نتایج جستجو برای: mcnp code
تعداد نتایج: 168334 فیلتر نتایج به سال:
Gamma radiation shielding features for three series of binary alloys identified as (Pb–Sn), (Pb–Zn), and (Zn–Sn) have been investigated. The mass attenuation coefficients (?/?) the selected were simulated using MCNP-5 code in energy range between 0.01 15 MeV. Moreover, values computed WinXCOM database same to validate simulation results. Results reveal a good agreement values. half value layer ...
Introduction: With the extensive application of radiation sources and radioactive materials in various fields, the study of attenuation and absorption of X-rays and gamma-rays in several materials has become an essential and interesting field of research. Glass materials are possible alternatives of concretes for radiation-shielding materials. Materials and Methods:...
Since 2005 the nodal diffusion based code system, OSCAR-3, was used for reactor support calculations of operational cycles High Flux Reactor in Petten, The Netherlands. OSCAR uses a two-step deterministic calculation, which homogenized cross sections are generated lattice environments using neutron transport simulations, and then passed to core simulator model full reactor. Limitations OSCAR-3 ...
The 250kW TRIGA Mark II research reactor, Vienna, is equipped with experimental facilities inside and outside the reactor core. Outside the core, there are four beam tubes (three radial and one tangential beam tube), a thermal column and a neutron radiography collimator, supplying neutrons for irradiation experiments. These experiments include neutron radiography, neutron tomography, neutron ac...
Most HWRs currently use natural uranium fuel. Using enriched uranium fuel results in a significant improvement in fuel cycle costs and uranium utilization. On the other hand, reactivity changes of HWRs over the full range of operating conditions from cold shutdown to full power are small. This reduces the required reactivity worth of control devices and minimizes local flux distribution perturb...
Boron-neutron capture therapy (BNCT) is an experimental radiation treatment modality used for highly malignant tumor treatments. Prior to irradiation with low energetic neutrons, a B compound is located selectively in the tumor cells. The effect of the treatment is based on the high LET radiation released in the B(n,α)Li reaction with thermal neutrons. BNCT has been used experimentally for brai...
background: in treating patients with radiation, the degree of accuracy for the delivery of tumor dose is recommended to be within ± 5% by icru in report 24. the experimental studies have shown that the presence of low-density inhomogeneity in areas such as the lung can lead to a greater than 30% change in the water dose data. therefore, inhomogeneity corrections should be used in treatment pla...
The present study deals with a new method for measuring the power of a reactor. This method uses gamma and neutron radiation resulted from the entire reactor structure, without changing its structure (online). In terms of functionality, this method can measure the reactor power in real-time and report it instantly. In order to obtain the relationship between reactor power and gamma and neutron ...
نمودار تعداد نتایج جستجو در هر سال
با کلیک روی نمودار نتایج را به سال انتشار فیلتر کنید