Nuclear reactor safety systems

Results: 253



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21IAEA SAFETY STANDARDS SERIES Design of Reactor Containment Systems

IAEA SAFETY STANDARDS SERIES Design of Reactor Containment Systems

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Source URL: www-pub.iaea.org

Language: English - Date: 2004-09-16 10:20:59
226. ENGINEERED SAFETY FUTURES F) Main forced-circulation circuit parameter monitoring system. Operational parameters are displayed on the Main Control Room (MCR) using visual and recording instruments, annunciation window

6. ENGINEERED SAFETY FUTURES F) Main forced-circulation circuit parameter monitoring system. Operational parameters are displayed on the Main Control Room (MCR) using visual and recording instruments, annunciation window

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Source URL: www.lei.lt

Language: English - Date: 2010-04-09 09:08:13
237. AUXILIARY SYSTEMS This Section describes the numerous cooling circuits of the plant. This includes circuits using purified and demineralized water employed for cooling safety related equipment around the core block, c

7. AUXILIARY SYSTEMS This Section describes the numerous cooling circuits of the plant. This includes circuits using purified and demineralized water employed for cooling safety related equipment around the core block, c

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Source URL: www.lei.lt

Language: English - Date: 2010-04-09 09:08:16
24American Nuclear Society Backgrounder: Japanese Earthquake/Tsunami; Problems with Nuclear Reactors:22 PM EST To begin, a sense of perspective is needed… right now, the Japanese earthquake/tsunami is clearly

American Nuclear Society Backgrounder: Japanese Earthquake/Tsunami; Problems with Nuclear Reactors:22 PM EST To begin, a sense of perspective is needed… right now, the Japanese earthquake/tsunami is clearly

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Source URL: bnrc.berkeley.edu

Language: English - Date: 2013-03-09 14:53:18
252. Design Basis Accidents of control rod channel cooling system. Single or multiple main circulation pump trip are examples of loss-of-flow transients. Loss-of-coolant accidents include full or partial breaks of group di

2. Design Basis Accidents of control rod channel cooling system. Single or multiple main circulation pump trip are examples of loss-of-flow transients. Loss-of-coolant accidents include full or partial breaks of group di

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Source URL: www.lei.lt

Language: English - Date: 2010-04-09 09:09:17
26

PDF Document

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Source URL: www.oecd-nea.org

Language: English - Date: 2012-09-19 10:29:15
27On Boundary Conditions for Instrumentation and Control Systems in Safety Analysis Marco Lanfredini GRNSPG-Univesrity of Pisa L.go L. Lazzarino 1, 56100 Pisa Italy

On Boundary Conditions for Instrumentation and Control Systems in Safety Analysis Marco Lanfredini GRNSPG-Univesrity of Pisa L.go L. Lazzarino 1, 56100 Pisa Italy

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Source URL: www.djs.si

Language: English - Date: 2013-11-20 15:44:24
28NUCLEAR QUALIFICATIONS VAPORE Plant for Thermomechanical and Fluid-Dynamic Tests on Components and Systems

NUCLEAR QUALIFICATIONS VAPORE Plant for Thermomechanical and Fluid-Dynamic Tests on Components and Systems

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Source URL: old.enea.it

Language: English - Date: 2010-11-26 04:48:50
29Microsoft Word - E_本文_final_.doc

Microsoft Word - E_本文_final_.doc

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Source URL: www.genanshin.jp

Language: English - Date: 2015-03-27 05:47:52
30A4  SAFETY EVALUATION OF INDIAN NUCLEAR POWER PLANTS STANDARD INDIAN PRESSURIZED HEAVY WATER REACTOR (IPHWR)

A4 SAFETY EVALUATION OF INDIAN NUCLEAR POWER PLANTS STANDARD INDIAN PRESSURIZED HEAVY WATER REACTOR (IPHWR)

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Source URL: npcil.nic.in

Language: English - Date: 2011-07-21 07:08:13