A comparative study to investigate burnup in research reactor fuel using two independent experimental methods

Iqbal, Masood; Mehmood, T.; Ayazuddin, S.K.; Salahuddin, A.; Pervez, S.

doi:10.1016/s0306-4549(01)00013-5

Cited by 7 publications

(1 citation statement)

References 2 publications

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“…Cal cu la tions for in-pile as well as out-of-pile param e ters are done by means of a mod i fied ver sion of the Karlsruhe iso tope gen er a tion and de ple tion code, KORIGEN [17]. This com puter code has been used for burn-up, iso to pic con cen tra tion and de cay char acter is tics of spent fuel [18][19][20]. The mod i fi ca tions to the code are de scribed be low.…”

Section: Methods Of Calculationmentioning

confidence: 99%

Comparison of actinides and fission products recycling scheme with the normal plutonium recycling scheme in fast reactors

Salahuddin

Iqbal

2013

NUCL TECH RAD PROT

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Multiple recycling of actinides and non-volatile fission products in fast reactors through the dry re-fabrication/reprocessing atomics international reduction oxidation process has been studied as a possible way to reduce the long-term potential hazard of nuclear waste compared to that resulting from reprocessing in a wet PUREX process. Calculations have been made to compare the actinides and fission products recycling scheme with the normal plutonium recycling scheme in a fast reactor. For this purpose, the Karlsruhe version of isotope generation and depletion code, KORIGEN, has been modified accordingly. An entirely novel fission product yields library for fast reactors has been created which has replaced the old KORIGEN fission products library. For the purposes of this study, the standard 26 groups data set, KFKINR, developed at Forschungszentrum Karlsruhe, Germany, has been extended by the addition of the cross-sections of 13 important actinides and 68 most important fission products. It has been confirmed that these 68 fission products constitute about 95% of the total fission products yield and about 99.5% of the total absorption due to fission products in fast reactors. The amount of fissile material required to guarantee the criticality of the reactor during recycling schemes has also been investigated. Cumulative high active waste per ton of initial heavy metal is also calculated. Results show that the recycling of actinides and fission products in fast reactors through the atomics international reduction oxidation process results in a reduction of the potential hazard of radioactive waste

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Section: Methods Of Calculationmentioning

confidence: 99%