Published 2019 | Version v1
Miscellaneous

Accident analysis of supercritical water reactor in startup

  • 1. Sun Yat-sen University, Sino-French Institute of Nuclear Engineering and Technology, Zhubai (China)
  • 2. Xi'an Jiaotong University, School of Nuclear Science and Technology, Xi'an (China)

Description

To analyze the typical accident characteristics during the startup of a supercritical water reactor(SCWR), the entire system model of the CSR1000 was established with the analysis code SCTRAN, based on models of the high performance light water reactor (HPLWR) steam cycle, SCWR circulation startup loop and passive safety systems. According to the sequence of the accident without a safety system and the trigger signal of the accident safety system under the rated condition, the new trigger signal during the startup is designed. "Loss of coolant flow accident (LOFA)", "loss of coolant accident (LOCA)" and "uncontrolled CR withdrawal accident" under startup procedure were calculated with the new trigger signal. The calculation results show that: the new trigger signal can ensure the effective and timely response of the safety system and ensure the safety of the reactor during the startup process. The cladding surface temperature of the reactor reaches the maximum value at the end of the fourth stage of startup procedure with LOCA. The temperature value is 850 ℃, which stays below the safety criterion with a large margin. (author)

Part of:
ISSCWR-9. The 9th International Symposium on Supercritical-Water-Cooled Reactors

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
Imprint Title
ISSCWR-9. The 9th International Symposium on Supercritical-Water-Cooled Reactors
Imprint Pagination
[62 Mb]
Journal Page Range
[9 p.]

Conference

Title
9. International Symposium on Supercritical-Water-Cooled Reactors
Dates
10-14 Mar 2019
Place
Vancouver, British Columbia (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
52015761
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ENGINEERED SAFETY SYSTEMS; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR START-UP; SUPERCRITICAL STATE; TURBULENT FLOW; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; FLUID FLOW; REACTOR LIFE CYCLE; REACTORS; SAFETY; START-UP

Optional Information

Notes
11 refs., 5 tabs., 6 figs.