Published January 1977 | Version v1
Report Restricted

Reflood heat transfer, THERM: a thermal-hydraulic emergency reflood model

Creators

Description

THERM models a reactor fuel rod during the reflood phase of the loss-of-coolant-accident (LOCA) analysis. The purpose of its development is twofold: to formulate a physically founded reflood heat transfer correlation and to identify important parameters governing the reflood process, a process that now limits the operation of many nuclear plants. THERM performs a one-dimensional, closed-channel, transient temperature analysis of a single fuel rod being cooled through bottom flooding. The code couples the fuel rod energy equations with the coolant channel mass and energy balances. The coolant inlet velocity is specified as a time dependent boundary condition

Availability note (English)

MF available from INIS under the Report Number; Combustion Engineering, Inc., Windsor, CT.

Files

Restricted

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

Additional details

Additional titles

Augmented title (English)
PWR and BWR

Publishing Information

Imprint Pagination
v p.
Report number
CENPD--228

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8334993
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CODES; FUEL RODS; HEAT TRANSFER; HYDRAULICS; LIQUID FLOW; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION; T CODES
Descriptors DEC
ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; FLUID FLOW; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS