Published March 2000 | Version v1
Report Open

Improvement of auditing technology of safety analysis through thermal-hydraulic separate effect tests

  • 1. Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

Description

The direct-contact condensation hear transfer coefficients are experimentally obtained in the following conditions : pure steam/steam in the presence of noncondensible gas, horizontal/slightly inclined pipe, cocurrent/countercurrent stratified flow with water. The empirical correlation for liquid Nusselt number is developed in conditions of the slightly inclined pipe and the cocurrent stratified flow. The several models - the wall friction coefficient, the interfacial friction coefficient, the correlation of direct-contact condensation with noncondensible gases, and the correlation of wall film condensation - in the RELAP5/MOD3.2 code are modified, As results, RELAP5/MOD3.2 is improved. The present experimental data is used for evaluating the improved code. The standard RELAP5/MOD3.2 code is modified using the non-iterative modeling, which is a mechanistic model and does not require any interfacial information such as the interfacial temperature, The modified RELAP5/MOD3.2 code os used to simulate the horizontally stratified in-tube condensation experiment which represents the direct-contact condensation phenomena in a hot leg of a nuclear reactor. The modeling capabilities of the modified code as well as the standard code are assessed using several hot-leg condensation experiments. The modified code gives better prediction over local experimental data of liquid void fraction and interfacial heat transfer coefficient than the standard code. For the separate effect test of the thermal-hydraulic phenomena in the pressurizer, the scaling analysis is performed to obtain a similarity of the phenomena between the Korea Standard Nuclear Power Plant(KSNPP) and the present experimental facility. The diameters and lengths of the hot-leg, the surge line and the pressurizer are scaled down with the similitude of CCFL and velocity. The ratio of gas flow rate is 1/25. The experimental facility is composed of the air-water supply tank, the horizontal pipe, the surge line and the pressurizer, and it simulates the related phenomena of the off-take at the inlet of surge line, the CCFL in the surge line and the inlet of pressurizer, and the mixture and collapsed levels in pressurizer

Availability note (English)

Available from INIS in electronic form; Also available from KINS

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Additional details

Publishing Information

Imprint Pagination
197 p.
Report number
KINS/HR--292

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38059466
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
COMPUTER CODES; EXPERIMENTAL DATA; HEAT TRANSFER; PRESSURIZERS; SAFETY ANALYSIS; SCALING; THERMAL HYDRAULICS
Descriptors DEC
DATA; ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; INFORMATION; MECHANICS; NUMERICAL DATA

Optional Information

Notes
42 refs, 53 figs, 12 tabs