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	<title>In Cheol Bang &#187; Project</title>
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	<link>https://neths.unist.ac.kr</link>
	<description>UNIST Thermal-hydraulics and Reactor Safety Lab</description>
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		<title>10. Development of nanofluid technology using gallium and sodium</title>
		<link>https://neths.unist.ac.kr/10-%ec%86%8c%eb%93%90-%eb%83%89%ea%b0%81%ec%9e%ac-%ed%99%9c%ec%84%b1-%ec%a0%80%ea%b0%90-%ea%b8%b0%ec%88%a0-%ea%b0%9c%eb%b0%9c-%ea%b0%88%eb%a5%a8-%eb%b0%8f-%ec%86%8c%eb%93%90-%eb%82%98%eb%85%b8/</link>
		<comments>https://neths.unist.ac.kr/10-%ec%86%8c%eb%93%90-%eb%83%89%ea%b0%81%ec%9e%ac-%ed%99%9c%ec%84%b1-%ec%a0%80%ea%b0%90-%ea%b8%b0%ec%88%a0-%ea%b0%9c%eb%b0%9c-%ea%b0%88%eb%a5%a8-%eb%b0%8f-%ec%86%8c%eb%93%90-%eb%82%98%eb%85%b8/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 01:21:57 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=366</guid>
		<description><![CDATA[&#160; Safety and economic feasibility &#160; After the Fukushima accident, the concerns on nuclear safety are increasing more than ever [&#8230;]]]></description>
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		<title>9. Development of Gallium-based passive decay heat removal system</title>
		<link>https://neths.unist.ac.kr/9-%ec%8b%a0%ea%b0%9c%eb%85%90%ec%9d%98-%ed%98%81%ec%8b%a0-%ec%9b%90%ec%a0%84-%ec%95%88%ec%a0%84%ea%b3%84%ed%86%b5-%ea%b0%9c%eb%b0%9c-ga-%eb%83%89%ea%b0%81-%ed%94%bc%eb%8f%99%ec%9e%94%ec%97%b4/</link>
		<comments>https://neths.unist.ac.kr/9-%ec%8b%a0%ea%b0%9c%eb%85%90%ec%9d%98-%ed%98%81%ec%8b%a0-%ec%9b%90%ec%a0%84-%ec%95%88%ec%a0%84%ea%b3%84%ed%86%b5-%ea%b0%9c%eb%b0%9c-ga-%eb%83%89%ea%b0%81-%ed%94%bc%eb%8f%99%ec%9e%94%ec%97%b4/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 01:19:01 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=361</guid>
		<description><![CDATA[Ga-cooled Passive Decay Heat Removal System Preliminary Concept of Advanced passive decay heat removal system (PDHRS) using gallium for SFR The [&#8230;]]]></description>
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		<title>8. Design and Development of safety analysis code for ultra long-life core reactor (UCFR)</title>
		<link>https://neths.unist.ac.kr/8-ucfr-%ec%84%a4%ea%b3%84-%eb%b0%8f-%ec%95%88%ec%a0%84%ed%95%b4%ec%84%9d-%ec%bd%94%eb%93%9c-%ea%b0%9c%eb%b0%9c-%ec%b4%88%ec%9e%a5%ec%a3%bc%ea%b8%b0-%ea%b3%a0%ec%86%8d%eb%a1%9c/</link>
		<comments>https://neths.unist.ac.kr/8-ucfr-%ec%84%a4%ea%b3%84-%eb%b0%8f-%ec%95%88%ec%a0%84%ed%95%b4%ec%84%9d-%ec%bd%94%eb%93%9c-%ea%b0%9c%eb%b0%9c-%ec%b4%88%ec%9e%a5%ec%a3%bc%ea%b8%b0-%ea%b3%a0%ec%86%8d%eb%a1%9c/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 01:16:42 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=356</guid>
		<description><![CDATA[3D view of one assembly of UCFR For analysis of thermal hydraulic safety aspect, MATRA-LMR and SLTHEN code are used. [&#8230;]]]></description>
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		<title>7. Design of Vented Fuel for ultra long-life core reactor (UCFR)</title>
