Published 2011
| Version v1
Book
HEFEST: models of heat transfer with steam and materials moving into mixing lower chamber of WWER type reactor at severe accident
Description
The realization peculiarities of models of melt interaction with reactor internals are considered. Computational region of WWER type reactor bottom and reactor internals is given. The general organization of calculation process of severe accident is described. The questions of interaction of calculating modules with calculating code RATEG describing thermohydraulic processes and SVEChA modulus determining the materials moving velocity are considered
Abstract (Russian)
Рассмотрены особенности реализации моделей взаимодействия расплава с внутрикорпусными устройствами. Приведена расчетная область нижней части корпуса ВВЭР и внутрикорпусных конструкций. Описана общая организация процесса расчета тяжелой аварии. Рассмотрены вопросы взаимодействия расчетных модулей с расчетным кодом РАТЕГ, описывающим теплогидравлические процессы, и модулем СВЕЧА, определяющим скорость перемещения материаловAdditional details
Additional titles
- Original title (Russian)
- HEFEST: модели теплообмена с паром и перемещения материалов в NKS реактора VVEhR при тяжелой аварии
Publishing Information
- Publisher
- Izd-vo Nauka
- Imprint Place
- Moscow (Russian Federation)
- ISBN
- 978-5-02-037971-8
- Imprint Title
- Proceedings of IBRAE RAS. Issue 12: Integral codes development and application for NPP safety analysis
- Imprint Pagination
- 304 p.
- Journal Page Range
- p. 144-180
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 44047766
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- H CODES; HEAT TRANSFER; MATHEMATICAL MODELS; MELTDOWN; NUMERICAL SOLUTION; R CODES; REACTOR ACCIDENT SIMULATION; REACTOR COMPONENTS; S CODES; STEAM; THERMAL DEGRADATION; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MATHEMATICAL SOLUTIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 9 figs. Imprint:Trudy IBRAEh RAN. Vypusk 12. Razrabotka i primenenie integral'nykh kodov dlya analiza bezopasnosti AEhS