Investigation on the start-up features of secondary-side passive residual heat removal system
- 1. Science and Technology on Thermal Energy and Power Laboratory, Wuhan Second Ship Design and Research Institute, Wuhan (China)
Description
In order to study the start-up characteristics of passive residual heat removal (PRHR) system, a numerical model is established to calculate the transient characteristics of secondary-side PRHR system under station blackout (SBO) accident. The results show that two-phase flow oscillation occurs during the establishment of natural circulation. This is caused by the mismatch between the variation of reactor residual heat power and the PRHR system operation power. In this paper, a thermal energy storage device is introduced to remove the high residual heat power of the reactor at the initial stage of shutdown. The latent thermal storage device using phase change materials (PCMs) as heat storage medium has the advantage of high potential heat storage density and almost constant phase change temperature. This new configuration can eliminate the flow oscillation phenomenon and reduce the maximum pressure of the steam generator. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 27th international conference on nuclear engineering (ICONE-27)
- Imprint Pagination
- [4028 p.]
- Journal Page Range
- 5 p.
Conference
- Title
- 27. international conference on nuclear engineering
- Acronym
- ICONE-27
- Dates
- 19-24 May 2019
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51012954
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- HEAT EXCHANGERS; HEAT SINKS; HEAT SOURCES; NATURAL CONVECTION; OFFSHORE NUCLEAR POWER PLANTS; PHASE CHANGE MATERIALS; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; RHR SYSTEMS; STATION BLACKOUT; THERMAL ENERGY STORAGE EQUIPMENT; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; CONVECTION; COOLING SYSTEMS; ENERGY STORAGE SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; MATERIALS; NUCLEAR FACILITIES; NUCLEAR POWER PLANTS; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SINKS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as Internet Data in PDF format, Folder Name: Track08, Paper ID: ICONE27-1808F.pdf; 9 refs., 8 figs., 1 tab.