Published 1997 | Version v1
Journal article Metadata-only

Method of calculating the effect of heterogeneous fuel composition on a fuel bundle power ramp

Creators

  • 1. Bhabha Atomic Research Centre, Bombay (India)
  • 2. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

Spent pressurized water reactor (PWR) fuel is directly reused in the Canada deuterium uranium (CANDU) reactor. The direct use of spent fuel in the DUPIC fuel cycle can be difficult because the spent PWR fuel composition depends on the enrichment and burnup history, so the DUPIC fuel composition will change accordingly. To reduce the composition heterogeneity effect on core performance, the DUPIC fuel was designed such that the neutronic properties of each DUPIC fuel bundle grow closer to each other by adjusting the fuel composition. Nonetheless, it is not possible to have a unique fuel composition for all the DUPIC fuel. To predict bundle power change due to fuel composition heterogeneity, a formulation was developed using the lattice parameters only

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
77
Journal Page Range
p. 200-202.
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
29020995
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; CANDU TYPE REACTORS; FUEL CYCLE; FUEL ELEMENT CLUSTERS; HETEROGENEOUS EFFECTS; LATTICE PARAMETERS; PERFORMANCE; PWR TYPE REACTORS; R CODES; REACTOR CORES; SPENT FUEL ELEMENTS
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-971125--.