Thermo-Hydraulic Codes for VVER LOCA and Transients...

Main
Thermo-Hydraulic Codes for VVER LOCA...

Thermo-Hydraulic Codes for VVER LOCA and Transients (csni-r2001-4)

0 / 0

Наскільки Вам сподобалась ця книга?

Яка якість завантаженого файлу?

Скачайте книгу, щоб оцінити її якість

Яка якість скачаних файлів?

Рік:

2001

Мова:

english

Сторінки:

249

Файл:

PDF, 1.34 MB

IPFS:

,

english, 2001

Читати Онлайн

Завантажити (pdf, 1.34 MB)

Виконується конвертація в

Конвертація в не вдалась

Можливо вас зацікавить

Bengt Pershagen — Light Water Reactor Safety

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

IAEA — Directory of Nuclear Reactors, Volume 1. Power Reactors

IAEA — Directory of Nuclear Reactors, Vol. 4. Power Reactors (Revised and Supplemented Edition of Vol. 1)

IAEA — Directory of Nuclear Reactors, Vol. 7. Power Reactors (Supplement to Vol. 4)

IAEA — Directory of Nuclear Reactors, Vol. 9. Power Reactors (Supplement to Vol. 4 and 7)

— Progress in Safety Systems for Advanced Water-Cooled Reactors (IAEA TECDOC-872)

— Specialists Meeting on Boron Dilution Reactivity Transients

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

— Accid. Anal. - Nucl. Powerplants w. Graphite-Moderated BW RBMK Reactors

— Accid. Anal. - Nuclear Powerplants with PWRs

— Behavior of Water Reactor Fuel Elements Under Accident Conditions (csni77-13)

— Cold-leg Break Experiment Vol 1 (csni-r1992-20-VOL1)

— Design, Devel Status of Small and Medium Reactor Systems (IAEA TECDOC-881)

— Feasibility Study - Supercritical LWRs for Electrical Power Prodn

— In-Vessel Core Degradation [validation martrix] (csni-r2000-21)

— NPR Reactor Hazards Review (detailed) Phase I [Declassified]

— NPR Reactor Hazards Review Vol 1 (phase 1 - production) [declassified]

— Proceedings of Topical Meeting on RIA Vol 2 (csni-r2003-8-vol2)

— PWR Program Progress Rpt [Dec 2 1955 - Jan 12 1956] [declassified]

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

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

— Steam Generator Tube Rupture (csni88-154)

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

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

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

— Water Reactor Safety Info Meeting Vol 2 [22nd, transactions]

R C Berkan; B R Upadhyaya; R A Kisner; United States. Office of Technology Support Programs.; Oak Ridge National Laboratory. Instrumentation and Controls Division.; All authors — Low-order dynamic modeling of the experimental breeder reactor II

Paul D Bayless; Idaho National Engineering Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; et al — Severe accident natural circulation studies at the INEL

Max Weber; U.S. Atomic Energy Commission. Division of Reactor Development and Technology — Status of LMFBR reheat in Western Europe, 1972 : report of the United States of America LMFBR Sodium Reheat Team visit to France, Germany (FRG), Netherlands, and United Kingdom, May 22-June 6, 1972

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

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

OECD Nuclear Energy Agency — International standard problem isp36 : cora-w2 experiment on severe fuel damage for a russian type pwr

中国核能动力学会反应堆热工流体专业委员会空泡物理和自然循环国家级重点实验室 — 核反应堆热工词典

— Natural Circulation Phenomena, Modeling and Reliability of Passive Systems That Utilize Natural Circulation

Ключові фрази