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Showing 1 to 20 of 93 for “"MCNP"”.
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Electron photon calculations using MCNP
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.
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MCNP Study of IPNS C Moderator Groove Configuration
Made available in DSpace on 2017-07-06T18:48:57Z (GMT). No. of bitstreams: 3 Keller_Steven_E_MS.pdf: 45536581 bytes, checksum: 66704840c669bb8886ccaa508f6b55c1 (MD5) Keller_Steven_E_MS_ABS.pdf: 536907 bytes, checksum: 5b8888a9a86c06349b79e6a352ffbc14 (MD5) license.txt: 4813 bytes, checksum: …
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Gamma spectroscopy by artificial neural network coupled with MCNP
… study comes from data library availability on MCNP. A perceptron network was employed to identify five elements from gamma spectra. In quantitative analysis, better results were obtained when the neural fitting tool in MATLAB was used. As a training function, Levenberg-Marquardt algorithm was …
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Multi-Purpose Research Reactor Designs Using MCNP and Origen
Made available in DSpace on 2017-07-06T18:48:39Z (GMT). No. of bitstreams: 3 Hu_Jianwei_MS.pdf: 12941059 bytes, checksum: bab58c978d20c697c63132361864a936 (MD5) Hu_Jianwei_MS_ABS.pdf: 35914 bytes, checksum: e11195f3129796aebd383242e916a02c (MD5) license.txt: 4813 bytes, checksum: …
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MCODE-3 : time-dependent depletion isotopics with MCNP-5 and SCALE-6.1
… the Monte Carlo N-Particle transport code, MCNP, with the Oak Ridge Isotope Generation point depletion code, ORIGEN-S. MCNP provides reaction rates and neutron flux in user-specified irradiation material regions. COUPLE, a data-editing code included in the SCALE- 6.1 software package, uses …
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Investigation of improved methods for assessing convergence of models in MCNP using Shannon entropy
… simulating the OECD/NEA benchmark #1 problem in MCNP. It was found that Shannon entropy does accurately predict the number of batches required for a source distribution to converge, though only when when the Shannon entropy mesh was the size of the tally mesh. The investigation of undersampling …
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Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP
… of subcritical assembly measurements and MCNP simulations. Next, a multitude of fission products were identified as candidates for burnup and spent fuel analysis of irradiated mixed oxide fuel. The best isotopes for these applications were identified by investigating half-life, photon …
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Speedup of MCNP(X) parallel KCODE execution via communication algorithm development and Beowulf Cluster optimization
This thesis examines two methods for speeding up MCNP KCODE calculations. The first approach is assembly of a low cost Beowulf Cluster for parallel computation. The first half describes the MIT Nuclear Engineering Department's Beowulf Cluster, Echelon, as a prototype. Echelon is a low cost, 30 …
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Monte Carlo dosimetry and activation calculation for a proposed fusion device : MCNP analysis of aAlcator C-MOD
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1985.
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Beam characterization at the neutron radiography reactor
… results produced by a Monte Carlo n-Particle (MCNP) model of the beamline. Improvement of the existing NRAD MCNP beamline model includes validation of the model's energy spectrum and the development of enhanced image simulation methods. The image simulation methods predict the radiographic …
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Epithermal neutron activation analysis of short-lived radionuclides using a pneumatic transport system and a pulsed D-T neutron generator
… half-lives. The Monte Carlo N-Particle (MCNP) radiation transport code was used to model the graphite pile, the pneumatic transport tube, and the neutron generator. This resulted in benchmarking and validation of the experimental results. In order to reach an agreement between the …
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Development of MURR flux trap model for simulation and prediction of sample loading reactivity worth and isotope production
… and predicts the requested isotope production. MCNP part of the MFTM model carries out neutron transport calculations and predicts the reactivity worth of sample loading in the flux trap while MonteBurns part of the model calculates isotope production from the target sample irradiated in the …
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Characterization of the Neutron Irradiation System for use in the Low-Dose-Rate Irradiation Facility at Sandia National Laboratories
… using Monte Carlo N-Particle transport code (MCNP). The model was validated by benchmarking it against measurements using multiple techniques. To characterize the radiation fields over the full spatial geometry of the irradiation system, it was necessary to use a number of instruments of …
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Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle
… of Monte Carlo N-Particle Transport Code (MCNP) to MSR modeling was verified. Then, a prescription for conceptual small thermal reactor LFTR and relevant calculations were performed using MCNP to determine the main neutronic parameters of the core reactor. The MCNP code was used to study …
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Gamma and neutron dose profiles near a Cf-252 brachytherapy source
… a Cf-252 brachytherapy source. Specifically, the MCNP-predicted gamma dose rate is a factor of two higher than the measured gamma dose rate at the distance of 1 cm, and the differences between the two results gradually diminish at distances farther away from the source. To resolve this …
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Development of a switchable radioisotope generator
… The completed cross sections were arranged in MCNP 6.1.1, such that alpha interactions may be simulated. Angular-energy dependence of secondary neutrons from <sup>9</sup>Be(α, n)<sup>12</sup>C were chosen for simulation study, as this reaction would be validated later on experimentally due to …
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Dosimetry of ¹²⁵Iodine protons for in vivo mouse irradiation study
… a series of simulations were performed using MCNP to calculate the expected dose equivalent reported by those dosimeters. Comparison of the dosimeters' recorded dose to MCNP's calculated dose showed agreement within experimental and statistical uncertainty for 82% of the measurements. This …
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Neutron dosimetry, moderated energy spectrum, and neutron capture therapy for ²⁵{45}R²Cf medical sources
… and experimental means. Monte Carlo N-ParticIe (MCNP) transport code was used in a distributed computing environment as a parallel virtual machine (PVM) to determine the absorbed neutron dose and neutron energy spectrum from 252Cf in a variety of clinically relevant materials. Herein, a …
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Synthesis and evaluation of radioactive gold nanoparticles for cancer treatment and imaging
… can be used for imaging. Also in this research, MCNP code was used to build a simple geometrical model of a human prostate, and then estimate the dose distribution that is deposited by radioactive gold nanoparticles (198AuNPs or 199AuNPs). The results from in vivo evalution of MGF-198AuNPs …
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