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Jendl 3.3

WebMACS calculated from JENDL-3.3 (Japanese Evaluated Nuclear Data Library, version 3, release 3) Descriptions (format of data files) ; Capture cross section for 336 nuclides ; Fission cross section for 61 nuclides (n,p) cross sections for 40 nuclides (n,α) cross sections for 32 nuclides ; Other reactions. These data were reported in Atomic Data and Nuclear … Web10 apr 2024 · を引用文献として記載してください。. JENDL-3.3の概要. 特 徴. 高速炉、熱中性子炉の設計・解析、核融合炉中性子工学、中性子遮蔽計算などに使える日本の汎 …

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WebComparative Studies of JENDL-3.3, JENDL-3.2, JEFF-3, JEF-2.2 and ENDF/B-6.8 Data Libraries on the Monte Carlo Continuous Energy Modeling of the Gas Turbine-Modular … WebCross sections of JENDL-3.2, JENDL-3.3 and JENDL-4.0 were linked. 2006/02/21 Modified to show links to evaluated data libraries. 2005/10/20 Information on spin and half-life shown in each nuclide page was modified. 2005/02/14 Modified to show decay energies. 2004/08/19 G-factors of JENDL-3.3 cross sections are given in cross section tables ... blueberry lemon muffins with lemon glaze https://soulandkind.com

(PDF) Status of JENDL - ResearchGate

Web1 gen 2011 · At around 510 keV, the values in JENDL-3.3 and ENDF/B-VII.0 were smaller than the present result by about 20%, but those in ENDF-VI.8 were larger than the present result by about 20%. Web29 apr 2024 · In order to validate MVP-II, Haut Taux de Combustion (HTC) experiments were analyzed using a code with relatively new nuclear data libraries, JENDL-4.0, ENDF/B-VII.1, and JEFF-3.2. Web15 nov 2010 · @article{osti_21417227, title = {Calculations of Maxwellian-averaged cross sections and astrophysical reaction rates using the ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, and ENDF/B-VI.8 evaluated nuclear reaction data libraries}, author = {Pritychenko, B and Mughaghab, S F and Sonzogni, A A}, abstractNote = {We have calculated the … free home exterior design tool

不同^235U快裂变缓发中子群参数比较和验证 - 豆丁网

Category:(PDF) Statistical Analysis of Neutron Induced Capture

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Jendl 3.3

JEFF-3.1, ENDF/B-VII and JENDL-3.3 critical assemblies …

WebJEFF-3.1, ENDF/B-VII and JENDL-3.3 critical assemblies benchmarking with the Monte Carlo code TRIPOLI J-Ch. Sublet, Y Peneliau and C. Jouanne1 CEA Cadarache, … Web15 dic 2012 · Abstract. Recent releases of three major world nuclear reaction data libraries, ENDF/B-VII.1, JENDL-4.0, and JEFF-3.1.1, have been tested extensively using benchmark calculations. The calculations were performed with the latest release of the continuous energy Monte Carlo neutronics code MCNP, i.e. MCNP6.

Jendl 3.3

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Web6 apr 2024 · The new production scheme of medical radioisotopes, such as 99 Mo, 64 Cu and 67 Cu, using accelerator neutrons is introduced in chapter 3. The development of separation methods of 99m Tc from 99 Mo, and 64 Cu and 67 Cu from Zn samples are given in chapter 4. The deuteron accelerator and the accelerator neutron source are … Web16 dic 2024 · This study evaluated the nuclear data libraries for a small 100 Mega Watt electric (MWe) Molten Salt Reactor with plutonium fuel. The reactor has a power output …

Webcalculated with JENDL-3.3 shows underestimation below 1 keV, while it makes better compared with JENDL-3.2 as shown in Fig. 11. In the energy region above 20 keV, a good agreement is generally obtained except between 0.1 and 1 MeV. For gamma-ray production data, JENDL-3.3 is improved from JENDL-3.2 as shown in Fig. 12. 4. Tungsten WebNeutron cross sections of 337 nuclides in JENDL-3.3 are presented in figures and tables. In the tables, shown are cross sections at 0.0253 eV and 14 MeV, Maxwellian average …

WebSelect first a library, then a sublibrary and finally click on a chemical element to obtain results. Data are available for materials with a cyan background. Library : Sublibrary : Version History: New: (December 2011) • ENDF/B-VII.1 evaluated neutron library. New in version 3.1 (October 2009) Web8 apr 2024 · Theoretical model code was used to evaluate neutron-induced radiative capture cross section on isotope of 237Np, 241Am, 243Am, 244Cm, and 245Cm with an effort to improve the contribution to the ...

Web11 apr 2024 · Requester: Dr Edward T. CHENG at GA, USA Email: Project (context): Structural material for fusion power reactors Impact: SiC is a potential very low activation structural material for a fusion power reactor. Al-27 produced from neutron irradiation of Si generates Al-26 via the Al-27(n,2n) reaction.

WebMaxwellian averaged cross sections, MACS, Astrophysical reaction rates, ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ENDF/B-VI.8,ROSFOND,CENDL-3.1. Results. Reference Paper. … free home extension design softwareWeb李 会，侯英伟，李德源(1.中国辐射防护研究院 核与辐射前沿技术研究中心，太原 030006；2.哈尔滨工程大学 核安全与仿真中心 ... blueberry-lemon ricotta pound cakeWeb8 feb 2008 · ENDF/B-VII.0, the first release of the ENDF/B-VII nuclear data library, was formally released in December 2006. Prior to this event the European JEFF-3.1 nuclear … blueberry lemon pound cake using cake mix