Jendl 3
Webcal Facility') (TRACY) in the Japan Atomic Energy JENDL-3.3 library and two former-used libraries, Research Institute. In the studies te accurate predic- JENDL-3.2') and ENDF/B_VI,6) are also discussed. tion of neutronic characteristics during power bursts is required because these characteristics control all tran- 2. Experiments Web27 ago 2014 · The preliminary benchmark tests indicate that JENDL-3.2 predicts various reactor characteristics more successfully than the previous version of JENDL-3.1.
Jendl 3
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Web30 apr 2013 · JENDL-3.3 is the final revision of the JENDL-3 series. The problems in JENDL-3.2 were resolved by considering the results of the benchmark analyses and new measurements. Covariances were estimated for important nuclides. After JENDL-3.3, in principle, we evaluate isotopic data without producing elemental data files. WebThis document contains a brief index to the five main data libraries for evaluated neutron reaction data, including BROND-2 from USSR, CENDL-2 from China, ENDF/B-6 from USA, JEF-2 from OECD/NEA, and JENDL-3 from Japan.
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. NDS 113, 3120 (2012) Calculations of Maxwellian-averaged cross sections and astrophysical reaction rates 2010 Downloads: 2012 Downloads: Webcalculated by JENDL-3.1 and 3.2 was evaluated based on the sensitivity analysis for ZPPR-9. The C/E values obtained by JENDL-3.2 approach 1.0 compared to JENDL-3.1 except for the reaction rate ratio of 238U fission to ^'Pu fission and the ratio of ^U capture to ^'Pu fission. In general, scattering
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 … Web27 ago 2014 · Calculations were made based on a continuous-energy Monte Carlo code MCNP4B/4C and multi-group discrete ordinates codes ANISN and DORT. The latest version of NJOY99 was employed to generate cross-section libraries for these transport codes. Calculations with JENDL-3.2, ENDF/B-VI, FENDL-1 and FENDL-2 were also made for …
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 of 100 MWe, which meets the demand for electricity generation in several regions or provinces outside Java Island. Several nuclear data libraries, such as JEFF 3.1, ENDF/B-VII.0, …
Web5 apr 2014 · 宏观方法存由于传输速度被本底淹没曲线,根据该曲线得到缓种方法以当前人们,需持续改进中子发射曲线作者自身,早期曾用中子发射曲线,JoannM.Campbell中子先驱占优裂变产物JEFF3.1采用中子群参数Keepin制作,ENDF/B6、ENDF/B7裂变参数,JEFF3.1,选择JEFF3.114.7MeV数据的相对份额ix ... dofus touch enutrof prospectionWebJENDL 3.2-A-JAERI Cadarache ORIGEN ENDFB/JEF-•-KTH-MCB, JEF-•-KTH - MCB JENDL-O-KTH-MCB ENDFB Days 16 8. EVOLUTION OF THE SPALLATION NEUTRON SOURCE INTENSITY - MAX/BoL Variation of External Source Intensity • keff=0,98 11 keff=0,94 SLTHE ROYAL 1 INSTITUTE OF" TECHNOIOGY 17 SPALLATION … facts about schumannWebThe general purpose file of JENDL-3 contains neutron nuclear data for 324 nuclides in the ENDF-5 format. In the JENDL-3 evaluation, much effort has been devoted to improve … facts about schools in ancient greece