Published 1975 | Version v1
Report Restricted

Thermal-hydraulic analysis of the first semiscale Mod-1 test series

Creators

Description

The predicted behavior of the semiscale Mod-1 system obtained through use of the RELAP4 computer program is compared with the experimentally observed response. Isothermal Test S-01-4A, chosen here as representative of the first test series, included a cold leg break configuration. The first test series was conducted under isothermal conditions. The electrically heated rods were replaced with a core simulator

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Augmented title (English)
PWR

Publishing Information

Imprint Pagination
17 p.
Report number
CONF-750607--35

Conference

Title
American Nuclear Society meeting.
Dates
8 Jun 1975.
Place
New Orleans, Louisiana, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7237129
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FLOW RATE; HEAT TRANSFER; HYDRAULICS; LIQUID FLOW; LOSS OF COOLANT; MATHEMATICAL MODELS; PRESSURE GRADIENTS; PRIMARY COOLANT CIRCUITS; PUMPS; PWR TYPE REACTORS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENERGY TRANSFER; FLUID FLOW; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS