PWG4 perspective on ex-vessel hydrogen sources

Main
PWG4 perspective on ex-vessel hydrogen...

PWG4 perspective on ex-vessel hydrogen sources

Nuclear Energy Agency. Committee on the Safety of Nuclear Installations

0 / 0

Sukakah Anda buku ini?

Bagaimana kualitas file yang diunduh?

Unduh buku untuk menilai kualitasnya

Bagaimana kualitas file yang diunduh?

Tahun:

2000

Penerbit:

OECD Nuclear Energy Agency

Bahasa:

english

Halaman:

11

Nama seri:

NEA/CSNI/R, (2000)19

File:

PDF, 34 KB

IPFS:

,

english, 2000

Mengunduh (pdf, 34 KB)

Pengubahan menjadi sedang diproses

Pengubahan menjadi gagal

Mungkin Anda tertarik

Committee on Application of Digital Instrumentation and Control Systems to Nuclear Power Plant Operations and Safety, National Research Council — Digital Instrumentation and Control Systems in Nuclear Power Plants: Safety and Reliability Issues

J.N. Lillington — Light Water Reactor Safety: The Development of Advanced Models and Codes for Light Water Reactor Safety Analysis

Gianni Petrangeli — Nuclear Safety

— Evolutionary Water-Cooled Reactors - Issues, Technologies (IAEA TECDOC-1117)

— Development, Design Aspects of Advanced Water Cooled Reactors (IAEA TECDOC-677)

— Advanced Containment Systems for Next-Gen Water Reactors (IAEA TECDOC-752)

— CO-H Combustion Chars in Severe Accident Cond (csni-r2000-10)

— Control of Release of Fission Products by Severe Accident (csni-r2000-9)

— Design of Reactor Containment Systems for Nuclear Powerplants (IAEA NS-G-1.10)

— Direct Containment Heating (csni89-153)

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

— Instrumentation to Manage Severe Accidents (csni-r1992-11)

— Iodine Chemistry in Reactor Safety [workshop] (csni-r91-15)

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

— Mitigation of Hydrogen Hazards in Water-Cooled Power Reactors (IAEA TECDOC-1196)

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

— Operator Aids for Severe Accidents - Mgt, Tng (csni-r1993-9)

— Pressure Suppression System Containments (csni86-126)

— Reactor Coolant System Leakage and Failure Probabilities (csni-r1995-6)

— Selected Containment Severe Accident Mgmt Strategies (csni-r1994-33)

— Status of Adv. Light-Water Nuclear Reactor Designs (IAEA TECDOC-1391)

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

— Steam Explosions and Reactor Safety (csni82-74)

— Tech Feas, Reliability of Passive Safety Systems for Nucl Powerplants (IAEA TECDOC-920)

— Use of Water to Cool a Molten Core in the Containment (csni-r1994-34)

— VVER-Specific Features [core degradation] (csni-r98-20)

— Water Reactor Safety Info Meeting Vol 2 [20th, Transactions]

— Water Reactor Safety Info Meeting [21st, transactions]

International Atomic Energy Agency.; Argonne National Laboratory — Safety of nuclear installations : future direction

T J Haste; K Trambauer; OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — Degraded core quench : summary of progress, 1996-1999 : executive summary

J C Cleveland; J C Conklin; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Oak Ridge National Laboratory — High temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research quarterly progress report, April 1-June 30, 1979

Fauske & Associates, Sandia National Laboratories — High-Pressure Melt Ejection (HPME) and Direct Containment Heating (DCH)

Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — In-vessel core debris retention and coolability : summary and conclusions : OECD/CSNI workshop, 3-6 March 1998, Garching near Munich, Germany

Nuclear Energy Agency Committee on the Safety of Nuclear Installations — In-vessel core degradation code validation matrix

OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations.; OECD Nuclear Energy Agency. Steering Committee for Nuclear Energy — Second OECD Specialist Meeting on Operator Aids for Severe Accident Management : (SAMOA-2) : Lyon, France, September 8-10, 1997

International Atomic Energy Agency — Design measures for prevention & mitigation of severe accidents at advanced water cooled reactors : proceedings of a technical committee meeting hedl in vienna, 21-25 october 1996

Istilah kunci