Influence of Γ Radiation of Short-living Fission Products on Kinetics of the Beryllium Reflected Core of Budapest Research Reactor

نویسندگان

  • A. Keresztúri
  • G. Hordósy
  • P. Vértes
چکیده

Two methods were elaborated for calculation of the kinetic effects caused by the photo-neutrons emitted in beryllium reflector of the VVRSZM type research reactor of KFKI-AEKI. The first simplified point kinetic model assumes that the importance of photo-neutrons is the same as that for the neutrons originated from the fission events. The point kinetic parameters were calculated by using the modified MCNP4A and TIBSO codes. A more realistic and complicated model was built in the KIKO3D code by introduction of additional delayed neutron groups and artificial fission in the reflector nodes. The additional response matrices responsible for the artificial fission were obtained from static coupled neutron-gamma MCNP4A calculations. The kinetic calculations show that the influence of the photo-neutrons is not negligible in the doubling time reactivity measurements. The reactivity-meter can give false values if the photo-neutron effect is not taken into account.

برای دانلود رایگان متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Computing Atomic Density Changes of Material Composition in Operation of the Nuclear Reactor Core

The present work investigates an appropriate way to calculate the 1700 atomic density changes in the reactor operations. To automate this procedure, a computer program has been designed by C#. This program suggests a way to solve this problem which is based on the solution system of differential equations (Bitman) that it is designed according to Runge-Kutta Fehlberg method. The designed softwa...

متن کامل

Optimization of the rate of production 99Mo-99mTC through fission in the TRR

Technetium is one of the most important radioisotopes recognized in medicine which is obtained through ‎the decay of molybdenum 99.The half-life of this radioisotope is 6 hours and it is capable of 140 kev gamma ray emission. Due to its short half-life, this radioisotope must be produced at the site of consumption, so that the shortest possible time interval between production and consumption c...

متن کامل

بررسی تغییرات راکتیویته راکتور MNSR اصفهان در اثر تغییر ضخامت لایه برلیوم سقف قلب راکتور با استفاده از کدهای محاسباتی WIMSD و MCNP و مقایسه با نتایج تجربی

In this work, the Isfahan Miniature Neutron Source Reactor (MNSR) is first simulated using the WIMSD code, and its fuel burn-up after 7 years of operation ( when the reactor was revived by adding a 1.5 mm thick beryllium shim plate to the top of its core) and also after 14 years of operation (total operation time of the reactor) is calculated. The reactor is then simulated using the MCNP code,...

متن کامل

Investigating the trajectory and amount of radioactive materials effluence in the atmosphere due to operation of Fars proposed research reactor

In this study, the trajectory and the concentration of radioactive nuclei in the atmosphere resulting from the Fars proposed research reactor innormal operation condition have been investigated. Since the reactor is in the conceptual design stage, so we use the characteristics of the Tehran research reactor, which is very similar to this reactor. Simulations were carried out for a one-year peri...

متن کامل

Nuclear fuel in a reactor accident.

Nuclear accidents that lead to melting of a reactor core create heterogeneous materials containing hundreds of radionuclides, many with short half-lives. The long-lived fission products and transuranium elements within damaged fuel remain a concern for millennia. Currently, accurate fundamental models for the prediction of release rates of radionuclides from fuel, especially in contact with wat...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2005