Coupled analysis for new fuel design using UN and UC for SCWR

Chaudri, Khurrum Saleem; Tian, Wenxi; Su, Yumin; Zhao, Hao; Zhu, Dahuan; Su, G.H.; Qiu, Suizheng

doi:10.1016/j.pnucene.2012.11.001

Cited by 29 publications

(8 citation statements)

References 31 publications

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“…Pseudo material construct (Conlin et al, 2005) Table 1 Design parameters for reference fuel assembly (Liu and Cheng, 2009 with square root interpolation between 100 K spaced cross section libraries is used to model the Doppler broadening effect for fuel materials. This methodology has been verified to give reasonably accurate results (Chaudri et al, 2013).…”

Section: Monte Carlo N-particle (Mcnp) Transport Theory Codementioning

confidence: 92%

“…Case 2 and 3 are carried out to check the feasibility of burning RG-Pu in SCWR. Case 9 explores the coated fuel pellet design (Chaudri et al, 2013) to use mixed thorium-uranium mono nitride fuel in light water reactor environment. Thorium mono nitride fuel pose similar problem of reaction with water as that for uranium mono nitride fuel.…”

Section: Explored Fuel Optionsmentioning

confidence: 99%

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Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR

Chaudri

Tian

et al. 2013

Progress in Nuclear Energy

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Section: Monte Carlo N-particle (Mcnp) Transport Theory Codementioning

confidence: 92%

Section: Explored Fuel Optionsmentioning

confidence: 99%

Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR

Chaudri

Tian

et al. 2013

Progress in Nuclear Energy

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“…Some researcheswereperformed on single-ligand ceramic fuels as a substitution of two ligand fuel (UO 2 ) for various reactors such as conventional boiling water reactors [12], Resource-renewable boilingwater reactor (RBWR) [13], the supercritical water reactor [14], and high conversion PWR design [15]. Accident Tolerant Fuel (ATF) [16] was developed by Russia after the Fukushima accident.…”

Section: Introductionmentioning

confidence: 99%

“…Natural nitrogen including 14 N and 15 N isotopes was used in UN fuel. Since the absorption cross-section of 14 N is higher than that of 15 N, 14 N absorbs neutrons parasitically and converts them to 14 C [13]. 14 C is a longlived radioactive isotope and is considered as a poison for the neutron economy.…”

Section: Introductionmentioning

confidence: 99%

Neutronic analysis of alternative ceramic fuels in the next generation of VVER-1000/V446 reactor

Rahimi,

Heidari,

Kheradmand Saadi

et al. 2023

Phys. Scr.

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One of the most important issues in nuclear fuel management is burnup increase, which impacts significantly on the reactor cycle length. Burnup enlargement specifically leads to reducing the cost of electricity generation and increasing efficiency. In the present study, the neutronic analysis of some alternative ceramic fuels includingUN, 15UN, and UChas been performedthe VVER-1000/V446 reactor, comparing with the conventional UO2. Being single-ligand, the alternative fuels’ density of heavy metals such as uranium is greater than UO2’s one. Therefore, the absorption and fissionamounts in thesefuels will be higher than theones in UO2 fuel. By modellingVVER-1000/V446 reactor with MCNPX2.6 Monte Carlo code, we showed that the excess reactivity value for UC fuel (169.173 ∆K/K) increased compared to UO2 fuel (165.526). Due to the ultra-high burnup, the reactor cycle length is 398 days for 15UN fuel, while it is 270, 308, and 130 days for UO2, UC, and UN fuels, respectively, and has increased by 47%. Therefore, the use of alternative fuels has advantages like plant construction cost reduction.excess reactivity, discharge burn up, making them suitable substitution of conventional UO2 for the next generation of LWRs.

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“…However, the major drawback to UN fuels are their low oxidation resistance; UN powder readily oxidizes in air and pellets in super-heated steam [14][15][16]. Three primary methods have been postulated to improve its oxidation resistance: Addition of USi x to UN powder followed by liquid phase sintering, alloying UN with compounds that will increase its oxidation resistance, and coating UN with a more inert material (such as ZrC) to produce a chemical barrier [3,9,17]. The focus of the work presented here is to use a nitride synthesis technique that avoids excessive carbon impurities and to develop an accident tolerant fuel.…”

Section: Introductionmentioning

confidence: 99%

Synthesis and sintering of UN-UO2 fuel composites

Jaques

Watkins

Croteau

et al. 2015

Journal of Nuclear Materials

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The design and development of an economical, accident tolerant fuel (ATF) for use in the current light water reactor (LWR) fleet is highly desirable for the future of nuclear power. Uranium mononitride has been identified as an alternative fuel with higher uranium density and thermal conductivity when compared to the benchmark, UO 2 , which could also provide significant economic benefits. However, UN by itself reacts with water at reactor operating temperatures. In order to reduce its reactivity, the addition of UO 2 to UN has been suggested. In order to avoid carbon impurities, UN was synthesized from elemental uranium using a hydride-dehydridenitride thermal synthesis route prior to mixing with up to 10 wt% UO 2 in a planetary ball mill.

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Coupled analysis for new fuel design using UN and UC for SCWR

Cited by 29 publications

References 31 publications

Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR

Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR

Neutronic analysis of alternative ceramic fuels in the next generation of VVER-1000/V446 reactor

Synthesis and sintering of UN-UO2 fuel composites

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