• Title/Summary/Keyword: Neutron scattering

Search Result 131, Processing Time 0.089 seconds

On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX

  • Xiao, Bowen;Wei, Linfang;Zheng, Youqi;Zhang, Bin;Wu, Hongchun
    • Nuclear Engineering and Technology
    • /
    • v.53 no.3
    • /
    • pp.732-740
    • /
    • 2021
  • Scattering resonance of medium mass nuclides leads complex spectrum in the fast reactor, which requires thousands of energy groups in the spectrum calculation. When the broad-group cross sections are collapsed, reaction rate cannot be completely conserved. To eliminate the error from energy collapsing, the Super-homogenization method in energy collapsing (ESPH) was employed in the fast reactor code SARAX. An ESPH factor was derived based on the ESPH-corrected SN transport equation. By applying the factor in problems with reflective boundary condition, both the effective multiplication factor and reaction rate were conserved. The fixed-source iteration was used to ensure the stability of ESPH iteration. However, in the energy collapsing process of SARAX, the vacuum boundary condition was adopted, which was necessary for fast reactors with strong heterogeneity. To further reduce the error caused by leakage, an additional conservation factor was proposed to correct the neutron current in energy collapsing. To evaluate the performance of ESPH with conservation factor, numerical benchmarks of fast reactors were calculated. The results of broad-group calculation agreed well with the direct full-core Monte-Carlo calculation, including the effective multiplication factor, radial power distribution, total control rod worth and sodium void worth.

The applicability study and validation of TULIP code for full energy range spectrum

  • Wenjie Chen;Xianan Du;Rong Wang;Youqi Zheng;Yongping Wang;Hongchun Wu
    • Nuclear Engineering and Technology
    • /
    • v.55 no.12
    • /
    • pp.4518-4526
    • /
    • 2023
  • NECP-SARAX is a neutronics analysis code system for advanced reactor developed by Nuclear Engineering Computational Physics Laboratory of Xi'an Jiaotong University. In past few years, improvements have been implemented in TULIP code which is the cross-section generation module of NECP-SARAX, including the treatment of resonance interface, considering the self-shielding effect in non-resonance energy range, hyperfine group method and nuclear library with thermal scattering law. Previous studies show that NECP-SARAX has high performance in both fast and thermal spectrum system analysis. The accuracy of TULIP code in fast and thermal spectrum system analysis is demonstrated preliminarily. However, a systematic verification and validation is still necessary. In order to validate the applicability of TULIP code for full energy range, 147 fast spectrum critical experiment benchmarks and 170 thermal spectrum critical experiment benchmarks were selected from ICSBEP and used for analysis. The keff bias between TULIP code and reference value is less than 300 pcm for all fast spectrum benchmarks. And that bias keeps within 200 pcm for thermal spectrum benchmarks with neutron-moderating materials such as polyethylene, beryllium oxide, etc. The numerical results indicate that TULIP code has good performance for the analysis of fast and thermal spectrum system.

OECD/NEA BENCHMARK FOR UNCERTAINTY ANALYSIS IN MODELING (UAM) FOR LWRS - SUMMARY AND DISCUSSION OF NEUTRONICS CASES (PHASE I)

  • Bratton, Ryan N.;Avramova, M.;Ivanov, K.
    • Nuclear Engineering and Technology
    • /
    • v.46 no.3
    • /
    • pp.313-342
    • /
    • 2014
  • A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).

XPS Study of Mn 2pp and 3s Satellite Structures of Heusler Alloys: NiMnSb, ppdMnSb, pptMnSb

