Intercomparison of personnel dosimetry for thermal neutron dose equivalent in neutron and gamma ray mixed fields.
نویسندگان
چکیده
منابع مشابه
Dosimetry in Mixed Neutron-Gamma Fields
The gamma field accompanying neutrons may, in certain circumstances, play an important role in the analysis of neutron dosimetry and even in the interpretation of radiation induced steel embrittlement. At the figh Flux Isotope Reactor pressure vessel the gamma-induced reactions dominate the responses of ' W p and 238u dosimeters, and9Be helium accumulation fluence monitors. The gamma induced at...
متن کاملDesign and manufacture of composite flexible shield for neutron-gamma mixed fields
In this study, a flexible composite shield with a combination of polyethylene, tungsten and boron carbide has been designed and constructed for neutron-gamma mixed fields. For this purpose, theoretical studies were conducted using the multi-purpose MCNPX Code. According to the results of simulation studies, a multi-purpose composite was constructed using a combination of a solid phase of boron ...
متن کاملInvestigation of neutron flux by thermoluminescence dosimeters in the neutron-gamma mixed field
Introduction: Neutrons have many applications in various fields, such as medicine. The important application of neutron in medical science is in Boron Neutron Capture Therapy (BNCT). Because of this, determination of neutron dose and flux is critical for the health maintaining of workers and patients exposed to this beam. The neutron radioisotope sources produce gamma rays in ...
متن کاملNeutron Capture Gamma Rays ( Thermal Neutron
Detection of landmines using nuclear techniques has been studied extensively since the late 1940s. Nuclear techniques look at either a return radiation, which is characteristic of explosive components that are infrequently found in soil (e.g., nitrogen or carbon), or an intensity change of a noncharacteristic scattered radiation, which is a function of a parameter that differs between soil and ...
متن کاملEstimation of neutron and gamma dose in the MNSR research reactor
In this study, the neutron and gamma doses in the dry channel and in the internal irradiation site of the Miniature Neutron Source research reactor (MNSR) has been calculated and measured. The MNSR reactor is a light water reactor with a maximum power of 30 kW and equipped with various irradiation facilities, including five irradiated sites, five irradiation sites and a dry channel. The interna...
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: Japanese Journal of Health Physics
سال: 1984
ISSN: 0367-6110,1884-7560
DOI: 10.5453/jhps.19.209