Published July 21, 1993 | Version v1
Miscellaneous

NEPTUN/5007, PWR LOCA Cooling Heat Transfer Tests for Loft, Boil-Off Experiments

Description

1 - Description of test facility: NEPTUN is designed to perform PWR LOCA simulation experiments, which provide the full length emergency cooling heat transfer tests for LOFT. Therefore the NEPTUN heater bundle with 33 electrical heater elements and 4 guide tubes simulates a section of the LOFT nuclear core. The main test loop also contains measuring systems for the carry-over rate and for the steam expelled, and a back-pressure control system. A water loop brings the water to the initial reflooding conditions. In addition, auxiliary systems maintain normal operating conditions. 2 - Description of test: Test 5007 was one of ten core boil-off experiments. It was chosen as the 'base case', because it was conducted at high pressure and intermediate power. The power is increased at about 50 secs and a rapid drop in the core fluid level occurs at about 100 secs. Between 100 and 110 secs, large voids are formed expelling some of the liquid from the core. At about 800 secs the power is shut off and the rods are allowed to cool down before the system is re-flooded. 3 - Status: CSNI1011/01, 21-Jul-1993 Arrived at NEADB

Availability note (English)

Available on-line: http://www.nea.fr/abs/html/csni1011.html

Additional details

Publishing Information

Imprint Pagination
[html]

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43123765
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
AUXILIARY SYSTEMS; COMPUTERIZED SIMULATION; CORING FLUIDS; GUIDE TUBES; HEAT TRANSFER; HEATERS; LOSS OF COOLANT; MEASURING METHODS; NUCLEAR CORES; PRESSURE CONTROL; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; RODS; TEST FACILITIES; WEBSITES
Descriptors DEC
ACCIDENTS; CONTROL; DOCUMENT TYPES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs.; This record replaces 40013907