mcnp code

Bismuth efficiency in shielding superficial tissues in computed tomography (CT) scans has been challenged due to the imbalance between image quality and dose reduction. The aim of this study is to reduce bismuth in shields and investigate the possibility of substitution with lower atomic materials.
Five different compounds, including raw polyvinyl alcohol (PVA) and four other samples containing variable weight fractions of bismuth oxide and with a constant fraction of magnetite were selected. Shielding factors, including linear attenuation coefficient(μ), mass attenuation coefficient(μρ), half-value layer (HVL), electron density (Ne), and effective atomic number (Zeff), were evaluated over a wide range of energy by precise computational methods, XCOM, and Monte Carlo N-Particle code.
Increasing the bismuth oxide concentration improves the radiation attenuation and absorption process. This effect was observed in the μρ graphs to medium energies (E < 0.3560 MeV).The simultaneous evaluation of Ne and Zeff predicts increased absorption due to the increased and dominant photoelectric effect (<0.1000 MeV), the raised Compton effect (0.1000 < E < 0.3560 MeV; followed by scattering owing to the predominant Compton effect), and formation (E ≈ 1.2200 MeV)and dominance of pair production phenomenon (E > 3.0000 MeV).Also, a quantitative analysis of absorption through HVL in several used energies showed the efficacy of these compounds in ionizing radiation absorption.
This study establishes the advantages of substituting bismuth with compounds having lower atomic number materials, and the possibility of alleviating bismuth and replacing it with magnetite and PVA in designing radiation shields in CT scans has been confirmed.

99mTc-Macro Aggregated-Albumin (99mTc-MAA) has been evaluated as a useful perfusion study agent. In this study, the human absorbed dose of 99mTc-MAA was estimated with MIRD and MCNP methods based on animal biodistribution data and finally compared with ICRP publication data.

In this study, for investigating the biodistribution of 99mTc-MAA, after radiolabeling of MAA with Technetium-99m, it was injected to mice via the tail vein. After 1-120 min post injection, the mice were sacrificed and some of their tissues dissected and counted for calculating the percentage of the injected dose per gram (% ID/g) and the absorbed dose. Then, the obtained data was converted to equivalent data in human for each tissue.

Dose prediction shows that the highest absorbed dose is observed in the lungs (MIRD: 6.8E-2 mGy/MBq, MCNP: 6.32E-2 mGy/MBq). There is good agreement between the results obtained from MIRD and MCNP simulation for lungs.

According to the present results and comparison with ICRP publication data, animal dissection model and simulation MCNP code can be useful tools for internally-absorbed dose estimation of pulmonary radiopharmaceuticals.

In recent years, there has been an increased interest toward non-lead radiation shields consisting of small-sized filler particles doped into polymer matrices. In this paper, we study a new polyvinyl alcohol (PVA)/WO3 composite in the presence of high-energy gamma photons through simulation via the Monte Carlo N-Particle (MCNP) simulation code.

An MCNP geometry was first designed in the software based on real-life conditions, and the generated geometry was validated by calculating the mass attenuation coefficient and making relative comparisons with standard tables. Using the lattice card in the MCNP input file, WO3 was considered as a filler dispersed in a PVA polymer at sizes of 10 µm and 30 nm with a weight concentration of 50 wt%. By defining 106-photons emitted from point sources corresponding to 662, 778, 964, 1112, 1170, 1130 and 1407 keV energy levels, and the F4 tally used to estimate the cell average flux, the values for mass attenuation coefficient and half-value layer (HVL) were calculated.

The results show that PVA/WO3 composite can be considered to shield X and γ-rays in the mentioned energies. However, nano-WO3 has a better ability to shield in comparison with the micro-WO3 fillers. The differences in attenuation changed at different energy levels, ascribed to the dominance of pair production occurrence and photon interactions in the composite, which was in good agreement with previous studies.

Our finding showed that the composite can be considered as a lead-free shielding material.

Introduction: Silicone gel breast implants are used for breast reconstruction post mastectomy. In the event of cancer recurrence, the radiation oncologists are forced to irradiate through the prosthesis device. Due to prosthesis higher atomic number dose perturbations occur during treatment. This study determined the influence of silicone gel thickness on the photon beam distribution. A Varian linear accelerator, water phantom (dimensions 30 × 30 × 30 cm3), silicone gel breast prosthesis and Omni-Pro Accept software were used in the study. With the gantry positioned at at a source-to-surface distance (SSD) of 100 cm, the collimators were adjusted to a field size of 10 × 10 cm2 and the 6 MeV photon beam was used. Omni-Pro Accept software was used to plot the percentage depth dose curves and the beam profiles. The results obtained with a Monte Carlo Nuclear Particle (MCNP) Code were validated with the measurement data. The beam profile and percentage depth dose curves were also measured for silicone gel thicknesses (4, 6, 8, 10, 12, 14 and 16 cm) and width 16.5 cm aligned 1 cm below the surface of the water. The measured and calculated percentage depth dose (PDD) ratio was 0.03. The measured and calculated beam profiles were 0.5% and 0.9% respectively. For the silicone gel prosthesis, the depth dose values at 0.5 cm below the prosthesis were 2.8%. Dose perturbations below the breast prosthesis are insignificant, breast prosthesis are safe in the event of carcinoma recurrences.

X-ray mammography is one of the general methods for early detection of breast cancer. Since glandular tissue in the breast is sensitive to radiation and it increases the risk of cancer, the given dose to the patient is very important in mammography..
The aim of this study was to determine the average absorbed dose of X-ray radiation in the glandular tissue of the breast during mammography examinations as well as investigating factors that influence the mean glandular dose (MGD). One of the precise methods for determination of MGD absorbed by the breast is Monte Carlo simulation method which is widely used to assess the dose..
We studied some different X-ray sources and exposure factors that affect the MGD. “Midi-future” digital mammography system with amorphous-selenium detector was simulated using the Monte Carlo N-particle extended (MCNPX) code. Different anode/filter combinations such as tungsten/silver (W/Ag), tungsten/rhodium (W/Rh), and rhodium/aluminium (Rh/Al) were simulated in this study. The voltage of X-ray tube ranged from 24 kV to 32 kV with 2 kV intervals and the breast phantom thickness ranged from 3 to 8 cm, and glandular fraction g varied from 10% to 100%..
MGD was measured for different anode/filter combinations and the effects of changing tube voltage, phantom thickness, combination and glandular breast tissue on MGD were studied. As glandular g and X-ray tube voltage increased, the breast dose increased too, and the increase of breast phantom thickness led to the decrease of MGD. The obtained results for MGD were consistent with the result of Boone et al. that was previously reported..
By comparing the results, we saw that W/Rh anode/filter combination is the best choice in breast mammography imaging because of the lowest delivered dose in comparison with W/Ag and Rh/Al. Moreover, breast thickness and g value have significant effects on MGD..

One of the best methods in the diagnosis and control of breast cancer is mammography. The importance of mammography is directly related to its value in the detection of breast cancer in the early stages, which leads to a more effective treatment. The purpose of this article was to calculate the X-ray spectrum in a mammography system with Monte Carlo codes, including MCNPX and MCNP5.
The device, simulated using the MCNP code, was Planmed Nuance digital mammography device (Planmed Oy, Finland), equipped with an amorphous selenium detector. Different anode/filter materials, such as molybdenum-rhodium (Mo-Rh), molybdenum-molybdenum (Mo-Mo), tungsten-tin (W-Sn), tungsten-silver (W-Ag), tungsten-palladium (W-Pd), tungsten-aluminum (W-Al), tungsten-molybdenum (W-Mo), molybdenum-aluminum (Mo-Al), tungsten-rhodium (W-Rh), rhodium-aluminum (Rh-Al), and rhodium-rhodium (Rh-Rh), were simulated in this study. The voltage range of the X-ray tube was between 24 and 34 kV with a 2 kV interval.
The charts of changing photon flux versus energy were plotted for different types of anode-filter combinations. The comparison with the findings reported by others indicated acceptable consistency. Also, the X-ray spectra, obtained from MCNP5 and MCNPX codes for W-Ag and W-Rh combinations, were compared. We compared the present results with the reported data of MCNP4C and IPEM report No. 78 for Mo-Mo, Mo-Rh, and W-Al combinations.
The MCNPX calculation outcomes showed acceptable results in a low-energy X-ray beam range (10-35 keV). The obtained simulated spectra for different anode/filter combinations were in good conformity with the finding of previous research.

Chlorotoxin is a 36 amino acids peptide, which is able to block chloride channels isolated from mouse brain. A derivative of chlorotoxin is synthesized and it is labeled by iodine 131; then animal experiments carry out on rats. Multiple organ doses may be calculated with biological distribution results in rats with labeled compounds using simulated MCNP4C code. Human dose can be calculated using the dose distribution in rats with a conversion ratio for dose distribution. Chloramine T is our method for marking, and electrophilic substitution reactions are methods for iodize of peptides. Simulation of a human phantom to evaluate dose distribution was done using simulation code MCNP4C. To evaluate the dose distribution in the human body, using this code and the accumulated activity in each organ tissue dose is calculated. To study the biological distribution of the radiotracer 131I, 0.37 MBq radiotracer was injected into rat via the tail vein. The accumulated activity in each organ with the agent “ID / g” is determined. Biological distribution of 131I-chlorotoxine in the normal rats is obtained. Its Decay constant in the liver is 0.07h and the effective half-life of the radiotracer is 10h in rat liver. The total number of particles found in the leak from liver tissue was reported 67600. Liver tissue dosimetries originating from other sources (thyroid tissue, stomach, kidney, right & left lung, spleen, and pancreas) were examined. Then, the overall dose to the target tissue will be calculated. Leaked beta particles in liver itself (self-dose) are the most delivered dose to the liver (98%); it is for gamma rays 1.1%, while its source is adjacent tissues in addition to liver (cross-dose); Because of low atomic number of the tissue, delivered dose originated from Bremsstrahlung (braking radiation) is low (0.9%). Radiation dose to the liver in intravenous injection of 0.37 MBq 131I-chlorotoxine radiotracer is 3.44 * 10-6.