Published 1974 | Version v1
Book Metadata-only

Analysis of the statistical error in a heat conduction code calculation

Creators

  • 1. Aerojet Nuclear Co., Idaho Falls, Idaho

Description

The statistical errors in the calculations of a heat conduction program resulting from uncertainties in input variables were evaluated for a pressurized water reactor fuel rod overpower situation. The computed average fuel temperature was 1980 +- 2300K, and the computed cladding surface temperature was 616 +- 40K. (U.S.)

Additional details

Additional titles

Augmented title (English)
Using Heat-1 computer code

Publishing Information

Publisher
Scripta Book Co.
Imprint Place
Washington, DC
Imprint Title
Heat transfer, 1974. Vol. 1
Imprint Pagination
p. 171-173.

Conference

Title
5. international heat transfer conference.
Dates
3 Sep 1974.
Place
Tokyo, Japan.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7220587
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTER CODES; ERRORS; FUEL CANS; FUEL RODS; H CODES; PWR TYPE REACTORS; SPATIAL DISTRIBUTION; STATISTICS
Descriptors DEC
DISTRIBUTION; FUEL ELEMENTS; MATHEMATICS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:See CONF-740925--P1.