• Nuclear Engineering and Technology
• /
• 제50권6호
• /
• pp.820-828
• /
• 2018

The growing nuclear threat has amplified the need for developing diverse and accurate nuclear forensics analysis techniques to strengthen nuclear security measures. The work presented here is part of a research effort focused on developing a methodology for reactor-type discrimination of weapons-grade plutonium. To verify the developed methodology, natural $UO_2$ fuel samples were irradiated in a thermal neutron spectrum at the University of Missouri Research Reactor (MURR) and produced approximately $20{\mu}g$ of weapons-grade plutonium test material. Radiation transport simulations of common thermal reactor types that can produce weapons-grade plutonium were performed, and the results are presented here. These simulations were needed to verify whether the plutonium produced in the natural $UO_2$ fuel samples during the experimental irradiation at MURR was a suitable representative to plutonium produced in common thermal reactor types. Also presented are comparisons of fission product and plutonium concentrations obtained from computational simulations of the experimental irradiation at MURR to the nondestructive and destructive measurements of the irradiated natural $UO_2$ fuel samples. Gamma spectroscopy measurements of radioactive fission products were mostly within 10%, mass spectroscopy measurements of the total plutonium mass were within 4%, and mass spectroscopy measurements of stable fission products were mostly within 5%.

• Nuclear Engineering and Technology
• /
• 제51권5호
• /
• pp.1355-1364
• /
• 2019

A recently published nuclear forensics methodology for source discrimination of separated weapons-grade plutonium utilizes intra-element isotope ratios and a maximum likelihood formulation to identify the most likely source reactor-type, fuel burnup and time since irradiation of unknown material. Sensitivity studies performed here on the effects of random measurement error and the uncertainty in intra-element isotope ratio values show that different intra-element isotope ratios have disproportionate contributions to the determination of the reactor parameters. The methodology is robust to individual errors in measured intra-element isotope ratio values and even more so for uniform systematic errors due to competing effects on the predictions from the selected intra-element isotope ratios suite. For a unique sample-model pair, simulation uncertainties of up to 28% are acceptable without impeding successful source-reactor discrimination. However, for a generic sample with multiple plausible sources within the reactor library, uncertainties of 7% or less may be required. The results confirm the critical role of accurate reactor core physics, fuel burnup simulations and experimental measurements in the proposed methodology where increased simulation uncertainty is found to significantly affect the capability to discriminate between the reactors in the library.

• Nuclear Engineering and Technology
• /
• 제52권6호
• /
• pp.1156-1163
• /
• 2020

Fuel temperature coefficient (FTC) of PuO₂+ZrO₂ (ROX) fueled LWR cell is analyzed neutronically with reactor- and weapons-grade plutonium fuels in comparison with a U-free PuO₂+ThO₂ (TOX), and a conventional MOX fuel cells. The FTC value of a ROX fueled LWR is smaller compared to a TOX or a MOX fueled LWRs and becomes extremely positive especially, at EOL. This is because when fuel temperature is increased, thermal neutron spectrum is shifted to harder, which is extreme at EOL in ROX fuel than that in TOX and MOX fuels. Consequently at EOL, ²³⁹Pu and ²⁴¹Pu contributes to positive fuel temperature reactivity (FTR) in ROX fuel, while they have negative contribution in TOX and MOX fuels. The FTC problem of ROX fuel is mitigated by additive ThO₂, UO₂ or Er₂O₃. In ROX-additive fuel, the atomic density of fissile Pu becomes more than additive free ROX fuel especially at EOL, which is the main cause to improve the FTC problem. The density of fissile Pu is more effective to decrease the thermal spectrum shifts with increase the fuel temperature than additive ThO₂, UO₂ or Er₂O₃ in ROX fuel.

• 분석과학
• /
• 제17권6호
• /
• pp.514-519
• /
• 2004

BOMARC 미사일 발사대 주변에서 채취한 토양에 대하여 입자크기에 따른 Pu 및 Am 방사능 분석 및 동위원소를 측정하였다. BOMARC 토양에서의 Pu와 Am 방사능 농도는 핵실험에 의해 생성된 방사능 낙진 준위보다 매우 높았으며, 입자크기가 증가함에 따라 감소하는 경향을 보여주었다. BOMARC 토양에서 측정한 Pu-238 / Pu-239, 240, Pu-241 / Pu-239, 240 및 Am-241 / Pu-239, 240 방사능비는 핵실험에 의해 생성된 방사능 낙진에 대한 방사능 농도비 보다 약간 낮은값을 나타내었다. ICP-MS로 측정한 Pu-240 / Pu-239 질량비는 북반구 대기권 핵실험 및 체르노빌 원전사고에 의한 질량비보다 매우 낮은 값을 나타내었고, Greenland Thule 지역에서 핵무기를 탑재한 B52 비행기 사고로 방출된 핵무기에 대한 질량비와 비슷한 값을 나타내었다. BOMARC 토양에서 측정된 Pu 및 Am 동위원소들의 방사능비 및 질량비로부터 BOMARC 토양에 오염된 Pu는 핵무기용 Pu로부터 생성되었다고 판단된다.