Published September 2007 | Version v1
Journal article Metadata-only

Programs for control of reactor vessel pressure: new achievements

Creators

Description

Paper dwells upon the integrity ensuring conditions for the NPP primary circuit components. One simulated the reactor pressure vessel parameters when cold water was supplied. One considered the concepts to ensure integrity of the reactor pressure vessel covering prototype testing during reactor operation

Abstract (Russian)

Приведены условия целостности компонентов первого контура АЭС. Смоделированы свойства корпуса давления реактора (КДР) в случае подачи холодной воды. Рассмотрены конценпции обеспечения целостности КДР, включающие испытания пробных образцов во время эксплуатации реактора

Additional details

Additional titles

Original title (Russian)
Программы контроля корпуса давления реактора: новые достижения

Publishing Information

Journal Title
Atomnaya Tekhnika za Rubezhom
Journal Issue
no.9
Journal Page Range
p. 14-20
ISSN
0320-9326
CODEN
ATRUA8

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
39094964
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Translation
Descriptors DEI
DAMAGING NEUTRON FLUENCE; MICROSTRUCTURE; PRESSURE CONTROL; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENT SIMULATION; REACTOR OPERATION; REACTOR SAFETY; RELIABILITY; THERMAL SHOCK
Descriptors DEC
CONTAINERS; CONTROL; COOLING SYSTEMS; ENERGY SYSTEMS; NEUTRON FLUENCE; OPERATION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; SAFETY; SIMULATION

Optional Information

Notes
Translated from German: atw 52. Jg. (2007) Heft 1 (Januar), s. 29-36; 13 figs.