Published May 2000 | Version v1
Miscellaneous

Simulation of late phase of the TMI-2 accident in SCDAP/RELAP5/MOD3.2

  • 1. Hanyang Univ., Seoul (Korea, Republic of)
  • 2. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

Description

TMI-2 accident is more valuable than the related experiments in the point of view that it is a real accident offering huge information about the late phase of severe accident. Therefore it gives out good standards for evaluation of code performance and input's suitableness by comparing the accident data and simulated outputs. In this study SCDAP/RELAP5/MOD3.2 was selected for accident simulation. And sensitivity analysis was performed on varied cases to find out the most proper input variable about the late phase of core melting phenomena. Other plants and experimental facilities' input deck were collected and analyzed for the sensitivity study and the shortcomings proposed by SCDAP/RELAP5 Peer Review were considered to the simulation. As a result gamma heating fraction in the input affect the progress of core melting phenomena. About this a study on the related model itself will be carried out

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
[CDROM]
Journal Page Range
[14 p.]

Conference

Title
2000 spring meeting of the KNS
Dates
26-27 May 2000
Place
Kori (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34027617
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
MELTING; PERFORMANCE; REACTOR ACCIDENTS; S CODES; SENSITIVITY ANALYSIS; SIMULATION; THREE MILE ISLAND-2 REACTOR
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
8 refs, 6 figs, 5 tabs