Published May 2015 | Version v1
Miscellaneous

An Overall Investigation of Cold Leg Pipe Break Accidents of the ATLAS Facility

  • 1. KAERI, Daejeon (Korea, Republic of)

Description

A previous parametric study of the direct vessel injection (DVI) line breaks was re-evaluated to see their applicability to the cold leg (CL) pipe breaks in ATLAS (Advanced Thermal-hydraulic test Loop for Accident Simulation). Evaluation results of the tests and analyses for the major parameters, i.e., the pressurizer (PZR) pressure, downcomer water level, collapsed core water level, and clad temperature, were compared for four different CL pipe break scenarios. The overall trends of the major parameters showed reasonable behaviors between the tests and analyses. The clad temperature showed conservative behaviors in the analyses using the suggested options. The suggested counter-current flow limit (CCFL) options for the fuel alignment plate (FAP) and cross-over legs (COLs) can be applicable to any small-break loss-of-coolant accident (SBLOCA) scenario for the CL pipe and DVI line breaks in the ATLAS tests. In this paper, a previous parametric study of the DVI line breaks was re-evaluated to see its applicability to that of the CL pipe breaks in ATLAS. The evaluation results of the tests and analyses for the major parameters, i.e., the PZR pressure, downcomer water level, core water level, and clad temperature, were compared for four different CL pipe break scenarios. The overall trends of the major parameters showed reasonable behaviors between the tests and analyses

Part of:
Proceedings of the KNS 2015 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2015 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2015 spring meeting of the KNS
Dates
6-8 May 2015
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47023287
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CLADDING; CURRENT LIMITERS; INJECTION; LOSS OF COOLANT; M CODES; PIPES; PRESSURIZERS; TEST FACILITIES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DEPOSITION; ELECTRICAL EQUIPMENT; EQUIPMENT; INTAKE; REACTOR ACCIDENTS; SURFACE COATING; TUBES

Optional Information

Notes
2 refs, 4 figs, 2 tabs