  • Yang, See-Hun;Oh, Se-Jung;ppark, Je-Geun
    • Proceedings of the Korean Vacuum Society Conference
    • /
    • 1994.02a
    • /
    • pp.50-50
    • /
    • 1994
  • Half-metallic Heusler alloys (NiMnSb, ppdMnSb, pptMnSb) have attracted much attention due to their unique electronic and magnetic structures. Sppin-ppolarized band structure calculation ppredicts metallic behavior for the majority sppin states and semiconductor behavior for the minority sppin states. We have studied the electronic structures of these half-metallic Heusler alloys by core-level pphotoemission sppectroscoppy of Mn 2pp and 3s XppS sppectra. We found large intensities of Mn 2pp satellites and 3s exchange spplitting comppared with other metal Mn-alloys. These satellite structure can be understood by applying Anderson imppurity model. This fact supports the calculated sppin pprojected ppartial density of states which suggests that the valence electrons be highly sppin ppolarized near Fermi level and that the electrons involved with charge-transfer be mainly minority sppin ones which have semiconducting band structure. The trend of charge transfer energies Δ from ligands (Sb 5pp) to Mn 3d, obtained from our model fitting, is consistent with that calculated from sppin pprojected ppartial density of state. Also the trend of d-d electron correlation energies U calculated from Mn Auger line L3 VV by Mg $K\alpha$ source is comppatible with that resulted from our model fitting. We fitted the Mn 3s curve in the same way as for insulating Mn comppounds by using the same pparameters calculated from Mn 2pp curve fitting exceppt for the Coulomb interaction energy Q between core hole and d-electrons. The 3s sppectra were analyzed by combing the charge transfer model and a simpple model taking into account the configuration mixing effect due to the intra-shell correlation. We found that the exchange interaction between 3s hole and 3d electrons is mainly respponsible for the satellite of Mn 3s sppectra. This is consistent with the neutron scattering data, which suggests local 3d magnetic moment. We find that the XppS analysis results of Mn 2pp and 3s satellite structures of half-metallic Heusler alloys are very similar to those of insulating transition metal comppounds.

  • PDF

Effect of Coiling Temperature and Alloying Elements on the Mechanical Properties and Precipitation Behavior in High Strength Hot Rolled Steel Sheets (고강도 열연강판의 기계적 성질과 석출거동에 미치는 권취온도와 합금원소의 영향)

  • Kang, S.S.;Lee, O.Y.;Han, S.H.;Jin, K.G.;Seong, B.S.
    • Korean Journal of Materials Research
    • /
    • v.13 no.10
    • /
    • pp.683-690
    • /
    • 2003
  • The high strength low alloy(HSLA) steels microalloyed with Nb, Ti and V have been widely used as the automobile parts to decrease weight of vehicles. The effects of process conditions are investigated in the aspects of the precipitation behavior and the mechanical properties of HSLA steel microalloyed with Nb and Ti using TEM, SANS and mechanical testing. When Ti was added to a 0.07C-1.7Mn steel which was coiled at $500^{\circ}C$, the specimen revealed the property of higher tensile strength of 853.1 MPa and the stretch-flangeability of 60%. The stretch-flangeability was increased up to 97.8% for coiling temperature above $700^{\circ}C$. The precipitation hardening cannot be achieved in the 0.045C-1.65Mn steel which was the lower density of fine precipitates. However, the 0.07C-1.7Mn steels containing Nb and/or Ti which was coiled at X$/^{\circ}C$ have a high precipitates density of $2${\times}$10^{ 5}$/$\mu$㎥. The high strength of these steels was attributed to the precipitation hardening caused by a large volume froction of (Ti, Nb)C precipitates with a size below 5 nm in ferrite matrix.

Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis

  • Du, Xianan;Choe, Jiwon;Choi, Sooyoung;Lee, Woonghee;Cherezov, Alexey;Lim, Jaeyong;Lee, Minjae;Lee, Deokjung
    • Nuclear Engineering and Technology
    • /
    • v.51 no.8
    • /
    • pp.1871-1885
    • /
    • 2019
  • The deterministic MOC code STREAM of the Computational Reactor Physics and Experiment (CORE) laboratory of Ulsan National Institute of Science and Technology (UNIST), was initially designed for the calculation of pressurized water reactor two- and three-dimensional assemblies and cores. Since fast reactors play an important role in the generation-IV concept, it was decided that the code should be upgraded for the analysis of fast neutron spectrum reactors. This paper presents a coupled code - TULIP/STREAM, developed for the fast reactor assembly and core calculations. The TULIP code produces self-shielded multi-group cross-sections using a one-dimensional cylindrical model. The generated cross-section library is used in the STREAM code which solves eigenvalue problems for a two-dimensional assembly and a multi-assembly whole reactor core. Multiplication factors and steady-state power distributions were compared with the reference solutions obtained by the continuous energy Monte-Carlo code MCS. With the developed code, a sensitivity study of the number of energy groups, the order of anisotropic PN scattering, and the multi-group cross-section generation model was performed on the keff and power distribution. The 2D core simulation calculations show that the TULIP/STREAM code gives a keff error smaller than 200 pcm and the root mean square errors of the pin-wise power distributions within 2%.

