Validation of ORIGEN-S Decay Heat Predictions for LOCA Analysis

نویسنده

  • Ian Gauld
چکیده

Recent developments in the nuclear data libraries used by the ORIGEN-S isotope generation and depletion code have enabled the extension of the code to accurately predict the delayed energy release rates from nuclear decay (decay heat) at very short cooling times of interest to reactor accident analysis. Historically this time domain has required integral methods, such as the ANS5.1 decay heat standard, because isotopic summation codes could not be reliably applied due to incomplete nuclear data. This paper describes work to validate ORIGEN-S against experimental measurements for decay times that extend down to about 1 second after fission. Benchmarks using measured gamma ray spectra following fission are also included because these results are important to predicting spatial energy deposition from delayed gamma energy release.

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

Problem - Dependent ORIGEN Library Compression to Increase Computational Efficiency

ORIGEN is a highly accurate code to model used fuel isotopic inventory evolution and associated radiation sources. The Oak Ridge Isotope Generation (ORIGEN) code is a depletion model to calculate neutron activation, actinide transmutation, fission product generation, and radiation source terms. This is done through analysis of the full isotopic transition matrix to solve the rate equations that...

متن کامل

The Overall Heat Transfer Characteristics of a Double Pipe Heat Exchanger: Comparison of Experimental Data with Predictions of Standard Correlations

The single-phase flow and thermal performance of a double pipe heat exchanger are examined by experimental methods. The working fluid is water at atmospheric pressure. Temperature measurements at the inlet and outlet of the two streams and also at an intermediate point half way between the inlet and outlet is made, using copper-constantan thermocouple wires. Mass flow rates for each stream are ...

متن کامل

Sampling Based Uncertainty Analysis of 10 % Hot Leg Break Loca in Large Scale Test Facility

Thermal hydraulic system codes are complex tools developed to estimate the transient behaviour of nuclear power plants (NPPs) during off-normal conditions. The evaluation of safety margins, the operator training, the optimization of the plant design and related emergency procedures are some of the major applications of these codes. Best estimate computer codes are used to calculate postulated a...

متن کامل

UWFDM-1147 Activation, Decay Heat, and Waste Disposal Analyses for the ARIES-AT Power Plant

Detailed activation, decay heat and waste disposal calculations of the ARIES-AT design are performed to evaluate the safety aspects of the device. The high initial activity of the SiC highly irradiated components translates directly into a higher initial decay heat for these structures than for the well-protected steel-based components. However, after a one-hour cool-down period, the SiC decay ...

متن کامل

NUREG/IA-0185 "Development and Validation of a Transition Boiling Model for the RELAP5/MOD3 Reflood Simulation"

The heat transfer model of the RELAP5/MOD3.1 (R5M3) code was extensively reviewed and assessed. The most important deficiency of the current version of the code was attributed to its treatment of the transition boiling heat transfer regime. The current transition boiling model significantly underpredicts the heat transfer rate to the liquid phase. Since at low quality conditions the liquid boil...

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 2006