Shielding calculations for industrial 5/7.5MeV electron accelerators using the MCNP Monte Carlo Code
نویسندگان
چکیده
منابع مشابه
A Monte Carlo Burnup Code Linking Mcnp and Rebus*
The REBUS-3 burnup code, used in the ANL RERTR Program, is a very general code that uses diffusion theory (DIF3D) to obtain the fluxes required for reactor burnup analyses. Diffusion theory works well for most reactors. However, to include the effects of exact geometry and strong absorbers that are difficult to model using diffusion theory, a Monte Carlo method is required. MCNP, “a general-pur...
متن کاملMonte Carlo Calculations Using MCNP4B for an Optimal Shielding Design of a 14-MeV Neutron Source
The shielding for 14-MeV neutrons from a D-T generator at SLAC needs to be optimized in terms of shield thickness and cost. Shielding calculations were made using the MCNP4B Monte Carlo code and the ENDF/B-VI cross section set. A few materials were studied: iron, borated polyethylene, three types of normal and heavy concrete, and mixtures of iron and borated polyethylene. The effects of shieldi...
متن کاملAutomated Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint Function
Although the Monte Carlo method is considered to be the most accurate method available for solving radiation transport problems, its applicability is limited by its computational expense. Thus, biasing techniques, which require intuition, guesswork, and iterations involving manual adjustments, are employed to make reactor shielding calculations feasible. To overcome this difficulty, we have dev...
متن کاملEvaluate Shielding Design of the Brachytherapy Unit by Using Monte Carlo Simulation Code
Shielding design is necessary for brachytherapy treatment room in order to protect the general public and employees. The main objective of this study was to investigate whether the protective unit of our Brachytherapy Centre provided adequate protection to the health and safety assessment of radiobiological impact. In this study, we estimated the effect of radiobiological protection from a sing...
متن کاملApplication of IRDF2002 dosimetry data to shielding benchmarks using the Monte Carlo code MCBEND
The IRDF2002 dosimetry cross-section data are processed into very fine energy groups and added to the detector response library for the Monte Carlo code MCBEND. The IRDF2002 covariances are processed into broad groups to form a MCBEND detector covariance library. A number of benchmark experiments are analysed using MCBEND with both IRDF2002 and IRDF90 data and the results compared. Uncertaintie...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
ژورنال
عنوان ژورنال: EPJ Web of Conferences
سال: 2017
ISSN: 2100-014X
DOI: 10.1051/epjconf/201715303011