Published May 2016 | Version v1
Miscellaneous

Analysis of small break loss of coolant accident for Chinese CPR1000

  • 1. FNC Technology Co., Yongin (Korea, Republic of)
  • 2. North-West University, Mahikeng (South Africa)
  • 3. Micro-Simulation Technology, Montville (United States)

Description

This research analyses the small break loss of coolant accident (LOCA) on a Chinese CPR1000 type reactor. LOCA accident is used as benchmark for the PCTRAN/CPR1000 code by comparing the effects and results to the Manshaan FSAR accident analysis. LOCA is a design basis accident in which a guillotine break is postulated to occur in one of the cold legs of a pressurized water reactor (PWR). Consequently, the primary system pressure would drop and almost all the reactor coolant would be discharged into the reactor containment. The drop in pressure would activate the reactor protection system and the reactor would trip. The simulation of a 3-inch small break loss of coolant accident using the PCTRAN/CPR1000 has revealed this code's effectiveness as well as weaknesses in specific simulation applications. The code has the ability to run at 16 times real time and produce very accurate results. The results are consistently producing the same trends as licensed codes used in Safety Assessment Reports. It is however able to produce these results in a fraction of the time and also provides a whole plant simulation coupling the various thermal, hydraulic, chemical and neutronic systems together with a plant specific control system

Part of:
Proceedings of the KNS 2016 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2016 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2016 spring meeting of the KNS
Dates
11-13 May 2016
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
48048898
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; CONTAINMENT; CONTROL SYSTEMS; DESIGN; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; SAFETY ANALYSIS; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 4 figs