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

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:552469
 [1]; ;  [2]
  1. Bhabha Atomic Research Centre, Bombay (India)
  2. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

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.

OSTI ID:
552469
Report Number(s):
CONF-971125--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN TANSAO; ISSN 0003-018X
Country of Publication:
United States
Language:
English

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