Published 1977 | Version v1
Book

Comparison of the HOTROD Code predictions with PIE data

Creators

  • 1. Br Nucl Fuels Ltd, Preston, Lancashire, Engl

Description

The HOTROD Code is a design oriented fuel rod modeling code, the 4B version of which is used to survey the lifetime performance of rod type oxide fuels and enable the designer to select the fuel design which best meets the operational requirements. A comparison of the code predictions with data obtained from various fuel irradiations shows reasonable agreement, and thereby confirms its acceptability for this use

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
Chicago, IL
Imprint Title
Water reactor fuel performance, ans topical meeting, 1977
Journal Page Range
p. 159-168.

Conference

Title
ANS topical meeting on water reactor fuel performance.
Dates
9 - 11 May 1981.
Place
St Charles, IL, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12642135
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; FISSION PRODUCT RELEASE; FUEL RODS; H CODES; PERFORMANCE; POROSITY; SPATIAL DISTRIBUTION; STRAINS
Descriptors DEC
DISTRIBUTION; FUEL ELEMENTS; REACTOR COMPONENTS