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Research Papers

Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor

[+] Author and Article Information
Yoshitaka Fukano

Japan Atomic Energy Agency,
1 Shiraki,
Tsuruga-shi 919-1279, Fukui, Japan
e-mail: fukano.yoshitaka@jaea.go.jp

1Corresponding author.

Manuscript received October 19, 2017; final manuscript received June 15, 2018; published online January 24, 2019. Assoc. Editor: Jovica R. Riznic.

ASME J of Nuclear Rad Sci 5(1), 011001 (Jan 24, 2019) (13 pages) Paper No: NERS-17-1166; doi: 10.1115/1.4040649 History: Received October 19, 2017; Revised June 15, 2018

Local subassembly faults (LFs) have been considered to be of greater importance in safety evaluation in sodium-cooled fast reactors (SFRs) because fuel elements were generally densely arranged in the subassemblies (SAs) in this type of reactors, and because power densities were higher compared with those in light water reactors. A hypothetical total instantaneous flow blockage (HTIB) at the coolant inlet of an SA gives most severe consequences among a variety of LFs. Although an evaluation on the consequences of HTIB using SAS4A code was performed in the past study, SAS4A code was further developed by implementing analytical model of power control system in this study. An evaluation on the consequences of HTIB in an SFR by this developed SAS4A code was also performed in this study. It was clarified by the analyses considering power control system that the reactor would be safely shut down by the reactor protection system triggered by either of 116% over power or delayed neutron detector (DND) trip signals. Therefore, the conclusion in the past study that the consequences of HTIB would be much less severe than that of unprotected-loss-of-flow (ULOF) was strongly supported by this study. Furthermore, SAS4A code was newly validated using four in-pile experiments which simulated HTIB events. The validity of SAS4A application to safety evaluation on the consequence of HTIB was further enhanced in this study. Thus, the methodology of HTIB evaluation was established in this study together with the past study and is applicable to HTIB evaluations in other SFRs.

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Figures

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Fig. 1

Schematic drawings of three major initiators on local faults

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Fig. 2

Schematic drawings of test sections in SCARABEE BE + 1 and BE + 2 experiments

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Fig. 3

Schematic drawing of test section in SCARABEE BE + 3 experiment

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Fig. 4

Schematic drawing of test section in SCARABEE BE + 3bis experiment

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Fig. 5

Phenomena observed in the SCARABEE experiments

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Fig. 6

Axial power profile of SCARABEE BE+ series experiments

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Fig. 9

Flow chart of power control system

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Fig. 13

Reactivity and power histories of Case MAXCP

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Fig. 14

Reactivity and power histories of Case MAXCV

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Fig. 7

Calculated coolant and cladding temperatures compared with those in SCARABEE BE + 3 experimental results

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Fig. 8

Condition of fuel, cladding, coolant, and wrapper tube at main event in SCARABEE BE + 3 experiment

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Fig. 12

Condition of fuel, cladding, coolant, and wrapper tube at the initiation of main events for Case MAXCV

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Fig. 10

Maximum overpower reached in this study compared with experimental data for fuel smear densities lower than 86% theoretical density

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Fig. 11

Condition of fuel, cladding, coolant, and wrapper tube at the initiation of main events for Case MAXCP

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Fig. 15

Histories of net reactivity in the HTIB compared with that in ULOF

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Fig. 16

Histories of total reactor power in the HTIB compared with that in ULOF

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Fig. 17

Damaged SAs at the time of reactor shutdown in each analytical case compared with that in ULOF

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