Published March 2005
| Version v1
Journal article
Studying the natural circulation and determining the heat removal in the APWR+ reactor steam generator
Creators
Description
Natural circulation in the APWR+ reactor steam generator is studied, the results are presented. The process of the flow siphon braking was considered
Abstract (Russian)
Приведены результаты изучения естественной циркуляции в парогенераторе реактора APWR+. Исследован процесс образования сифонного торможения потокаAdditional details
Additional titles
- Original title (Russian)
- Изучение естественной циркуляции и определение характеристик теплоотвода в парогенераторе реактора APWR+
Publishing Information
- Journal Title
- Atomnaya Tekhnika za Rubezhom
- Journal Issue
- no.3
- Journal Page Range
- p. 24-26
- ISSN
- 0320-9326
- CODEN
- ATRUA8
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 38011291
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Translation
- Descriptors DEI
- CIRCULATING SYSTEMS; FLOW RATE; FLOWSHEETS; HEAT FLUX; LOSS OF COOLANT; NATURAL CONVECTION; STEAM GENERATORS; TEST FACILITIES; TWO-PHASE FLOW; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BOILERS; CONVECTION; DIAGRAMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; INFORMATION; MASS TRANSFER; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Translated from Japanese: Denki hyoron, 2004, v. 89, No. 1, p. 161-163; 5 figs., 1 tab.