Published 2005 | Version v1
Journal article Metadata-only

Physical statutes of reactor VVER-1000 analyze and management of emergency situations

Creators

  • 1. Kontsern Rosehnergoatom, Moscow (Russian Federation)
  • 2. Obninskij Gosudarstvennyj Tekhnicheskij Univ. Atomnoj Ehnergetiki, Obninsk (Russian Federation)

Description

Physical categories of nuclear power installation (NPI) determined by physical process which pass in elements of its equipment are suggested and founded. It is shown that combination of physical categories determines physical conditions of NPI. A technique for analysis of physical categories for determination of physical conditions of NPI is given. Analysis of different physical conditions of NPI is conducted, a technique of decision acceptance by operator on control of emergency situation ( in support of safety system) with the purpose of consistent conversion to the final (safety) condition is developed

Abstract (Russian)

Предложены и обоснованы понятия физических категорий ядерной энергетической установки (ЯЭУ), определяемые физическими процессами, протекающими в элементах ее оборудования. Показано, что сочетание физических категорий определяет физическое состояние ЯЭУ. Приведена методика анализа физических категорий для определения физических состояний ЯЭУ. Проведен анализ различных физических состояний ЯЭУ, разработана методика принятия решений оператором по управлению аварийной ситуацией (в поддержку систем безопасности) с целью последовательного перевода ее в конечное (безопасное) состояние

Additional details

Additional titles

Original title (Russian)
Анализ физических состояний реактора VVEhR-1000 и управление аварийными ситуациями

Publishing Information

Journal Title
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Journal Issue
no.3
Journal Page Range
p. 60-68
ISSN
0204-3327

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
38011341
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CONTROL; DECISION MAKING; FLOWSHEETS; HEAT TRANSFER; MASS TRANSFER; NOVOVORONEZH-5 REACTOR; NUCLEAR POWER PLANTS; PARAMETRIC ANALYSIS; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR OPERATORS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; CONTAINERS; COOLING SYSTEMS; DIAGRAMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; NUCLEAR FACILITIES; PERSONNEL; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information

Notes
8 refs., 4 figs.