Phase Behavior and Spontaneous Vesicle Formation in Aqueous Solutions of Anionic Ammonium Dodecyl Sulfate and Cationic Octadecyl Trimethyl Ammonium Chloride Surfactants

  • Kang, Kye-Hong;Kim, Hong-Un;Lim, Kyung-Hee
    • Bulletin of the Korean Chemical Society
    • /
    • v.28 no.4
    • /
    • pp.667-674
    • /
    • 2007
  • Phase behavior for the mixed aqueous surfactant systems of cationic octadecyl trimethyl ammonium chloride (OTAC)/anionic ammonium dodecyl sulfate (ADS)/water was examined. Below the total surfactant concentrations of 1.5 m molal, mixed micelles were formed. At the total surfactant concentrations higher than 1.5 m molal, there appeared a region where mixed micelles and vesicles coexist. As the surfactant concentration increased, the systems looked very turbid and much more vesicles were observed. The vesicles were spontaneously formed in this system and their existence was observed by negative-staining transmission electron microscopy (TEM), small-angle neutron scattering (SANS) and encapsulation efficiency of dye. The vesicle region was where the molar fraction α of ADS to the total mixed surfactant was from 0.1 to 0.7 and the total surfactant concentration was above 5 × 10-4 molality. The size and structure of the vesicles were determined from the TEM microphotographs and the SANS data. Their diameter ranged from 450 nm to 120μm and decreased with increasing total surfactant concentration. The lamellar thickness also decreased from 15 nm to 5 nm with increasing surfactant concentration and this may be responsible for the decrease in vesicle size with the surfactant concentration. The stability of vesicles was examined by UV spectroscopy and zeta potentiometry. The vesicles displayed long-term stability, as UV absorbance spectra remained unchanged over two months. The zeta potentials of the vesicles were large in magnitude (40-70 mV) and the observed longterm stability of the vesicles may be attributed to such high ζ potentials.

Mn 도핑 농도에 따른 ZnO 나노 입자의 구조와 자성 특성 연구

  • Kim, Jeong-Hun;Kim, Seon-Ho;Jeon, Gwang-Deok;Lee, Ji-Eun;Lee, Hui-Su;Jeong, Jin-Cheol;Choe, Pu-Reum;Eo, Jin-Seok;Park, Jun-Ho;Lee, Ji-Un;Choe, Seung-Yeon;Choe, Gyu-Hyeon;Baek, Min;Yang, U-Cheol
    • Proceedings of the Korean Vacuum Society Conference
    • /
    • 2013.02a
    • /
    • pp.604-604
    • /
    • 2013
  • 차세대 반도체 분야인 스핀트로닉스 소자의 필수적인 물질인 강자성-반도체 하이브리드 물질인 Dilute magnetic semiconductor (DMS)에 관한 연구가 최근 많은 관심을 가지고 있다. 그중에서 넓은 에너지 밴드 갭 에너지(3.37 eV)를 가지고 있고 상온에서 엑시톤 결합 에너지가 ~60 mV로 광전자 소자, 전계 디스플레이 에 응용이 가능한 물질인 ZnO는 최근에 전이금속을 도핑하여 상온에서 강자성 특성을 나타내어 활발한 연구가 이루어지고 있다. 그러나, 이 물질에 대한 특성과 자성의 원인 규명에 관한 연구는 논란이 되고 있다. 본 연구에서는 Mn이 도핑된 ZnO 나노 입자를 만들고, Mn 물질의 도핑 농도에 따른 ZnO 나노 입자의 구조, 크기 및 자기 구조를 측정하여 구조와 자성의 상관관계에 관한 연구하였다. ZnxMn1-xO 나노 입자는 화학적 졸-겔(sol-gel) 방법을 이용하여 준비하였다. ZnxMn1-xO 나노 입자의 크기 및 격자 구조적 특징은 XRD (X-ray diffraction)와 TEM (Transmission Electron Microscope), SEM (Scanning Electron Microscope), SANS (Small Angle Neutron Scattering)를 이용하여 측정하였고 물질의 자기적 특징은 SQUID를 이용하여 조사하였다. Mn 도핑이 증가함에 따라 격자간격이 커지고 나노 입자의 크기는 감소하였으며, Zn와 Mn의 성장 시, 비율이 9:1의 경우에 상온에서 강자성 특성이 나타남을 보았다. 그 이상의 Mn 도핑 비율에서는 상자성 특성이 나타남을 보았다. 본 연구를 통하여 스핀트로닉스 소자 응용을 위한 ZnO 나노 입자에 최적의 Mn 도핑 농도를 제시하고 나노 입자의 자기 특성 형성의 원인 및 모델을 제시하였다.

