Transient Fuel Behavior and Failure Condition in the CABRI-2 Experiments

Sato, Ikken; Lemoine, Francette; Struwe, D.

doi:10.13182/nt04-a3464

Cited by 37 publications

(15 citation statements)

References 4 publications

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“…1,2,4) As the fuel enthalpy at PPN before TOP, results of the PAPAS-2S code, 4) which can be used to calculate fuel thermal conditions including coolant boiling behavior, are used. Injected energy at PPN during TOP is added to the pre-TOP enthalpy calculated using PAPAS-2S to deduce the EIP.…”

Section: Discussionmentioning

confidence: 99%

“…It can also be concluded that there is no basic difference between the single-pin and three-pincluster geometries. (3) Background of Fuel Penetration Dependence on the Fuel Enthalpy In a previous study, 4) it was concluded that large-scale fuel swelling and disruption take place at about 1.0 kJ/g, and the fuel acquires a certain mobility at about 1.2 kJ/g. In general, the axial profile of fuel enthalpy distribution is continuous with its peak slightly above the midplane.…”

Section: Discussionmentioning

confidence: 99%

“…Such plenum gas blowout behavior is basically common to the former CABRI single-pin tests. 4) Based on the response of the TCs located on the outer surface of the niobium tube, the progression of the coolant channel voiding in the TP2 test is schematically illustrated in Fig. 5.…”

Section: Before the Top Triggeringmentioning

confidence: 99%

“…In the preceding CABRI programs, [1][2][3][4] behavior during the ULOF accident was studied using a single-pin geometry. Through tests in these programs, valuable information on fuel failure and postfailure material relocation behavior was obtained.…”

Section: Introductionmentioning

confidence: 99%

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Three-Pin Cluster CABRI Tests Simulating the Unprotected Loss-of-Flow Accident in Sodium-Cooled Fast Reactors

Onoda

Fukano

Sato

et al. 2011

Journal of Nuclear Science and Technology

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Two three-pin cluster tests simulating the Unprotected Loss-of-Flow (ULOF) accident of Sodiumcooled Fast Reactors (SFRs) were conducted focusing on postfailure fuel relocation and freezing behavior. These tests supplied complementary information to the existing CABRI tests with a single-pin geometry. Based on detailed data evaluation and theoretical interpretation for the three-pin cluster tests, it is concluded that axial fuel relocation and freezing are dominated by local fuel enthalpy, and the relation between penetration length and local fuel enthalpy observed in these CABRI tests is basically applicable to the large-bundle condition. It is also clarified that a fuel/steel mixture tends to create tight blockages near the axial ends of the relocating fuel. Part of the fission gas released from the heating-up and melting fuel is expected to be trapped within the bottled-up region between the upper and lower blockages and will keep this region pressurized for a relatively long period.

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Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

Section: Before the Top Triggeringmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Three-Pin Cluster CABRI Tests Simulating the Unprotected Loss-of-Flow Accident in Sodium-Cooled Fast Reactors

Onoda

Fukano

Sato

et al. 2011

Journal of Nuclear Science and Technology

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“…[1][2][3][4] In this program, the Viggen-4 fuel pin with a high smear density (approximately 90%TD, TD: Theoretical Density) was used for the E12 test, and the Ophelie-6 fuel pins with a low smear density (approximately 80%TD) were used for the E9 and E9bis tests. Through this program, it was understood that the fuel smear density was playing an important role in the failure threshold.…”

Section: Introductionmentioning

confidence: 99%

Fuel Pin Behavior under Slow-Ramp-type Transient-Overpower Conditions in the CABRI-FAST Experiments

Fukano

Onoda

Sato

et al. 2009

Journal of Nuclear Science and Technology

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In the CABRI-FAST experimental program, four in-pile tests were performed with slow-power-ramptype transient-overpower conditions (called hereafter as ''slow TOP'') to study transient fuel pin behavior under inadvertent control-rod-withdrawal-type events in liquid-metal-cooled fast breeder reactors. The slow TOP test with a preirradiated solid-pellet fuel pin under a power ramp rate of approximately 3%Po/s was realized as a comparatory test against an existing test in the CABRI-2 program where approximately 1%Po/s was adopted with the same type of fuel pin. In spite of the different power ramp rates, the evaluated fuel thermal conditions at the observed failure time are quite similar. Three slow TOP tests with the preirradiated annular fuel resulted in no pin failure showing a high failure threshold. Based on posttest examination data and a theoretical evaluation, it was concluded that intrapin free spaces, such as central hole, macroscopic cracks, and fuel-cladding gap, effectively mitigated the fuel cladding mechanical interaction. It was also clarified that cavity pressurization became effective only in the case of a very large amount of fuel melting. These CABRI-FAST slow TOP tests, in combination with the existing CABRI and TREAT tests, provided an extended slow TOP test database under various fuel and transient conditions.

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