Published 1985 | Version v1
Book

Design variants for improving the thermal hydraulic performance of AGR fuel

  • 1. UKAEA Windscale Nuclear Power Development Labs.
  • 2. Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.

Description

Several design variants for improving the thermal-hydraulic performance of the CAGR fuel element are considered. They include reducing parasitic pressure losses by streamlining support features and pin ends, alternative roughness forms, differential roughening, differential bore diameter and different numbers of pins in the element. (author)

Additional details

Publishing Information

Publisher
British Nuclear Energy Society.
Imprint Place
London (UK)
ISBN
0 7277 0231 9
Imprint Title
Nuclear fuel performance. 2 v.
Imprint Pagination
547 p.
Journal Page Range
v. 2 p. 35-40.

Conference

Title
Nuclear fuel performance conference.
Dates
25-29 Mar 1985.
Place
Stratford-upon-Avon (UK).

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
17059962
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGR TYPE REACTORS; FUEL ELEMENTS; HYDRAULICS; OPTIMIZATION; SPECIFICATIONS; THERMODYNAMICS
Descriptors DEC
ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR COMPONENTS; REACTORS