• Nuclear Engineering and Technology
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• v.56 no.3
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• pp.873-879
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• 2024

A sodium-cooled fast reactor (SFR) core has a potential of prompt criticality due to a change of core material distribution during a severe accident, and the resultant energy release has been one of the safety issues of SFRs. In this study, the safety assessment of an unprotected loss-of-flow (ULOF) in a small SFR (SSFR) has been performed using the SIMMER-IV computer code, which couples the models of space- and time-dependent neutronics and multi-component, multi-field thermal hydraulics in three dimensions. The code, therefore, is applicable to the simulations of transient behaviors of extended disrupted core material motion and its reactivity effects during the transition phase (TP) of ULOF, including a potential of prompt-criticality power excursions driven by fuel compaction. Several conservative assumptions are used in the TP analysis by SIMMER-IV. It was found out that one of the important mechanisms that drives the reactivity-inserting fuel motion was sodium vapor pressure resulted from a fuel-coolant interaction (FCI), which itself was non-energetic local phenomenon. The uncertainties relating to FCI is also evaluated in much conservative way in the sensitivity analysis. From this study, the ULOF characteristics in an SSFR have been understood. Occurrence of recriticality events under conservative assumptions are plausible, but their energy releases are limited.

• Korean journal of food and cookery science
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• v.12 no.3
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• pp.331-338
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• 1996

The main aim of this study was to develop carrot soups with fishery products, which is improved from traditional gruel of Cheju island. For this the optimal procedure and ingredient mixing ratio for making basic carrot soup was determined through the instrumental measurement, the sensory evaluation and the nutrient analysis, and then the carrot-fishery soups were prepared by mixing the fishery products from Cheju island. The results were as follows: The optimal procedure for making basic carrot soup was to saute the sliced carrots and soaked rices with the sesame oil for 5 min, add the water, bring to a boil for 6 min, simmer for 15 min, then puree the soup. The optimal ingredient mixing ratio in the basic carrot soup was carrot 300 g: rice 45 g: water 900 $m\ell$: sesame oil 15 $m\ell$: salt 5 g. For preparing carrot-fishery soups were the optimal fishery products mixing ratio i) 30% tile fish or crab, ii) prawn, abalone, top shell, or ear shell 20%, iii) sea urchin 15%, iv) fusiform or gulf weed 5％. The order of sensory evaluation scores, on a 5-point scale, were sea urchin, crab > top shell, tile fish > abalone, ear shell > prawn > coral fish > fusiform, gulf weed. Nutrient composition analysis showed that vitamin A was 5 times higher in carrot soup than in pumpkin soup. Sensory evaluation scores show that carrot soup was prepared to pumpkin soup. A portion (200 g) of the soup would provide 144% of the recommended daily allowance of vitamin A. The results of this work indicate that an acceptable carrot-fishery soups of better nutritional and sensory values than pumpkin soup can be prepared.

• Nuclear Engineering and Technology
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• v.47 no.3
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• pp.240-252
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• 2015

In the original licensing application for the prototype fast-breeder reactor, MONJU, the event progression during an unprotected loss of flow (ULOF), which is one of the technically inconceivable events postulated beyond design basis, was evaluated. Through this evaluation, it was confirmed that radiological consequences could be suitably limited even if mechanical energy was released. Following the Fukushima-Daiichi accident, a new nuclear safety regulation has become effective in Japan. The conformity of MONJU to this new regulation should hence be investigated. The objectives of the present study are to conduct a preliminary evaluation of ULOF for MONJU, reflecting the knowledge obtained after the original licensing application through CABRI experiments and EAGLE projects, and to gain the prospect of in-vessel retention for the conformity of MONJU to the new regulation. The preliminary evaluation in the present study showed that no significant mechanical energy release would take place, and that thermal failure of the reactor vessel could be avoided by the stable cooling of disrupted-core materials. This result suggests that the prospect of in-vessel retention against ULOF, which lies within the bounds of the original licensing evaluation and conforms to the new nuclear safety regulation, will be gained.