LMFBR models for the ORIGEN2 computer code

Croff, A.G.; McAdoo, J.W.; Bjerke,

doi:10.2172/5908568

Cited by 4 publications

(3 citation statements)

References 11 publications

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“…Such a re ac tor, the Superphoenix, is op er at ing in France [22]. A de tailed model of the 1250 MWe LMFBR is de scribed by Croff et al [23]. At re load ing time, the LMFBR is re fueled with a batch of core fuel el e ments con tain ing 9.8 TIHM (tons of ini tial heavy metal) core fuel, 5.166 TIHM of ax ial blan ket fuel and a batch of ra dial blan ket fuel el ements con tain ing 9.059 TIHM ra dial blan ket fuel.…”

Section: Depletion Calculationsmentioning

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: Depletion Calculationsmentioning

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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“…LMFBR core fuel in equilibrium recycle. 26 The contamination level of the U-233 produced in LWRs fueled with mixtures of enriched uranium and thorium would be still higher but, even at several thousand ppm, the dose rate from a 5-kg sphere of U-233 would be still about an order-of-magnitude lower than that required to achieve the IAEA criterion for self-protection of 100-rem per hour at 1 meter (see Table 2). For "fresh" U-233, i.e.…”

Section: Energy Intervalmentioning

confidence: 99%

U‐232 and the proliferation‐resistance of U‐233 in spent fuel

Kang¹,

Hippel²

2001

Science & Global Security

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The factors influencing the level of U-232 contamination in U-233 are examined for heavy-water-moderated, light-water-moderated and liquid-metal cooled fast breeder reactors fueled with natural or low-enriched uranium and containing thorium mixed with the uranium or in separate target channels. U-232 decays with a 69-year half-life through 1.9-year half-life Th-228 to T1-208, which emits a 2.6 MeV gamma ray upon decay.We find that pressurized light-water-reactors fueled with LEU-thorium fuel at high burnup (70 MWd/kg) produce U-233 with U-232 contamination levels of about 0.4 percent. At this contamination level, a 5 kg sphere of U-233 would produce a gammaray dose rate of 13 and 38 rem/hr at 1 meter one and ten years after chemical purification respectively. The associated plutonium contains 7.5 percent of the undesirable heat-generating 88-year half-life isotope Pu-238.However, just as it is possible to produce weapon-grade plutonium in low-burnup fuel, it is also practical to use heavy-water reactors to produce U-233 containing only a few ppm of U-232 if the thorium is segregated in "target" channels and discharged a few times more frequently than the natural-uranium "driver" fuel. The dose rate from a 5-kg solid sphere of U-233 containing 5 ppm U-232 could be reduced by a further factor of 30, to about 2 mrem/hr, with a close-fitting lead sphere weighing about 100 kg.Thus the proliferation resistance of thorium fuel cycles depends very much upon how they are implemented.

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“…O sistema de códigos neutrônicos será constituído pelo código de transporte por Monte Carlo MCNP4B , pelo código de queima e decaimento radioativo ORIGEN2. 1 (CROFF, 1980;CROFF, 1981; e a integração entre estes dois será feita com MONTEBURNS (POSTON e TRELLUE, 1999). Tal sistema permite obter diversos parâmetros neutrônicos de interesse em um reator nuclear (inclusive em sistemas e dispositivos geometricamente complexos), tais como, fluxo de nêutrons, fator de multiplicação de nêutrons efetivo, distribuição de potência, valor de reatividade de barras de controle, excesso de reatividade, etc.…”

Section: Capítulo 1-introduçãounclassified

Simulação do reator TRIGA IPR-R1 utilizando metodos de transporte por Monte Carlo

Dalle¹

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LMFBR models for the ORIGEN2 computer code

Cited by 4 publications

References 11 publications

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

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

U‐232 and the proliferation‐resistance of U‐233 in spent fuel

Simulação do reator TRIGA IPR-R1 utilizando metodos de transporte por Monte Carlo

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