Master Curve Appr to Reactor Pressure Vessel Integ in Nucl...

Main
Master Curve Appr to Reactor Pressure...

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

0 / 0

คุณชอบหนังสือเล่มนี้มากแค่ไหน

คุณภาพของไฟล์เป็นอย่างไรบ้าง

ดาวน์โหลดหนังสือเพื่อประเมินคุณภาพของไฟล์

คุณภาพของไฟล์ที่คุณดาวน์โหลดมาเป็นอย่างไรบ้าง

ฉบับ/เล่ม:

launch

ปี:

2005

ภาษา:

english

จำนวนหน้า:

116

ไฟล์:

PDF, 1.34 MB

IPFS:

,

english, 2005

อ่านออนไลน์

ดาวน์โหลด (pdf, 1.34 MB)

กำลังแปลงเป็น อยู่

การแปลงเป็น ล้มเหลว

คุณอาจสนใจ

— MARTI Digial Cellcast

D. François and A. Pineau (Eds.) — From Charpy To Present Impact Testing

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

unknown — Effect of Neutron Irradiation on Fracture Toughness of Austentitic Stainless Steels

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

— Embrittlement DataBase Vers 1

— Flow Locallization Procs in Deformation of Irradiated Reactor Structure Alloys

— Fusion Reactor Materials [Semi-Annual Rpt Dec 31, 1996]

— Fusion Reactor Materials [Semi-Annual Rpt Dec 31, 1997]

— Fusion Reactor Materials [Semi-Annual Rpt Jun 30, 1994]

— Fusion Reactor Materials [Semi-Annual Rpt Jun 30, 1997]

— Fusion Reactor Materials [Semi-Annual Rpt Mar 31, 1990]

— Fusion Reactor Materials [Semi-Annual Rpt Mar 31, 1993]

— Fusion Reactor Materials [Semi-Annual Rpt Mar 31, 1995]

— Fusion Reactor Materials [Semi-Annual Rpt Sep 30, 1993]

— Fusion Reactor Materials [Semi-Annual Rpt Sep 30, 1994]

— Infl of High-Dose Irrad on Core Struct, Fuel Mtls - Adv Reactors (IAEA TECDOC-1039)

— Irradiation Damage Processes in RPV Steels (presentation slides)

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

— Reactor Mtls Pgm - Baseline Mtls Props Hbk - 1950s Stainless Steel Weldments

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

— VVER Re-Embrittlement (presentation slides)

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

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

— C.S.N.I. specialist meeting on instrumented precracked charpy testing ; Palo Alto, California December 1-3, 1980

White, C.J.; Charpentier, P.L.; Franklin, D.G.; Kammenzind, B.F.; Kreyns, P.H..; Bourgeois, W.F.; Bettis Atomic Power Laboratory.; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information — Lifetime embrittlement of reactor core materials

Farrell, K — Radiation effects in the stainless steel primary coolant supply adapter

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

ASME — ASME PCC-2S-2015 Supplement to ASME PCC-2-2015 Repair of Pressure Equipment and Piping

W. R. Tyson and B. Mukherjee (Eds.) — Proceedings of the Metallurgical Society of the Canadian Institute of Mining and Metallurgy. Proceedings of the International Symposium on Fracture Mechanics, Winnipeg, Canada, August 23–26, 1987

R.J.M. Konings (editor) — Comprehensive Nuclear Materials, Volume 4: Radiation Effects in Structural and Functional Materials for Fission and Fusion Reactors

G. Robert Odette， Steve Zinkle — Structural Alloys for Nuclear Energy Applications

H. Liebowitz (Eds.) — Fracture of Metals. An Advanced Treatise

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

Jaroslav Koutský and Jan Kočik (Eds.) — Radiation Damage of Structural Materials

Davis, Joyce S.; Harries, D. R — Irradiation embrittlement and creep in fuel cladding and core compounds : proceedings of the Conference organized by the British Nuclear Energy Society in London, 9-10 November 1972

คำที่ถูกค้นหาบ่อยที่สุด