Denaturing fissile materials

DeVolpi, A.

doi:10.1016/0149-1970(82)90022-1

Cited by 50 publications

(26 citation statements)

References 32 publications

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“…Вследствие жёсткого -излучения дочерних продуктов распада 232 U ядерный заряд, изготовленный из урана с заметной долей 232 U, потребует специальной дистанционной технологии обращения [21]. Изо-топ 232 U является мощным источником нейтронов спонтанного деления (1300 н/(скг) [21]).…”

Section: физические характеристики легководного ядерного реактора с дunclassified

“…Изо-топ 232 U является мощным источником нейтронов спонтанного деления (1300 н/(скг) [21]). Кроме того, испускаемые им -частицы способны генерировать нейтроны в (, n)-реакциях на ядрах лёгких элемен-тов, которые всегда присутствуют в делящемся материале в виде примесей.…”

Section: физические характеристики легководного ядерного реактора с дunclassified

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Fusion Hybrid With Thorium Blanket: On Its Innovative Potential in Fuel Cycle of Nuclear Reactors

Шмелев¹,

Kulikov²,

Kurnaev³

et al. 2014

PAST-TF

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Гибридный реактор синтеза-деления с ториевым бланкетом. О его потенциале в топливном цикле ядерных реакторов ВАНТ. Сер. Термоядерный синтез, 2014, т. 37, вып. В настоящее время не прекращаются дискуссии о целесообразности вовлечения тория в топливный цикл ядерной энергетики. В данной статье показано, что топливо на основе 231 Pa-232 U-233 U-Th, которое можно накапливать в гибридном термоядерном реакторе (ГТР) с Th-бланкетом, будучи использовано в легководном ядерном реакторе, открывает возможность достижения глубокого -до 30% тяжёлых атомов (т.а.) и даже сверхглубокого выгорания. Эта возможность обосновывается тем, что такое топливо обладает способностью стабилизации размножающих свойств в процессе глубокого выгорания. Помимо этого, приме-нение такого топлива позволяет повысить защищённость ядерного топливного цикла (ЯТЦ) от неконтролируемого распростра-нения делящихся материалов, так как в топливе, накапливаемом в Th-бланкете, урановая фракция содержит беспрецедентно большую долю изотопа 232 U (в количестве нескольких процентов!), что в замкнутом ЯТЦ в существенной мере будет препятст-вовать переключению делящихся материалов на неэнергетические цели.Ключевые слова: гибридный термоядерный реактор, ториевый бланкет, протактиний-231, уран-232, глубокое выгорание топ-лива, нераспространение, замкнутый топливный цикл ядерных реакторов. FUSION HYBRID WITH THORIUM BLANKET: ON ITS INNOVATIVE POTENTIAL IN FUEL CYCLE OF NUCLEAR REACTORS A.N. Shmelev, G.G. Kulikov, V.А. Kurnaev, G.H. Salahutdinov, E.G. Kulikov, V.А. Аpse National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Moscow, RussiaCurrently there are discussions about appropriateness of involving thorium into fuel cycle of nuclear power. The paper demonstrates the use of 231 Pa-232 U-233 U-Th composition to be produced in thorium blanket of hybrid thermonuclear reactor (HTR) as a fuel material of nuclear power light-water reactors that opens an opportunity to reach high (up to 30% of heavy metals) or even ultra-high fuel burnup. The fuel composition is characterized by the stabilized neutron-multiplying properties in the process of high fuel burn-up. In addition, the fuel composition can upgrade the protection of nuclear fuel cycle against unauthorized proliferation of fissile materials due to the unprecedented large fraction of 232 U (at the level of several percents!) in uranium produced from thorium in the HTR blanket that can substantially complicate a diversion of fissile materials to illegal purposes from peaceful energy utilization.Ключевые слова: hybrid thermonuclear reactor, thorium blanket, protactinium-231, uranium-232, high fuel burn-up, non-proliferation, closed fuel cycle of nuclear reactors. ВВЕДЕНИЕТрадиционно технология управляемого термоядерного синтеза (УТС) рассматривалась и рассматри-вается как источник энергии с практически неисчерпаемыми ресурсами на длительную перспективу. Однако ведущиеся разработки, освоение и введение в строй быстрых реакторов и замыкание ядерного топливного цикла (ЯТЦ) также позволят расширит...