		<link>https://neths.unist.ac.kr/7-%eb%b0%b0%ea%b8%b0%ed%98%95-%ed%95%b5%ec%97%b0%eb%a3%8c%eb%b4%89-%ec%84%a4%ea%b3%84-%ec%b4%88%ec%9e%a5%ec%a3%bc%ea%b8%b0%eb%a5%bc-%ec%9c%84%ed%95%9c-vented-fuel-%ea%b8%b0/</link>
		<comments>https://neths.unist.ac.kr/7-%eb%b0%b0%ea%b8%b0%ed%98%95-%ed%95%b5%ec%97%b0%eb%a3%8c%eb%b4%89-%ec%84%a4%ea%b3%84-%ec%b4%88%ec%9e%a5%ec%a3%bc%ea%b8%b0%eb%a5%bc-%ec%9c%84%ed%95%9c-vented-fuel-%ea%b8%b0/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 01:14:50 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=354</guid>
		<description><![CDATA[UCFR (Ultra-long-life Core Fast Reactor) The concept for UCFR is designed to be operating at higher temperature and neutron dose [&#8230;]]]></description>
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		<title>6. Development of heat transfer enhancement technique for high-power density nuclear fuel</title>
		<link>https://neths.unist.ac.kr/6-%ea%b3%a0%ec%b6%9c%eb%a0%a5%eb%b0%80%eb%8f%84-%ed%95%b5%ec%97%b0%eb%a3%8c%eb%b4%89-%ec%84%a4%ea%b3%84-%ec%97%b4%ec%a0%84%eb%8b%ac-%ec%a6%9d%ec%a7%84-%ea%b8%b0%ec%88%a0-%ea%b0%9c/</link>
		<comments>https://neths.unist.ac.kr/6-%ea%b3%a0%ec%b6%9c%eb%a0%a5%eb%b0%80%eb%8f%84-%ed%95%b5%ec%97%b0%eb%a3%8c%eb%b4%89-%ec%84%a4%ea%b3%84-%ec%97%b4%ec%a0%84%eb%8b%ac-%ec%a6%9d%ec%a7%84-%ea%b8%b0%ec%88%a0-%ea%b0%9c/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 01:12:58 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=349</guid>
		<description><![CDATA[&#160; For every engineering area, it is very important to increase the way of heat transfer to get high power [&#8230;]]]></description>
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		<title>5. Development of innovative safety system for nuclear power plant and severe accident management strategy</title>
		<link>https://neths.unist.ac.kr/5-%ec%8b%a0%ea%b0%9c%eb%85%90%ec%9d%98-%ed%98%81%ec%8b%a0-%ec%9b%90%ec%a0%84-%ec%95%88%ec%a0%84%ea%b3%84%ed%86%b5-%eb%b0%8f-%ec%a4%91%eb%8c%80%ec%82%ac%ea%b3%a0-%eb%8c%80%ec%b2%98-%ec%8b%9c%ec%8a%a4/</link>
		<comments>https://neths.unist.ac.kr/5-%ec%8b%a0%ea%b0%9c%eb%85%90%ec%9d%98-%ed%98%81%ec%8b%a0-%ec%9b%90%ec%a0%84-%ec%95%88%ec%a0%84%ea%b3%84%ed%86%b5-%eb%b0%8f-%ec%a4%91%eb%8c%80%ec%82%ac%ea%b3%a0-%eb%8c%80%ec%b2%98-%ec%8b%9c%ec%8a%a4/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 01:10:18 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=343</guid>
		<description><![CDATA[&#160; Wall temperature variation during water reflood &#160; In a nuclear reactor system, the emergency core cooling system (ECCS) provides [&#8230;]]]></description>
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		<title>4. Design of safety system and safety assessment using system analysis code for nuclear power plant</title>
		<link>https://neths.unist.ac.kr/4-%ec%b2%a8%eb%8b%a8-%ec%8b%9c%ec%8a%a4%ed%85%9c-%ec%84%a4%ea%b3%84-%eb%b0%8f-%ec%95%88%ec%a0%84%ed%95%b4%ec%84%9d-%ec%bd%94%eb%93%9c-%ea%b0%9c%eb%b0%9c-%ec%9b%90%ec%a0%84/</link>
		<comments>https://neths.unist.ac.kr/4-%ec%b2%a8%eb%8b%a8-%ec%8b%9c%ec%8a%a4%ed%85%9c-%ec%84%a4%ea%b3%84-%eb%b0%8f-%ec%95%88%ec%a0%84%ed%95%b4%ec%84%9d-%ec%bd%94%eb%93%9c-%ea%b0%9c%eb%b0%9c-%ec%9b%90%ec%a0%84/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 01:07:28 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=329</guid>