  • PDF

Gamma ray attenuation behaviors and mechanism of boron rich slag/epoxy resin shielding composites

  • Mengge Dong;Suying Zhou ;He Yang ;Xiangxin Xue
    • Nuclear Engineering and Technology
    • /
    • v.55 no.7
    • /
    • pp.2613-2620
    • /
    • 2023
  • Excellent thermal neutron absorption performance of boron expands the potential use of boron rich slag to prepare epoxy resin matrix nuclear shielding composites. However, shielding attenuation behaviors and mechanism of the composites against gamma rays are unclear. Based on the radiation protection theory, Phy-X/PSD, XCOM, and 60Co gamma ray source were integrated to obtain the shielding parameters of boron rich slag/epoxy resin composites at 0.015-15 MeV, which include mass attenuation coefficient (µt), linear attenuation coefficient (µ), half value thickness layer (HVL), electron density (Neff), effective atomic number (Zeff), exposure buildup factor (EBF) and exposure absorption buildup factor (EABF).µt, µ, HVL, Neff, Zeff, EBF and EABF are 0.02-7 cm2/g, 0.04-17 cm-1, 0.045-20 cm, 5-14, 3 × 1023-8 × 1023 electron/g, 0-2000, and 0-3500. Shielding performance is BS4, BS3, BS3, BS1 in descending order, but worse than ordinary concrete. µ and HVL of BS1-BS4 for 60Co gamma ray is 0.095-0.110 cm-1 and 6.3-7.2 cm. Shielding mechanism is main interactions for attenuation gamma ray by BS1-BS4 are elements with higher content or higher atomic number via Photoelectric Absorption at low energy range, and elements with higher content via Compton Scattering and Pair Production in Nuclear Field at middle and higher energy range.

New Magnetic Phases of Fe-N and Mn-Al Alloys Produced by Mechanochemical Milling (기계적 밀링 및 화학적 추출법에 의해 제조한 Fe-N 및 Mn-Al계의 새로운 자성재료)

  • Kyu-Jin Kim;Tae-Hwan Noh;Kenji Suzuki
    • Journal of the Korean Magnetics Society
    • /
    • v.4 no.4
    • /
    • pp.347-354
    • /
    • 1994
  • The structural change and magnetic properties of mechanically milled Fe-N and Mn-Al alloy powders have been investigated by XRD, TEM, VSM, $M\"{o}ssbauer$ spectroscopy and inelastic neutron scattering measurements. During milling of ${\gamma}'-Fe_{4}N$ powders, and fcc ${\gamma}'-Fe_{4}N$ phase is transformed to a bct ${\alpha}'-Fe(N)$ phase by stress-induced martensitic transformation, being accompanied by an initial increase in saturation magnetization. During annealing the bct ${\alpha}'-Fe(N)$ nanocrystalline phase which is obtained by mechanical grinding for a long time, an ${\alpha}'-Fe_{16}N_{2}$ phase partially appears as an intermediate phase at 673~773 K, causing an increase in saturation magnetization. During milling of Mn-45, 70 and 85 at.% Al mixed powders, Al atoms are partially solubilized into an ${\alpha}-Mn$ phase. The Al supersaturated ${\alpha}-Mn-type$ phases change from paramagnetic to ferromagnetic : the saturation magnetization is 11 emu/g for the as-milled Mn-70 at.% Al powders. Moreover, by removing almost all Al atoms from the as-milled Mn-85 at.% Al powders using chemical leaching, the saturation magnetization increases up to 36 emu/g. The above bct ${\alpha}'-Fe(N)$ and ferromagnetic ${\alpha}-Mn$ type alloys are the magnetic materials found for the first time, by using the present mechanochemical process.

  • PDF