BWR Full Integral Simulation Test (FIST). Phase I test results

Technical Report · Sat Sep 01 00:00:00 EDT 1984

DOI:https://doi.org/10.2172/6370409· OSTI ID:6370409

Hwang, W S; Alamgir, M; Sutherland, W A

A new full height BWR system simulator has been built under the Full-Integral-Simulation-Test (FIST) program to investigate the system responses to various transients. The test program consists of two test phases. This report provides a summary, discussions, highlights and conclusions of the FIST Phase I tests. Eight matrix tests were conducted in the FIST Phase I. These tests have investigated the large break, small break and steamline break LOCA's, as well as natural circulation and power transients. Results and governing phenomena of each test have been evaluated and discussed in detail in this report. One of the FIST program objectives is to assess the TRAC code by comparisons with test data. Two pretest predictions made with TRACB02 are presented and compared with test data in this report.

• Research Organization: General Electric Co., San Jose, CA (USA). Nuclear Fuel and Special Projects Div.
• OSTI ID: 6370409
• Report Number(s): NUREG/CR-3711; EPRI-NP-3602; GEAP-30496; ON: TI85900059
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
TEST FACILITIES
HEAT TRANSFER
HYDRAULICS
COMPUTER CALCULATIONS
EXPERIMENTAL DATA
FLOW RATE
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
VOID FRACTION
ACCIDENTS
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
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210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled