Published July 1988 | Version v1
Report Restricted

The development of APRIL.MOD2: A computer code for core meltdown accident analysis of boiling water nuclear reactors

Creators

Description

This report summarizes the thermal-hydraulic models used in APRIL. MOD2. This digital computer code was developed at Rensselaer Polytechnic Institute Corporation (ESEERCO) and the Boiling Water Reactor Severe Accident Technology Program at Oak Ridge National Laboratory (ORNL). The APRIL.MOD2 code can be used for the mechanistic analysis of severe accident phenomena in Boiling Water Nuclear Reactors (BWRs) having either Mark-I or Mark-II containment systems

Availability note (English)

MF available from INIS under the Report Number; NTIS, PC A13/MF A01 - US Govt. Printing Office; 1 as TI88012914.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
279 p.
Report number
NUREG/CR--5157

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20016418
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
A CODES; BWR TYPE REACTORS; CONCRETES; CONTAINMENT; CORIUM; FUEL CANS; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; HYDROGEN; MATHEMATICAL MODELS; MELTDOWN; NUMERICAL SOLUTION; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; BUILDING MATERIALS; COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MATERIALS; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Portions of this document are illegible in microfiche products.
Secondary number(s)
ORNL/Sub--81-9089/3.