Nuclear reactor safety system

Results: 67



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11CHAPTER 13 SAFETY PROMOTIONAL ACTIVITIES AERB organizes and/or participates in discussion meetings and other professional meets to deliberate on nuclear and radiation safety aspects and the system of

CHAPTER 13 SAFETY PROMOTIONAL ACTIVITIES AERB organizes and/or participates in discussion meetings and other professional meets to deliberate on nuclear and radiation safety aspects and the system of

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Source URL: www.aerb.gov.in

Language: English - Date: 2014-08-17 08:39:09
12General Distribution  October, 1999 ISOE INFORMATION SHEET Replacement of Reactor Internals and Full System

General Distribution October, 1999 ISOE INFORMATION SHEET Replacement of Reactor Internals and Full System

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Source URL: www.nsra.or.jp

Language: English - Date: 2014-02-28 01:38:55
13Reference - 1  Overview of Safety at Fukushima Daiichi Nuclear Power Station We at TEPCO feel deep remorse that the safety systems that we stated would operate in case of accident in the Fukushima Daiichi establishing pe

Reference - 1 Overview of Safety at Fukushima Daiichi Nuclear Power Station We at TEPCO feel deep remorse that the safety systems that we stated would operate in case of accident in the Fukushima Daiichi establishing pe

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Source URL: www4.tepco.co.jp

Language: English - Date: 2012-12-14 05:27:48
14Pressurized Water Small Modular Reactor (SMR), Design Basis Accident Analysis using the ASTEC code 1 2

Pressurized Water Small Modular Reactor (SMR), Design Basis Accident Analysis using the ASTEC code 1 2

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Source URL: www.djs.si

Language: English - Date: 2015-02-07 16:50:28
15Simulation of AP1000’s Passive Containment Cooling with the German Containment Code System COCOSYS Philipp Broxtermann, Hans-Josef Allelein Institute for Reactor Safety and Reactor Technology (LRST), RWTH Aachen Univer

Simulation of AP1000’s Passive Containment Cooling with the German Containment Code System COCOSYS Philipp Broxtermann, Hans-Josef Allelein Institute for Reactor Safety and Reactor Technology (LRST), RWTH Aachen Univer

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Source URL: www.djs.si

Language: English - Date: 2012-07-16 15:41:58
16Manuscript Title in Title Case

Manuscript Title in Title Case

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Source URL: www.djs.si

Language: English - Date: 2012-07-16 15:43:22
17Calculations of a Postulated Stylized Small Region of a VVER-1000 Core by KARATE code system and MCNP György Hegyi, Csaba Maráczy, Gábor Hordósy, Emese Temesvári MTA KFKI Atomic Energy Research Institute Konkoly The

Calculations of a Postulated Stylized Small Region of a VVER-1000 Core by KARATE code system and MCNP György Hegyi, Csaba Maráczy, Gábor Hordósy, Emese Temesvári MTA KFKI Atomic Energy Research Institute Konkoly The

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Source URL: www.djs.si

Language: English - Date: 2012-07-16 15:36:03
18Page 1 of 11  Foreword This course is intended for a senior undergraduate or graduate engineering or science student. Some basic familiarity with nuclear power system design and operation is assumed. The objective is tha

Page 1 of 11 Foreword This course is intended for a senior undergraduate or graduate engineering or science student. Some basic familiarity with nuclear power system design and operation is assumed. The objective is tha

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Source URL: www.nuceng.ca

Language: English - Date: 2015-01-11 13:21:39
19Reference - 1  Overview of Safety at Fukushima Daiichi Nuclear Power Station We at TEPCO feel deep remorse that the safety systems that we stated would operate in case of accident in the Fukushima Daiichi establishing pe

Reference - 1 Overview of Safety at Fukushima Daiichi Nuclear Power Station We at TEPCO feel deep remorse that the safety systems that we stated would operate in case of accident in the Fukushima Daiichi establishing pe

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Source URL: www.tepco.co.jp

Language: English - Date: 2012-12-14 05:27:48
20Design Requirements and Engineering Considerations

Design Requirements and Engineering Considerations

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Source URL: www.nuceng.ca

Language: English - Date: 2015-01-10 17:09:25