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Fuel Failure Behavior of Unirradiated Fuel Rods under Reactivity Initiated Accident Conditions

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TLDR
In this article, an in-reactor experimental research on fuel behavior under reactivity initiated accident conditions has been performed in the Nuclear Safety Research Reactor (NSRR), where unirradiated test fuel rods were exposed to pulse-power at the energy depositions of 39-433 cal/g·UO2 in water environment with ambient pressure and temperature.
Abstract
An in-reactor experimental research on fuel behavior under reactivity initiated accident conditions has been performed in the Nuclear Safety Research Reactor (NSRR). Unirradiated test fuel rods were exposed to pulse-power at the energy depositions of 39-433 cal/g·UO2 in water environment with ambient pressure and temperature.Oxidation and deformation of the cladding commence at the energy deposition of about 140 cal/g·UO2, and increase almost in proportion to the energy deposition.There are two types of fuel failure which are characterized by the circumferential cracks in the cladding or guillotine type break, and by the accompaniment of fuel fragmentation. The threshold energy depositions for them are about 260 and 380 cal/g·UO2, respectively.The former is the brittle fracture of the cladding. The cladding material becomes thinner because of melting of the cladding inner surface, and becomes brittle by oxidation. The failure is caused by the prevention of cladding contraction at or after the time of quenching of the brittle cladding due to strong binding between the pellets and cladding.The latter is the failure caused by the melting of the pellet accompanied with the considerable loss of mechanical strength in the cladding, resulting in the generation of mechanical energy.

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Journal ArticleDOI

A study of fuel behavior under reactivity initiated accident conditions — review

TL;DR: In this article, results obtained in the 400 tests performed to simulate reactivity initiated accidents since 1975 in the Japanese Nuclear Safety Research Reactor, are described, including the effects of cooling environment, defective fuel elements, fuel design parameters, the behaviour of fuel elements for various reactor types, all done for a wide range of energy deposition.
Journal ArticleDOI

Effects of Rod Pre-Pressurization on Light Water Reactor Fuel Behavior during Reactivity Initiated Accident Conditions

TL;DR: In this paper, the effects of initial internal pressure on fuel rod behavior during reactivity initiated accident (RIA) conditions were investigated in the Nuclear Safety Research Reactor (NSRR).
Journal ArticleDOI

Zircaloy-UO2 and -Water Reactions and Cladding Temperature Estimation for Rapidly-Heated Fuel Rods under an RIA Condition

TL;DR: In this paper, the maximum cladding temperature can be estimated from measured oxidation thicknesses in the temperature range of 1,000~1,600°C, from melting microstructures in the range of 2,950°C and also from the volume fraction of precipitates, (U, Zr)02-x, in once-molten oxygen-stabilized α-zircaloy in 1,950~2,400°C.
Journal ArticleDOI

Evaluation of Effective Energy Deposition in Test Fuel during Power Burst Experiment in NSRR

TL;DR: In this paper, the authors attempted to evaluate the relative fission rate change in the test fuel subjected to the power burst testing in the NSRR through the measurements and analyses of the fission power changes.
Journal ArticleDOI

Cladding Embrittlement and Fuel Rod Failure Threshold under Reactivity Initiated Accident Condition

TL;DR: In this paper, a diffusion equation of oxygen was solved under a finite system with moving boundary conditions to obtain the oxygen concentration and evaluate the cladding embrittlement, which well explain the experimental results.
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