BEST ESTIMATE METHODS IN THERMAL HYDRAULIC SAFETY ANALYSIS

Main
BEST ESTIMATE METHODS IN THERMAL...

BEST ESTIMATE METHODS IN THERMAL HYDRAULIC SAFETY ANALYSIS

OECD NEA

0 / 0

এই বইটি আপনার কতটা পছন্দ?

ফাইলের মান কিরকম?

মান নির্ণয়ের জন্য বইটি ডাউনলোড করুন

ডাউনলোড করা ফাইলগুলির মান কিরকম?

ভাষা:

english

পৃষ্ঠা:

35

ফাইল:

PDF, 107 KB

IPFS:

,

english0

অনলাইনে পড়া

তে রূপান্তর প্রক্রিয়া চলছে

-এ রূপান্তর ব্যর্থ হয়েছে

আপনি আগ্রহী হতে পারেন

Dan Gabriel Cacuci — Handbook of Nuclear Engineering: Vol. 1-4

national fire protection association — NFPA 806 : Performance-Based Standard for Fire Protection for Advanced Nuclear Reactor Electric Generating Plants Change Process 2020 Edition

— Specialists Meeting on Boron Dilution Reactivity Transients

— Research Reactor Core Conversion Guidebook Vol 1 [Summary] (IAEA TECDOC-643v1)

— Accid. Anal. for Nuclear Powerplants

— Advanced Instrumentation and Measurement Techniques (csni-r1997-33)

— Advanced Thermal-Hydraulic, Neutronic Codes Vol 1 (csni-r2001-2-vol1)

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

— Boron Reactivity Transients (csni-r1996-03)

— Bubbler-Condenser-Related Research (csni-r2001-3)

— Code Validation Matrix - Thermohydraulic Codes for LWR LOCA (csni87-132)

— Finite Element Analysis - Degraded Concrete Structures (csni-r99-1)

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

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

— Fuel-Coolant Interactions (csni-r1997-26)

— Large Break LOCA [proceedings] Vol 1 (csni-r2003-17-vol1)

— Leak-Before-Break in Nuclear Reactor Piping [specialist meeting] (csni84-82)

— NUPEC Hydrogen Mixing, Distribution Test (csni-r1994-29)

— Operating Experience - Computer-Based I&C Systems Vol 1 (csni-r2002-1-vol1)

— Pressure Suppression System Containments (csni86-126)

— Proceedings of Topical Meeting on RIA Vol 1 (csni-r2003-8-vol1)

— PSA as Aid to Nuclear Powerplant Management (csni86-125)

— Seismic Risk Assessment for Nuclear Powerplants (csni83-76)

— Separate Effects Matrix - Thermal-Hydraulic Effects Code Validation (csni-r1993-14)

— Severe Accident Management Implimentation (csni-r1995-5)

— SOAR Report on Boiling-Water Reactor Stability (csni-r1996-21)

— Status of Degraded Core Issues (csni-r2001-5)

— Status of LMFBR Safety Technology [part 2] (csni81-62)

— Steam Explosions and Reactor Safety (csni82-74)

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

— Thermohydraulics of Emergency Core Cooling in LWRs (csni89-161)

— Training of Nuclear Reactor Personnel (csni87-138)

— Transient Behavior of High-Burnup Fuel (csni-r1996-23)

— Transient Behavior of High-Burnup Fuel (csni-r95-22)

— Transient Thermal-Hydraulics, Neutronic Codes - Reqmts (csni-r1997-04)

প্রায়শই ব্যবহৃত পরিভাষা