Published July 1996 | Version v1
Report Open

The analysis of thermal-hydraulic models in MELCOR code

Creators

  • 1. POhang Univ., of Science and TECHnology, Pohang (Korea, Republic of)

Description

The objective of the present work is to verify the prediction and analysis capability of MELCOR code about the progression of severe accidents in light water reactor and also to evaluate appropriateness of thermal-hydraulic models used in MELCOR code. Comparing the results of experiment and calculation with MELCOR code is carried out to achieve the above objective. Specially, the comparison between the CORA-13 experiment and the MELCOR code calculation was performed

Availability note (English)

Available from INIS in electronic form; Also available from KINS

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Additional details

Publishing Information

Imprint Pagination
284 p.
Report number
KINS/HR--153

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37079125
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ACCIDENTS; COMPUTER CALCULATIONS; FORECASTING; INTERSTITIAL HYDROGEN GENERATION; M CODES; PWR TYPE REACTORS; SENSITIVITY; SIMULATION; THERMAL HYDRAULICS
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; PHYSICAL RADIATION EFFECTS; POWER REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
20 refs, 192 figs, 6 tabs