Dose Estimation on Surgeon for radionuclide Vertobroplasty  Yu.G. Zabaryansky1, A.A. Golovin2, Yu.A. Kurachenko

Purpose: To estimate the doses to a surgeon for a new operation – radionuclide vertebroplasty. To normalize the irradiation for the maximum number of operations in which the total equivalent dose will not exceed the values specified in the NRB-99/2009. Material and methods: The widespread Monte-Carlo code MCNP used with data libraries, as well as the ICRP-38 data on radionuclide characteristics. Results: Using the radionuclide 188Re, the most promising for this procedure, the equivalent dose in the doctor’s palms does not exceed 1 mSv per operation. A surgeon can perform up to 580 operations per year without violating radiation safety standards. Conclusion: Calculation methods proved the safety of radionuclide vertebroplasty for the surgeon and service personnel.

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Investigation of Nuclear Data Libraries with TRIPOLI-4 Monte Carlo Code for Sodium-cooled Fast Reactors

Nuclear Data Sheets ◽

10.1016/j.nds.2014.04.099 ◽

2014 ◽

Vol 118 ◽

pp. 433-436

Author(s):

Y.-K. Lee ◽

E. Brun

Keyword(s):

Monte Carlo ◽

Nuclear Data ◽

Monte Carlo Code ◽

Fast Reactors ◽

Data Libraries ◽

Nuclear Data Libraries

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Dual-energy contrast-enhanced digital mammography: Glandular dose estimation using a Monte Carlo code and voxel phantom

Physica Medica ◽

10.1016/j.ejmp.2015.03.013 ◽

2015 ◽

Vol 31 (7) ◽

pp. 785-791 ◽

Cited By ~ 7

Author(s):

E. Tzamicha ◽

E. Yakoumakis ◽

I.A. Tsalafoutas ◽

A. Dimitriadis ◽

E. Georgiou ◽

...

Keyword(s):

Monte Carlo ◽

Digital Mammography ◽

Dual Energy ◽

Monte Carlo Code ◽

Dose Estimation ◽

Voxel Phantom ◽

Contrast Enhanced

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Improvement and Benchmarking of the New Shutdown Dose Estimation Method by Monte Carlo Code

Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications ◽

10.1007/978-3-642-18211-2_138 ◽

2001 ◽

pp. 865-870 ◽

Cited By ~ 5

Author(s):

L. Petrizzi ◽

H. Iida ◽

D. Valenza ◽

P. Batistoni

Keyword(s):

Monte Carlo ◽

Estimation Method ◽

Monte Carlo Code ◽

Dose Estimation

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Digital breast tomosynthesis: Mean glandular dose estimation using monte carlo code

Physica Medica ◽

10.1016/j.ejmp.2016.07.224 ◽

2016 ◽

Vol 32 ◽

pp. 326

Author(s):

E. Tzamicha ◽

A. Dimitriadis ◽

H. Gonis ◽

E. Georgiou ◽

V. Tsapaki ◽

...

Keyword(s):

Monte Carlo ◽

Digital Breast Tomosynthesis ◽

Monte Carlo Code ◽

Dose Estimation ◽

Breast Tomosynthesis ◽

Mean Glandular Dose

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Proposal of shutdown dose estimation method by Monte Carlo code

Fusion Engineering and Design ◽

10.1016/s0920-3796(01)00188-0 ◽

2001 ◽

Vol 55 (4) ◽

pp. 411-418 ◽

Cited By ~ 42

Author(s):

Davide Valenza ◽

Hiromasa Iida ◽

Romano Plenteda ◽

Robert T. Santoro

Keyword(s):

Monte Carlo ◽

Estimation Method ◽

Monte Carlo Code ◽

Dose Estimation

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Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation ◽

10.1115/icone26-81694 ◽

2018 ◽

Author(s):

Junjie Rao ◽

Xiaotong Shang ◽

Kan Wang

Keyword(s):

Monte Carlo ◽

Neutron Flux ◽

Pressure Vessel ◽

Variance Reduction ◽

Fission Neutron ◽

Deep Penetration ◽

Monte Carlo Code ◽

Calculation Methods ◽

Neutron Distribution ◽

Window Method

RMC is a 3-D continuous energy Monte Carlo code developed by REAL team in Tsinghua University, China. Besides the capability of fuel cycle burnup calculation, hybrid MPI/OpenMP parallelism strategy, sensitivity and uncertainty analysis, N-TH coupling calculation, shielding calculation methods including general source description, regional importance method, weight window method and source biasing method have been also developed for deep penetration problems. H.B.Robinson-2 Pressure Vessel Benchmark (HBR-2 benchmark) is used for the qualification of pressure vessel neutron flux calculation methods and shielding calculations based on this model have been performed by Monte Carlo codes such as SCALE, MCNPX and deterministic transport code DORT. In this work, the verification calculation of shielding calculation capability of RMC is conducted based on HBR-2 benchmark. The total calculation consists of two stages. Criticality calculation is performed first to obtain the fission neutron distribution in the reactor core assemblies. Then the fission neutron distribution is regarded as the initial neutron source in the following fixed source calculation. Variance reduction techniques such as source biasing and regional importance methods are combined together to be able to reduce the variance of the neutron flux in regions within and outside the pressure vessel including the downcomer and cavity regions. The preliminary calculation results show good agreement with MCNP and the shielding calculation of RMC is justified and applicable for deep penetration problems.

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