Empirical and Mechanistic Transient Fission Gas Release Model for High-Burnup LOCA Conditions

نویسندگان

چکیده

In response to the nuclear industry desire extend burnup beyond current licensing practices, US Nuclear Regulatory Commission (NRC) released a research information letter (RIL) that provides basis for analyzing fuel fragmentation, relocation, and dispersal (FFRD) in light-water reactors. Of five elements discussed, most ambiguous is significance of transient fission gas (FG) release (FGR) (tFGR) its effects on performance under loss-of-coolant accident conditions. fresh fuel, FG migration eventual primarily governed by diffusion-based mechanisms at higher temperatures (>1,000°C). However, governing FGR changes as increases. More recent indicates increases increases, specifically temperature conditions, this occurs lower with new mechanism. This behavior has been attributed microcracking likely related microstructure embrittlement presence over pressurized bubbles. The NRC RIL outlines complexity phenomenon need deeper understanding adequately address FFRD regulatory application. Therefore, manuscript intends summarize publicly available tFGR data discuss observed dependencies (e.g., burnup, heating rate, sample geometry, terminal temperature). An empirical model developed benchmarked against recently published experimental data. limited conditions which fitting exist and, therefore, high-level discussion included provide roadmap atomistically-informed multiscale modeling conjunction collection develop mechanistic widely applicable broad range high burnup.

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

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Modelling of Fission Gas Behaviour in High Burnup Nuclear Fuel

The safe and economic operation of nuclear power plants (NPPs) requires that the behaviour and performance of the fuel can be calculated reliably over its expected lifetime. This requires highly developed codes that treat the nuclear fuel in a general manner and which take into account the large number of in uences on fuel behaviour, e.g. thermal, mechanical, chemical, etc. Although many mature...

متن کامل

Recovery and Restructuring induced by Fission Energy Ions in High Burnup Nuclear Fuel

In light water commercial reactors, extensive change of grain structure was found at high burnup ceramic fuels. The mechanism is driven by bombardment of fission energy fragments and studies were conducted by combining accelerator based experiments and computer science. Specimen of CeO2 was used as simulation material of fuel ceramics. With swift heavy ion (Xe) irradiation on CeO2, with 210 MeV...

متن کامل

Conditions for the manifestation of transient effects in fission

The conditions for the manifestation of transient effects in fission are carefully examined by analysing experimental data where fission is induced by peripheral heavy-ion collisions at relativistic energies. Experimental total nuclear fission cross sections of U at 1⋅A GeV on gold and uranium targets are compared with the predictions of a nuclear-reaction code, where transient effects in fissi...

متن کامل

Fission Gas Release Comparison for PWR Duplex Fuel Pellets

Current research has identified Duplex pellets as an effective strategy for decreasing the centerline temperature of the fuel. However, before this design can be widely utilized several areas, including fission gas release, need to be better characterized. Therefore, this paper seeks to ascertain the relative difference in fission gas release between a standard solid UO2 reference design and a ...

متن کامل

A combined empirical and mechanistic codon model.

The evolutionary selection forces acting on a protein are commonly inferred using evolutionary codon models by contrasting the rate of synonymous to nonsynonymous substitutions. Most widely used models are based on theoretical assumptions and ignore the empirical observation that distinct amino acids differ in their replacement rates. In this paper, we develop a general method that allows assim...

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

ژورنال

عنوان ژورنال: Journal of Nuclear Materials

سال: 2023

ISSN: ['1873-4820', '0022-3115']

DOI: https://doi.org/10.1016/j.jnucmat.2023.154557