Published July 1980 | Version v1
Report Restricted

LOCA simulation in NRU-heatup instrumentation package

Creators

Description

The LOCA simulation program will develop a well-characterized data set for evaluating the consequences of a hypothetical LOCA in an LWR. Heatup, reflood, and quench will be simulated using low-level fission heat as a surrogate for the system enthalpy and decay heat that would drive the hypothetical LOCA terminal transient. To achieve these objectives, six full-length test assemblies will be irradiated. The geometric configuration of each assembly represents a 6 by 6 segment of a 17 by 17 pressurized water reactor (PWR) fuel bundle

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82007088.

Files

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The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
PWR

Publishing Information

Imprint Pagination
18 p.
Report number
PNL-SA--8742

Conference

Title
Review group conference on advanced instrumentation for reactor safety research.
Dates
29 - 31 Jul 1980.
Place
Oak Ridge, TN, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
13689228
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFORMATION; FUEL ASSEMBLIES; FUEL CANS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MOCKUP; PWR TYPE REACTORS; REACTOR SAFETY; THERMOCOUPLES; URANIUM DIOXIDE
Descriptors DEC
ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY TRANSFER; MEASURING INSTRUMENTS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRUCTURAL MODELS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-800747--8.