Published 1997 | Version v1
Journal article Metadata-only

Optimum fuel rod dimensions

Creators

  • 1. ABB Combustion Engineering Nuclear Power, Inc., Windsor, CT (United States)

Description

ABB Combustion Engineering (ABB CE) evaluated two fuel rod designs with different moderator-to-fuel ratios: (1) a standard ABB CE rod for 16 X 16 fuel with high uranium loading: value-added pellets, and (2) a thinner rod with reduced clad surface area, clad thickness, and uranium loading: here called the 16 X 16 OFA (optimized fuel assembly). It is well known that all pressurized water reactors are under-moderated; this ensures a negative moderator temperature coefficient (MTC). Increasing the lattice moderation is thus expected to improve uranium utilization while having a detrimental effect on MTC. This study was performed to quantify the uranium utilization benefit and other effects of increased moderation

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
77
Journal Page Range
p. 386-387.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
1997 American Nuclear Society (ANS) winter meeting.
Dates
16-20 Nov 1997.
Place
Albuquerque, NM (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
29021110
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; FUEL RODS; PWR TYPE REACTORS; REACTOR CORES; SURFACE AREA; TEMPERATURE COEFFICIENT; THICKNESS
Descriptors DEC
DIMENSIONS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-971125--.