Published 2003 | Version v1
Miscellaneous

REATRAN sensitivity calculations for anticipated transient without scram

  • 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)

Description

Best estimate analyses were performed for a loss of feedwater transient without scram and turbine trip without scram on Kori unit 1 using RETRAN-3D/MOD3.1 computer code. The results showed that the peak pressure for loss of feedwater ATWS and turbine trip ATWS with AMSAC did not exceed the ASME Code Level C limit criterion (3200psig) when MTC was less than -7pcm/F. For the ATWS analysis, particular effort was given to the effects of varying the nodalization of steam generator secondary side and maximum time step size on primary side pressure response. The sensitivity of primary pressure response to moderator reactivity feedback coefficients, turbine trip time, auxiliary feedwater supply time, pressurizer relief capacity, auxiliary feedwater supply capacity, and steam generator level setpoint for AMSAC actuation was also studied

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2003 spring meeting of the KNS
Dates
29-30 May 2003
Place
Gyeongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
35063908
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ATWS; COMPUTER CALCULATIONS; FEEDWATER; KORI-1 REACTOR; R CODES; SCRAM; SENSITIVITY ANALYSIS; TRANSIENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DESIGN BASIS ACCIDENTS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
12 refs, 22 figs, 1 tab