MCNP6 calculation of neutron flux map in the httr during normal operation
نویسندگان
چکیده
Detailed neutron flux distribution is important to understand the neutronic behavior during operation as well precise core optimization and safety analysis of a reactor. In literature, no calculations have been performed show detailed map for high temperature engineering test reactor (HTTR) because limitation old codes low performance computing system. HTTR prismatic type reactor, helium gas-cooled, graphite-moderated, providing 30 MWth power up 950 oC outlet temperature. The present work deals with MCNP6 Monte-Carlo calculation determine in normal operation. At first, at several positions was validated by comparing corresponding reaction rate between measurement. After that small cells 1cm×1cm×10cm obtained entire using fmesh tally code.
منابع مشابه
the effect of e-64 on the developmental competence of sheep cocs during in vitro maturation
in the present study, the effect of e-64 at different concentrations (0.5, 1, 5 and 10 µm) added to (1) the ivm medium on oocyte nuclear maturation and developmental competence of ovine oocytes, and (2) to the ivc medium on embryonic development of ovine embryos were investigated.
Investigation 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 کاملA Preliminary Comparison of MCNP6 Delayed Neutron Emission from
A Description of the Experiment The DNC system at RMCC uses the SLOWPOKE-2 reactor [2] as a source of neutrons. Samples containing 235 U were prepared as acidified aqueous solutions from certified reference standards (natural U standard CRM 4321C, NIST, Gaithersburg, MD, and depleted U standard CRM U005A 0.5064 ± 0.0003 atom% U, New Brunswick Laboratory, Argonne, IL). Each solution was containe...
متن کاملCalculation and evaluation of the vital head organs dose during Neutron Therapy in Tehran Research Reactor using Zubal phantom
In the recent years some studies has been done to consider the capability of Tehran Research Reactor for Boron neutron capture therapy (BNCT). The purpose of this study is to evaluate the sensitive organs dose during the treatment of patient with deep brain tumor by TRR. The calculation has been carried out using the Monte Carlo code MCNPX for ZUBAL head and neck phantom. The method was tested ...
متن کاملNeutron Fluence Estimates Inside the APS Storage Ring During Normal Operation
Introduction In an electron storage ring, neutrons are generated as a result of the electron beam interaction with high-Z materials, such as scrapers and collimators [1]. When the energy of the incident electron beam is sufficiently high, it can produce high-energy photons, which subsequently interact with a nucleus, resulting in the emission of nucleons. This interaction is known as a photonuc...
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: Habaršysy - A?l-Farabi atynda?y K?azak? memlekettik u?lttyk? universitetì. Fizika seriâsy
سال: 2022
ISSN: ['1563-0315', '2663-2276']
DOI: https://doi.org/10.26577/rcph.2022.v82.i3.03