxicity.

Animals↗
PubMed1999

The impact of recirculating industrial air on aircraft painting operations.

The 1990 Clean Air Act Amendments resulted in new environmental regulations for hazardous air pollutants. Industries such as painting facilities may have to treat large volumes of air, which increases the cost of an air control system. Recirculating a portion of the air back into the facility is an option to reduce the amount of air to be treated. The authors of this study developed a computer model written in Microsoft Excel 97 to analyze the impact of recirculation on worker safety and compliance costs. The model has a chemical database with over 1300 chemicals. The model will predict indoor air concentrations using mass balance calculations and results are compared to occupational exposure limits. A case study is performed on a C-130 aircraft painting facility at Hill Air Force Base, Utah. The model predicts strontium chromate concentrations found in primer paints will reach 1000 times the exposure limit. Strontium chromate and other solid particulates are nearly unaffected by recirculation because the air is filtered during recirculation. The next highest chemical, hexamethylene diisocyanate, increases from 2.6 to 10.5 times the exposure limit at 0 percent and 75 percent recirculation, respectively. Due to the level of respiratory protection required for the strontium chromate, workers are well protected from the modest increases in concentrations caused by recirculating 75 percent of the air. The initial cost of an air control system is $4.5 million with no recirculation and $1.8 million at 75 percent recirculation. The model is an excellent tool to evaluate air control options with a focus on worker safety. In the case study, the model highlights strontium chromate primers as good candidates for substitution. The model shows that recirculating 75 percent of the air at the Hill painting facility has a negligible impact on safety and could save $2.7 million on the initial expenses of a thermal treatment system.

Air Pollutants, Occupational↗
PubMed1999

MIRD Pamphlet No. 15: Radionuclide S values in a revised dosimetric model of the adult head and brain. Medical Internal Radiation Dose.

UNLABELLED: Current dosimetric models of the brain and head lack the anatomic detail needed to provide the physical data necessary for suborgan brain dosimetry. During the last decade, several new radiopharmaceuticals have been introduced for brain imaging. The marked differences of these tracers in tissue specificity within the brain and their increasing use for diagnostic studies support the need for a more anthropomorphic model of the human brain and head for use in estimating regional absorbed dose within the brain and its adjacent structures. METHODS: A new brain model has been developed that includes eight subregions: the caudate nuclei, the cerebellum, the cerebral cortex, the lateral ventricles, the lentiform nuclei, the thalami, the third ventricle and the white matter. This brain model is incorporated within a total revision of the head model presented in MIRD Pamphlet No. 5 Revised. Modifications include the addition of the eyes, the teeth, the mandible, an upper facial region, a neck region and the cerebrospinal fluid within both the cranial and spinal regions. RESULTS: Absorbed fractions of energy for photon and electron sources located in 14 source regions within the new model were calculated using the EGS4 Monte Carlo radiation transport code for particles in the energy range 10 keV-4 MeV. These absorbed fractions were then used along with radionuclide decay data to generate S values for 24 radionuclides that are used in clinical or investigational studies of the brain, 12 radionuclides that localize within the cranium and spinal skeleton and 12 radionuclides that selectively localize in the thyroid gland. CONCLUSION: A substantial revision to the dosimetric model of the adult head and brain originally published in MIRD Pamphlet No. 5 Revised is presented. This revision supports suborgan brain dosimetry for a variety of radiopharmaceuticals used in neuroimaging. Dose calculations for the neuroimaging agent 1231-tropane provide an example of the new model and yield mean brain doses that are consistent with published values. However, the absorbed dose to subregions within the brain such as the caudate and lentiform nuclei may exceed the average brain dose by a factor of up to 5.

Adult↗
PubMed1999

Five pediatric head and brain mathematical models for use in internal dosimetry.

UNLABELLED: Mathematical models of the head and brain currently used in pediatric neuroimaging dosimetry lack the anatomic detail needed to provide the necessary physical data for suborgan brain dosimetry. To overcome this limitation, the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine recently adopted a detailed dosimetric model of the head and brain for the adult. METHODS: New head and brain models have been developed for a newborn, 1, 5, 10 and 15 y old for use in internal dosimetry. These models are based on the MIRD adult head and brain model and on published head and brain dimensions. They contain the same eight brain subregions and the same head regions as the adult model. These new models were coupled with the Monte Carlo transport code EGS4, and absorbed fractions of energy were calculated for 14 sources of monoenergetic photons and electrons in the energy range of 10 keV-4 MeV. These absorbed fractions were then used along with radionuclide decay data to generate S values for all ages for 99mTc, considering 12 source and 15 target regions. RESULTS: Explicit transport of positrons was also considered with separation of the annihilation photons component to the absorbed fraction of energy in the calculation of S values for positron-emitting radionuclides. No statistically significant differences were found when S values were calculated for positron-emitting radionuclides under explicit consideration of the annihilation event compared with the traditional assumption of a uniform distribution of 0.511-MeV photons. CONCLUSION: The need for electron transport within the suborgan brain regions of these pediatric phantoms was reflected by the relatively fast decrease of the self-absorbed fraction within many of the brain subregions, with increasing particle energy. This series of five dosimetric head and brain models will allow more precise dosimetry of radiopharmaceuticals in pediatric nuclear medicine brain procedures.

