Self-protection Analysis of Denatured Thorium-plutonium Fuel

نویسنده

  • Luis Alberto Torres
چکیده

With growing demands for commercial nuclear power, there is also a growing need for better energy efficiency from nuclear power reactors. In order to reach a high burnup up to 100 MWd/kg, previous research has examined the use of thorium-plutonium mixedoxide fuel as a potential candidate for this high-burnup goal. Though the neutronics studies have looked upon this fuel type favorably, the purpose of this paper is to investigate the self-protection capabilities of this fuel type, for anti-proliferation purposes. In particular, there were two proliferation-resistance methods that were analyzed. First, this study examined the time-dependant dose-rate of the spent fuel caused by the decay of the isotope uaranium-232, which releases a high-energy gamma of 2.6 MeV. Next, this study examined the possibility of denaturing the fuel with depleted uranium in order to dilute the weapons-usable isotope uranium-233 in the spent fuel. The U-232 dose rate was also calculated for the denatured case. Ultimately, the study found that there was a negligible different in the amount of time that it takes for either fuel type to become self-protective. The denatured case showed that it requires much more plutonium than the undenatured case in order to ensure that there is not sufficient weapons-usable U-233 in the discharged fuel. Thesis Supervisor: Edward E. Pilat Title: Research Scientist, Nuclear Science and Engineering Acknowledgements I would like to thank Eugene Shwageraus for his guidance and patience on this project. I would like to thank Edward E. Pilat for your support and dedication to my completion of this project. I would like to thank Mujid Kazimi for giving me the opportunity to contribute to research for the Center of Advanced Nuclear Energy Systems. Table of

برای دانلود 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

An analysis of misconceptions about thorium-based fuel cycles as a technical fix to the nuclear proliferation problem

This paper analyzes several prevalent misconceptions about nuclear fuel cycles that breed fissile uranium-233 from thorium. Its main conclusions are: a Uranium-233, despite the gamma radioactivity of associated isotopes, is a rather attractive material for making fission bombs, and is a credible material for subnational as well as national groups to use for this purpose. e "Pure" thorium cycles...

متن کامل

محاسبات مصرف سوخت و پارامترهای نوترونیک مربوط به رآکتورهای آب سنگین تحقیقاتی با سوخت اورانیوم- توریوم توسط کد MCNPX

One of the main characteristics of heavy water research reactors is their high production of plutonium. This work demonstrates the possibility of reduction of plutonium production and other actinides in heavy water research reactors. Among the many ways for reducing plutonium production in a heavy water reactor, in this research, changing the fuel from natural uranium to thorium-uranium mixed f...

متن کامل

Study of thorium advanced fuel cycle utilization in light water reactor VVER-440

The first step in investigation of thorium fuel is evaluation of the results obtained from the spectral code for this type of fuel. The benchmark summarized by IAEA in 2003 was used for partial validation of the code HELIOS 1.9. The benchmark was focused on a comparison of the methods and basic nuclear data. Acceptable results of benchmark comparison allowed examining and comparing different ad...

متن کامل

Improved PWR Core Characteristics with Thorium-containing Fuel

Thorium is an element for possible use as nuclear fuel, because of the fertile property of Th-232, which could convert into U-233 after neutron capture and beta decays. However, thorium based fuels have not been successfully implemented, because of the high cost and the higher complexity compared with once-through uranium fuel. Therefore, the focus of this thesis is on thorium for use in tradit...

متن کامل

Resistance of U-233 in Spent Fuel

The factors influencing the level of U-232 contamination in U-233 are examined for heavy-water-moderated, light-water-moderated and liquid-metal cooled fast breeder reactors fueled with natural or low-enriched uranium and containing thorium mixed with the uranium or in separate target channels. U-232 decays with a 69-year half-life through 1.9-year half-life Th-228 to Tl-208, which emits a 2.6 ...

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

برای دانلود 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

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2011