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Section: физические характеристики легководного ядерного реактора с дunclassified

Fusion Hybrid With Thorium Blanket: On Its Innovative Potential in Fuel Cycle of Nuclear Reactors

Шмелев¹,

Kulikov²,

Kurnaev³

et al. 2014

PAST-TF

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“…It is based on the main composition of Pu-239, which is more than 95% in total plutonium composition. 29) Plutonium production for such composition directly comes from converted depleted uranium as loaded fuel at the blanket region without any MA doping materials. The produced material in the blanket region should have an intrinsic barrier in order to protect this material or to reduce the level of proliferation resistance.…”

Section: Isotopic Plutonium Composition Analysismentioning

confidence: 99%

“…Plutonium categorizations are based on the following levels of plutonium composition from weapon grade to plutonium exempt grade. 24) The attractiveness concept adopted several criteria based on the fissile plutonium contents as well as even mass of plutonium compositions: (1) Level of weapon-grade plutonium, 12,26,29) (2) Level of plutonium with 30% Pu-240, 12,26) (3) Level of plutonium with 6% Pu-238, 13) (4) Level of plutonium exempt from safeguards. 11) Attractiveness levels as comparative analysis based on different MOX and TRU fuel loadings in the core and different MA loadings in the blanket region, which are based on their isotopic plutonium compositions, are shown in Fig.…”

Section: Materials Attractiveness Analysismentioning

confidence: 99%

Basic Analysis on Isotopic Barrier of Material Attractiveness Based on Plutonium Composition of FBR

Permana

Suzuki

Saito

2011

Journal of Nuclear Science and Technology

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Fuel behaviors of the large fast breeder reactor have been investigated, as well as material attractiveness based on isotopic plutonium composition for evaluating proliferation resistance with regards to a combined evaluation of decay heat and spontaneous fission neutron barrier as key parameters of isotopic material barrier. Trans-uranium fuel (TRU) (MA + U-Pu) in the core regions and MA doping (MA + natural U) in the blanket regions as options of MA loading produce a higher Pu-238 composition for denaturing plutonium, which mainly comes from converted Np-237. The isotopic plutonium composition of TRU fuel is relatively less than the Pu composition of MOX fuel except for the Pu-238 composition that is higher than that of MOX fuel. MA in the core or blanket regions, which produces a higher Pu-238 composition, plays a key role in obtaining a high-level material barrier of decay heat and spontaneous fission neutron compositions. The material attractiveness level of plutonium composition in the core regions can be categorized as practically unusable and its level becomes less by adopting TRU fuel. In addition, the material attractiveness level in the blanket regions as being practically unusable can be reached from weapon grade by loading MA at a 2% doping rate.

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“…In the present paper, pressurized water reactor loaded with UOX of 5% 235 U (low enriched uranium: LEU) and 20% 235 U (high enriched uranium: HEU) are chosen as the basic fuels to represent current commercial technology and the upper limit of uranium enrichment to be exempted from proliferation concern 12) respectively. At first, the addition of all minor actinides (Np, Am, and Cm) into UOX is considered, and the second option is the addition of only 237 Np (thereafter will be called as Np Table 2.…”

Section: Approachmentioning

confidence: 99%

Inherent Protection of Plutonium by Doping Minor Actinide in Thermal Neutron Spectra

Peryoga

Sagara

Saito

et al. 2005

J. Nucl. Sci. Technol.

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The present study focuses on the exploration of the effect of minor actinide (MA) addition into uranium oxide fuels of different enrichment (5% 235 U and 20% 235 U) as ways of increasing fraction of even-mass-number plutonium isotopes. Among plutonium isotopes, 238 Pu, 240 Pu and 242 Pu have the characteristics of relatively high decay heat and spontaneous fission neutron rate that can improve proliferation-resistant properties of a plutonium composition. Two doping options were proposed, i.e. doping of all MA elements (Np, Am and Cm) and doping of only Np to observe their effect on plutonium proliferation-resistant properties. Pressurized water reactor geometry has been chosen for fuels irradiation environment where irradiation has been extended beyond critical to explore the subcritical system potential. Results indicate that a large amount of MA doping within subcritical operation highly improves the proliferation-resistant properties of the plutonium with high total plutonium production. Doping of 1% MA or Np into 5% 235 U enriched uranium fuel appears possible for critical operation of the current commercial light water reactor with reasonable improvement in the plutonium proliferation-resistant properties.

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Denaturing fissile materials

Cited by 50 publications

References 32 publications

Fusion Hybrid With Thorium Blanket: On Its Innovative Potential in Fuel Cycle of Nuclear Reactors

Fusion Hybrid With Thorium Blanket: On Its Innovative Potential in Fuel Cycle of Nuclear Reactors

Basic Analysis on Isotopic Barrier of Material Attractiveness Based on Plutonium Composition of FBR

Inherent Protection of Plutonium by Doping Minor Actinide in Thermal Neutron Spectra

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