Adult↗
PubMed1999

A three-dimensional transport model for determining absorbed fractions of energy for electrons within trabecular bone.

UNLABELLED: Bone marrow is generally the dose-limiting organ of concern in radioimmunotherapy and in radionuclide palliation of bone pain. However, skeletal dosimetry is complicated by the intricate nature of its microstructure, which can vary greatly throughout skeletal regions. In this article, a new three-dimensional electron transport model for trabecular bone is introduced, based on Monte Carlo transport and on bone microstructure information for several trabecular bone sites. METHODS: Marrow cavity and trabecular chord length distributions originally published by Spiers et al. were randomly sampled to create alternating regions of bone, endosteum and marrow during the three-dimensional transport of single electrons. For the marrow spaces, explicit consideration of the site-specific elemental composition was made in the transport calculations based on the percentage of active and inactive marrow in each region. The electron transport was performed with the EGS4 electron transport code and the parameter reduced electron-step transport algorithm. Electron absorbed fractions of energy were tabulated for seven adult trabecular bone sites, considering three source and target regions: the trabecular marrow space (TMS), the trabecular bone endosteum (TBE) and the trabecular bone volume (TBV). RESULTS: For all source-target combinations, the absorbed fraction was seen to vary widely within the skeleton. These variations can be directly attributed to the differences in the trabecular microstructure of the different skeletal regions. For many source-target combinations, substantial energy dependence was seen in the calculated absorbed fraction, a factor not considered in values recommended by the International Commission on Radiological Protection (ICRP). A one-dimensional model of electron transport in trabecular bone, based on range-energy relationships, was also developed to verify the three-dimensional transport model and to evaluate differences between the two modeling approaches. Differences of approximately 10%-15% were seen, particularly at low electron energies. In the case of a TBV source and a TMS target (or vice versa), differences >50% were seen in the absorbed fraction. CONCLUSION: The three-dimensional model of electron transport in trabecular bone allows improved estimates of skeletal absorbed fractions. The model highlights both the regional and the energy dependency of the absorbed fraction not previously considered in the ICRP model.

Adult↗
PubMed1999

A three-dimensional transport model for determining absorbed fractions of energy for electrons within cortical bone.

UNLABELLED: Any radionuclide that is transported through the blood stream will also be carried through the haversian canals within cortical bone. These canals are lined with a layer of endosteum that contains radiosensitive cells. This paper introduces a new three-dimensional electron transport model for cortical bone based on Monte Carlo transport and on bone microstructural information for several cortical bone regions. METHODS: Previously published haversian cavity and bone matrix chord length distributions for cortical bone were randomly sampled to create alternating regions of bone matrix, endosteum and haversian canal tissues during the three-dimensional transport of single electrons. Electron transport was performed using the EGS4 transport code with the parameter reduced electron step transport algorithm. Electron-absorbed fractions of energy were tabulated for three adult cortical bone sites considering three source and target regions: the cortical haversian space, the cortical bone endosteum (CBE) and the cortical bone volume (CBV). RESULTS: Absorbed fractions assessed with the new model were shown to be highly energy dependent for most combinations of source-target regions in cortical bone. Although chord length data were available for three different bone sites (femur, humerus and tibia), very little variation with bone site was noted in the absorbed fraction data. CONCLUSION: International Commission on Radiation Protection (ICRP)-recommended absorbed fractions for cortical bone are given only for the CBE as target region and for the CBE and CBV as source regions. Comparisons of these recommended absorbed fractions with the absorbed fractions calculated in this study show large differences. For example, ratios of self-absorbed fractions to the CBE in this model and in the ICRP 30 model are approximately 0.25, approximately 4 and approximately 1.5 for initial electron energies of 10, 200 keV and 4 MeV, respectively. Consequently, this new transport model of electrons in cortical bone will improve the relatively energy-independent data recommended by the ICRP. This model will also allow consideration of the haversian canals as a potential radiation source.

Absorption↗
PubMed1999

The MIRD perspective 1999. Medical Internal Radiation Dose Committee.

The MIRD schema is a general approach for medical internal radiation dosimetry. Although the schema has traditionally been used for organ dosimetry, it is also applicable to dosimetry at the suborgan, voxel, multicellular and cellular levels. The MIRD pamphlets that follow in this issue and in coming issues, as well as the recent monograph on cellular dosimetry, demonstrate the flexibility of this approach. Furthermore, these pamphlets provide new tools for radionuclide dosimetry applications, including the dynamic bladder model, S values for small structures within the brain (i.e., suborgan dosimetry), voxel S values for constructing three-dimensional dose distributions and dose-volume histograms and techniques for acquiring quantitative distribution and pharmacokinetic data.

Humans↗