		<description><![CDATA[원자력 발전소 안전성 향상을 위해서는 이와 관련된 해석코드의 수행이 필수적이다. 이러한 해석코드의 수행은 핵연료의 국부적인 부분에서 시작하여 피복재, 원자로 노심, [&#8230;]]]></description>
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		<title>3. Heat transfer enhancement technique using nanofluid for coolant in nuclear applications</title>
		<link>https://neths.unist.ac.kr/3-%ec%b2%a8%eb%8b%a8-%eb%83%89%ea%b0%81%ec%9e%ac-%ea%b8%b0%ec%88%a0-%ea%b0%9c%eb%b0%9c-%eb%82%98%eb%85%b8%ec%9c%a0%ec%b2%b4-%ec%97%b4%ec%a0%84%eb%8b%ac-%ec%a6%9d%ec%a7%84-%ea%b8%b0%ec%88%a0/</link>
		<comments>https://neths.unist.ac.kr/3-%ec%b2%a8%eb%8b%a8-%eb%83%89%ea%b0%81%ec%9e%ac-%ea%b8%b0%ec%88%a0-%ea%b0%9c%eb%b0%9c-%eb%82%98%eb%85%b8%ec%9c%a0%ec%b2%b4-%ec%97%b4%ec%a0%84%eb%8b%ac-%ec%a6%9d%ec%a7%84-%ea%b8%b0%ec%88%a0/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 00:59:18 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=324</guid>
		<description><![CDATA[A variety of Generation III/III+ water-cooled reactor designs featuring enhanced safety and improved economics are being proposed by nuclear power [&#8230;]]]></description>
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		<title>2. Development of heat transfer enhancement technique for cladding of nuclear fuel</title>
		<link>https://neths.unist.ac.kr/2-%ec%b2%a8%eb%8b%a8-%ed%95%b5%ec%97%b0%eb%a3%8c-%ed%94%bc%eb%b3%b5%ec%9e%ac-%ea%b0%9c%eb%b0%9c-%ed%94%bc%eb%b3%b5%ec%9e%ac-%ec%97%b4%ec%a0%84%eb%8b%ac-%ec%a6%9d%ec%a7%84-%ea%b8%b0%ec%88%a0/</link>
		<comments>https://neths.unist.ac.kr/2-%ec%b2%a8%eb%8b%a8-%ed%95%b5%ec%97%b0%eb%a3%8c-%ed%94%bc%eb%b3%b5%ec%9e%ac-%ea%b0%9c%eb%b0%9c-%ed%94%bc%eb%b3%b5%ec%9e%ac-%ec%97%b4%ec%a0%84%eb%8b%ac-%ec%a6%9d%ec%a7%84-%ea%b8%b0%ec%88%a0/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 00:55:42 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=319</guid>
		<description><![CDATA[Recently undesired Axial Offset Anomaly (AOA) was issued in the nuclear industry. AOA referring to an unexpected neutron flux depression [&#8230;]]]></description>
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		<title>1. Development of unmelting nuclear fuel: high thermal conductivity fuel material</title>
		<link>https://neths.unist.ac.kr/1-%eb%85%b9%ec%a7%80-%ec%95%8a%eb%8a%94-%ed%95%b5%ec%97%b0%eb%a3%8c-%ea%b0%9c%eb%b0%9c-%ec%97%b4%ec%a0%84%eb%8f%84%eb%8f%84%ea%b0%80-%ec%9a%b0%ec%88%98%ed%95%9c-%ed%95%b5%ec%97%b0%eb%a3%8c/</link>
		<comments>https://neths.unist.ac.kr/1-%eb%85%b9%ec%a7%80-%ec%95%8a%eb%8a%94-%ed%95%b5%ec%97%b0%eb%a3%8c-%ea%b0%9c%eb%b0%9c-%ec%97%b4%ec%a0%84%eb%8f%84%eb%8f%84%ea%b0%80-%ec%9a%b0%ec%88%98%ed%95%9c-%ed%95%b5%ec%97%b0%eb%a3%8c/#comments</comments>
		<pubDate>Thu, 18 Jun 2015 00:53:02 +0000</pubDate>
		<dc:creator><![CDATA[neths]]></dc:creator>
				<category><![CDATA[Project]]></category>

		<guid isPermaLink="false">http://faculty.unist.ac.kr/neths/?p=315</guid>
		<description><![CDATA[&#160; The commercial nuclear power industry is interested in advanced fuels that can produce higher power levels with a higher [&#8230;]]]></description>
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