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Verification of DeCART2D/CAPP code system for VHTR analysis with PMR-200 benchmark
Jeong, Eun,Park, Jinsu,Lee, Hyun Chul,Zhang, Peng,Yu, Jiankai,Lemaire, Matthieu,Choi, Sooyoung,Lee, Deokjung Elsevier 2019 Annals of nuclear energy Vol.133 No.-
<P><B>Abstract</B></P> <P>This paper presents the verification of the DeCART2D/CAPP code system for the Very High Temperature Gas-Cooled Reactor (VHTR) analysis with the Prismatic Modular Reactor 200 (PMR-200) benchmark. The McCARD Monte Carlo (MC) code is used to obtain the reference solution. The verification has been performed for the effective multiplication factor (<I>k<SUB>eff</SUB> </I>) and reactivity coefficients at the levels of fuel compact, fuel block, and full core. Furthermore, the verification of the depletion calculation has been conducted for the fuel block and the verification for the power distribution has been performed at the levels of fuel block, two-dimensional (2D) and three-dimensional (3D) full core. The verification results of DeCART2D, CAPP, and DeCART2D/CAPP are compared systematically against the reference McCARD solutions to demonstrate the VHTR modeling capability and accuracy of the codes. It was successfully shown that the <I>k<SUB>eff</SUB> </I> errors of the DeCART2D/CAPP code system are smaller than ∼510 pcm, the isothermal temperature coefficient (ITC) errors are smaller than ∼0.66 pcm/K, and the power distribution errors are smaller than 2.80%. It was also shown that the maximum <I>k<SUB>eff</SUB> </I> errors of DeCART2D fuel block depletion calculations are smaller than ∼460 pcm.</P>
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Jang, Jaerim,Kim, Wonkyeong,Jeong, Sanggeol,Jeong, Eun,Park, Jinsu,Lemaire, Matthieu,Lee, Hyunsuk,Jo, Yongmin,Zhang, Peng,Lee, Deokjung Elsevier 2018 Annals of nuclear energy Vol.114 No.-
<P><B>Abstract</B></P> <P>This paper presents the validation of the continuous-energy Monte Carlo neutron-transport code MCS with the ENDF/B-VII.0 neutron cross-section library for the criticality safety analysis of PWR spent fuel pools and storage casks. The MCS code is developed by the COmputational Reactor physics and Experiment laboratory (CORE) of Ulsan National Institute of Science and Technology (UNIST) for the analysis of Pressurized Water Reactors (PWRs) with high fidelity and high performance. The validation is conducted with 279 selected critical benchmarks from the International Criticality Safety Benchmark Evaluation Project (ICSBEP). The 279 validation cases are representative of PWR spent fuel pools and storage casks with <SUP>235</SUP>U enrichment ranging from 2.35 wt% to 4.74 wt%, pin pitch ranging from 1.075 cm to 2.540 cm, moderator to fuel ratio (H/U) ranging from 0.4683 and 11.5398, Energy of the Average Lethargy causing Fission (EALF) ranging from 0.0109 eV to 1.0600 eV, without soluble boron and with soluble boron concentration ranging from 0.015 g/L to 5.030 g/L. The calculation of the effective neutron multiplication factor by MCS is validated by the comparison between experiment and calculation for the selected critical benchmarks. The Upper Safety Limit (USL) of the MCS code is established in accordance to the NUREG/CR-6698 guideline recommended by the NRC (US National Regulatory Commission). The full validation process and determination of USL based on the selected critical benchmarks was also repeated with the MCNP6.1 and SERPENT2.1.27 codes in order to compare the performances of MCS with other reactor analysis codes. This paper demonstrates the capability of the MCS code for the criticality safety analysis of PWR spent fuel pools and storage casks.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Validation of UNIST Monte Carlo code MCS with ENDF/B.VII.0 nuclear data library. </LI> <LI> Criticality safety analysis of PWR spent fuel pool and storage cask. </LI> <LI> Upper safety limits derived with single-sided tolerance band, limit and non-parametric methods. </LI> <LI> Code/code comparison against MCNP6.1 and SERPENT2.1.27 Monte Carlo codes. </LI> </UL> </P>
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Optical temperature sensing properties of Yb3+/Tm3+ co-doped NaLuF4 crystals
Lili Tong,Xiangping Li,Ruinian Hua,Lihong Cheng,Jiashi Sun,Jinsu Zhang,Sai Xu,Hui Zheng,Yanqiu Zhang,Baojiu Chen 한국물리학회 2017 Current Applied Physics Vol.17 No.7
Yb3þ/Tm3þ and Yb3þ/Er3þ co-doped NaLuF4 crystals were synthesized by a facile hydrothermal method. The optical temperature sensing properties of Tm3þ based upon its two thermally coupled energy levels 3F2, 3 and 3H4 were systematically investigated by means of fluorescence intensity ratio (FIR) technique. The 980 nm laser-induced thermal effect on Tm3þ doped NaLuF4 crystals was studied by using Er3þ doped sample as thermal probe. The temperature sensitivity of Tm3þ in NaLuF4: Yb3þ/Tm3þ crystals shows a nonlinear dependence on temperature, and the maximum value is about 0.00045 K『1 at 600 K. The accuracy and reliability of the optical thermometry based on Tm3þ in NaLuF4: Yb3þ/Tm3þ crystals has been checked by using Yb3þ/Er3þ co-doped sample as temperature sensing unit. The results demonstrate that NaLuF4: Yb3þ/Tm3þ crystals have good sensing stability and may have potential application for the optical thermometry.
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