IAEA-CN-220-279 Alternatives to Truncated Multiplicity Analysis to Improve Verification of Uranium Fuel Cycle Materials

نویسندگان

  • Adrienne M. LaFleur
  • Stephen Croft
  • Karen A. Miller
  • Martyn T. Swinhoe
  • Anthony P. Belian
چکیده

More accurate verification of U enrichment and mass in UF6 storage cylinders and of UO2F2 holdup contained in process equipment is needed to improve international safeguards and nuclear material accountancy at uranium enrichment plants. Small UF6 cylinders (1.5” and 5” diameter) are used to store the full range of enrichments from depleted to highly-enriched UF6. For independent verification of these materials, it is essential that the U mass and enrichment measurements do not rely on facility operator declarations. Furthermore, in order to be deployed by IAEA inspectors to detect undeclared activities (e.g. during complementary access), it is also imperative that the measurement technique is quick, portable, and sensitive to a broad range of U masses. Truncated multiplicity analysis is a technique that reduces both the value and the variance of the measured neutron count rates by only considering values 0, 1, and 2 of the multiplicity distribution. This is especially important for reducing the uncertainty in the measured doubles and triples rates in environments with a high cosmic ray background relative to the uranium signal strength. However, we believe that truncated multiplicity analysis may throw away too much useful data by truncating the distribution at 2. This paper investigates two alternative methods to truncated multiplicity analysis: 1) uses a 1σ outlier rejection limit to truncate the multiplicity distribution based on the measured data and 2) uses a second identical detector next to the detector measuring the item to directly track the cosmic ray variation. Experimental measurements of small UF6 cylinders and UO2F2 working reference materials were performed at Los Alamos National Laboratory (LANL). The data were analyzed using the alternative methods and traditional truncated multiplicity analysis to compare the impact of the methods on the measured count rates and uncertainties. The results from this analysis directly support nuclear safeguards at enrichment plants and provide a more accurate verification method for UF6 cylinders and uranium holdup in high

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

Minimization of waste from uranium purification, enrichment and fuel fabrication

FOREWORD As any industry, nuclear industry generates a diverse range of waste which has to be managed in a safe manner to be acceptable to the public and the environment. The cost of waste management, the risks to the public and employees, and the detriment to the environment are dependent on the quantity and radioactive content of the waste generated. Waste minimization is a necessary activity...

متن کامل

Sustainability Features of Nuclear Fuel Cycle Options

The nuclear fuel cycle is the series of stages that nuclear fuel materials go through in a cradle to grave framework. The Once Through Cycle (OTC) is the current fuel cycle implemented in the United States; in which an appropriate form of the fuel is irradiated through a nuclear reactor only once before it is disposed of as waste. The discharged fuel contains materials that can be suitable for ...

متن کامل

Verification measurements of the IRMM-1027 and the IAEA large-sized dried (LSD) spikes

In the frame of the accountancy measurements of the fissile materials, reliable determinations of the plutonium and uranium content in spent nuclear fuel are required to comply with international safeguards agreements. Large-sized dried (LSD) spikes of enriched 235U and 239Pu for isotope dilution mass spectrometry (IDMS) analysis are routinely applied in reprocessing plants for this purpose. A ...

متن کامل

Management 48 th Annual Meeting of the Institute of Nuclear Materials Management

196 SAGSI: Its Role and Contribution to Safeguards Development ............................ 1 J. Carlson Abstract #163 Nuclear Issue of North Korea and Applicability of the IAEA Safeguards System to North Korea .................................................................................................. 6 K. Choe163 Nuclear Issue of North Korea and Applicability of the IAEA Safeguards Syst...

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

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 2014