Reactor coolant system overpressure analysis during low temperature conditions for Qinshan phase II
Description
When reactor primary system is single-phase water solid conditions, system overpressure may be caused by mass input or heat input. The overpressure case caused only by mass input is considered for Qinshan Phase-I, Framatome also only considers the overpressure case caused by heat input for Daya Bay design. But the design for Qinshan Phase-II is referenced to Daya Bay design (RCC-P is both adopted), its safety injection flowrate is greater than that of Daya Bay compared to primary coolant volume respectively, hence the overpressure caused by mass input should be analyzed besides the case caused by heat input. The Reactor Coolant System (RCS) will be protected by the safety valves of Residual Heat Removal system (RHR) under these two kinds of overpressure cases. The pressure of RCS and RHR is required to be less than 110% design pressure of RHR during transient, i.e. 5.11MPa, in order to ensure the RHR being in safety operation. This is the first time to analyze these two typical cases in China. It aims to demonstrate that the volume and set points of RHR safety valves meet the design criterion under overpressure cases during low temperature conditions for Qinshan Phase-II, consequently avoid RHR pressure exceeding the required value, and ensure the system in safety operation. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Imprint Pagination
- 3690 p.
- Journal Page Range
- 5 p.
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Acronym
- NUTHOS-6
- Dates
- 4-8 Oct 2004
- Place
- Nara (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36083944
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DAYA BAY-1 REACTOR; HEATING LOAD; NUCLEAR POWER PLANTS; PRESSURE DEPENDENCE; PRIMARY COOLANT CIRCUITS; PUMPS; R CODES; REACTOR COOLING SYSTEMS; RHR SYSTEMS; TEMPERATURE RANGE 0065-0273 K; TRANSIENTS; VALVES
- Descriptors DEC
- COMPUTER CODES; CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TEMPERATURE RANGE; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name FRIDAY October 8, 2004, Paper ID N6P 170.pdf