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Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessels...

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Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessels (IAEA TECDOC-1470)

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పుస్తక నాణ్యత అంచనా వేయడాలనుకుంటే దీన్ని దింపుకోండి

దింపుకొన్న ఫైళ్ళ నాణ్యత ఏమిటి?

సంవత్సరం:

2005

భాష:

english

పేజీల సంఖ్య:

127

ఫైల్:

PDF, 2.05 MB

IPFS:

,

english, 2005

ఆన్‌లైన్‌లో చదవండి

కి మార్పిడి జరుగుతూ ఉంది.

కి మార్పిడి విఫలమైంది!

మీకు ఆసక్తిగా కనిపించ వచ్చు

— PERIODIC INSPECTION OF PRESSURE VESSELS

Electric Power Research Institute — EPRI Boiler Condition Assessment Guideline 4 Edition

— Ageing of Steam Generators (IAEA TECDOC-981)

— Aged, Decommissioned Mtl Collection and Testing (csni-r1995-17)

— Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessel Internals (IAEA TECDOC-1471)

— Aging Management of LWR Components - Vol 5 [Metal Containments]

— Effects of Ni on Irrad. Embrittlement (LW Press Vessel Steels) (IAEA TECDOC-1441)

— Erosion and Corrosion of Nuclear Powerplant Mtls (csni-r1994-26)

— Fracture Mechanics and NDE in Safety Assessment of Components (csni-r91-14)

— Fracture Mechanics Verification by Lg-Scale Testing (csni-r1992-21)

— Managing Ageing of Mtls in Spent-Fuel Storage Facilities (IAEA TRS-443)

— Master Curve Appr to Reactor Pressure Vessel Integ in Nucl Powerplants (IAEA TRS-429)

— Mgmt of Ageing of PWR Pressure Vessels (IAEA TECDOC-1120)

— Mgmt of Ageing of PWR Vessel Internals (IAEA TECDOC-1119)

— Plant Life Mgmt - Long-Term Operation of Light-Water Reactors (IAEA TR-448)

— Repair Practices - Nucl Pwrplnt Containment Metallic Press. Boundaries

— Safety Aspects of Nuclear Powerplant Ageing (IAEA TECDOC-540)

— Stable Crack Growth During Overstressing, Testing of Pressure Vessels (csni85-113)

— System 80+ Standard [nucl. powerplnt] Design - Vol 05

— Tech Aspects of Ageing for Long-Term Operations (csni-r2002-26)

— Thermal Fatigue in LWR Piping Caused by Mixing, Stratification (csni-r98-8)

— VVER Re-Embrittlement (presentation slides)

— Water Reactor Safety Info Meeting Vol 3 [21st, Transactions]

— Water Reactor Safety Info Meeting [25th, transactions]

D A Conley; Jerald L Edson; C F Fineman; Idaho National Engineering Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering — Aging study of boiling water reactor high pressure injection systems

International Atomic Energy Agency — Assessment and management of ageing of major nuclear power plant components important to safety: concrete containment buildings

International Atomic Energy Agency — Management of research reactor ageing

Vikram N Shah; Arthur G Ware; A M Porter; Idaho National Engineering Laboratory.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs — Review of industry efforts to manage pressurized water reactor feedwater nozzle, piping, and feedring cracking and wall thinning

OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations. Principal Working Group No. 3 on Primary Circuit Integrity — Workshop on Reactor Coolant System Leakage and Failure Probabilities : Koln (Germany), 9-11 December 1992

Pachner J. (red.) — Assessment and management of ageing of major nuclear power plant components important to safety: Primary piping in PWRs

— Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process

Liu Cengdian (Eds.) — Design & Analysis. Proceedings of the Sixth International Conference Held in Beijing, People's Republic of China, 11–15 September 1988

Maurice Stewart and Lewis Oran (Eds.) — Pressure Vessels Field Manual. Common Operating Problems and Practical Solutions

P. B. Hirsch (Author) — Fracture, Plastic Flow and Structural Integrity in the Nuclear Industry-Proceedings of the 7th Symposium Organised by the Technical Advisory Group on Structural Integrity in the Nuclear Industry

K. R. Rao — Companion guide to the ASME boiler and pressure vessel code: criteria and commentary on select aspects of the boiler & pressure vessel and piping codes

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