2024 Jendl 3

Jendl 3

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August undefined, 2024

WebJENDL-3: The data in the MeV region were modified. The data of important heavy nuclides were evaluated with the simultaneous evaluation. The γ-ray production data were given … Web1 dic 2002 · Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various. benchmark tests of the previous library JENDL-3.2. …

Integral Test of JENDL-3.3 with Shielding Benchmarks

Web12 apr 2024 · About Press Copyright Contact us Creators Advertise Developers Terms Privacy Policy & Safety How YouTube works Test new features NFL Sunday Ticket Press Copyright ... Web10 apr 2024 · Graphs of cross sections stored in JENDL-3.3 Cross section and ν-bar plotting tool Available to select nuclides and reaction types, fix axes, plot one or more data, and … sanffe.info

[0905.2086] Calculations of Maxwellian-averaged Cross Sections …

Web摘要：中子学积分实验是检验评价中子核数据库质量的一种重要手段,是核数据库建设工作的一项重要内容.国际上已开展了大量的积分实验,对数据库更新起到了重要作用,国内此方面的工作开展较少.铁是核装置的重要结构材料,其快中子截面数据的精确度对新型核装置设计具有重要意义.本论文采用板 ... Web1 mar 1994 · The calculations using JENDL-3 show overall agreement with the experimental data as well as those with ENDF/B-IV. Particularly, JENDL-3 gives better results than … WebJENDL-3.3. NOTICE: The users are requested to cite the No.1 of the papers given below for referencing JENDL-3.3. Summary of JENDL-3.3. Purpose. To provide a Japanese standard library for fast breeder reactors, thermal reactors, fusion neutronics and shielding calculations, and other applications. Number of nuclides. san fe texas shooting

ZZ ORIGEN2.2-UPJ, A complete package of ORIGEN2 libraries …

Analyses of Criticality and Reactivity for TRACY Experiments Based …

Web2. 2. 1 Benchmark Tests of JENDL-3. 2 for Thermal and Fast Reactors Hideki Takano Japan Atomic Energy Research Institute Tokai, Ibaraki, 319-11, Japan +81-292-82-6151 … Webthere is no clear difference between both integrated fast fluxes of JENDL-3 and ENDF/B-V and the result of JENDL-3 below 0.1 MeV is about 20 % smaller around 5 x 10 "3 MeV and about 20% smaller around 2x 10 A MeV than that of ENDF/B-V The reason for the latter is the sensitivity of 59 Co ( n, y ) ^ Co reaction rate again, as can be seen in Fig. 4. sanfew rs3 in taverlyWeb• 2002, JENDL-3.3 (337) with 209 PT’s in the URR (+ JEFF-3.1/Th) • International Handbook of Evaluated Criticality Benchmarks Experiment, ICSBEP September 2006 edition • Run … shortcut open new tab

"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. " - Jendl 3

Jendl 3

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 … Web1 - Description: ORLIBJ32 is a package of the libraries for ORIGEN2 code based on JENDL-3.2(NEA-1642). The one grouped cross section data for PWR and BWR were compiled …

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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: Web2. 2. 1 Benchmark Tests of JENDL-3. 2 for Thermal and Fast Reactors Hideki Takano Japan Atomic Energy Research Institute Tokai, Ibaraki, 319-11, Japan +81-292-82-6151 Benchmark calculations for a variety of thermal and fast reactors have been performed by using the newly evaluated JENDL-3 Version-2 (JENDL-3.2) file. In the thermal reactor

WebThe 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 … Web27 ago 2014 · Calculations with JENDL-3.2, ENDF/B-VI, FENDL-1 and FENDL-2 were also made for comparison. In the present study, benchmark results of neutron and gamma …

Web31 dic 1994 · @article{osti_62121, title = {Testing of BROND-2, JENDL-3, and ENDF/B-VI neutron data through integral experiments using ABBN-90 constant system}, author = {Manturov, G and Nikolaev, M N and Semyonov, M Yu and Tsiboulia, A M}, abstractNote = {Group constants calculated from evaluated data adopted in different libraries were used … 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 …

Web10 apr 2024 · Summary of JENDL-3.2. Purpose. To provide a Japanese standard library for fast breeder reactors, thermal reactors, fusion neutronics and shielding calculations. Number of nuclides. 340. Incident neutron energy range. 10 …

Web被引用回数：0 パーセンタイル：0.32(Physics, Nuclear) 原子核の変形並びに回転や振動を記述する軟回転体模型を構築し、チャンネル結合法に基づいて核構造の情報を光学模型に取り入れたことは故Soukhovitsukii博士の偉大な成果である。 sanfer sports cars miami fl 33166Web30 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. shortcut open in new tab edgeWebJENDL 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 … sanfew potionWebcompiled from the BROND-2, ENDF/B-VI and JENDL-3 data files [41 . It includes neutron interaction and photon production cross-section data. The second version of the generat purpese file of the European Fusion File, EFF-2, had been developed in the framewerk of sanffe info loginWebJSSTDL-300 [3], a common multigroup library of neutron 300 groups and gamma 104 groupsfor shielding applications produced from JENDL-3.2 [4] with the PROF-GROUCH-G/B [5] code byJapanese Nuclear Data Committee, is widely applied in Japan. However, the self-shielding correction inJSSTDL-300 is probably inadequate due to the following two … sanffs.info loginWeb27 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. sanffe.info loginWeb29 mar 2024 · Dear Norbert, you could try the JENDL HE library and see if that changes something. However, looking at your output file I’ve noticed that you used 181Ta.80c in the [Material] section. Typically nuclear data library extensions ending in .XXc designate libraries for neutron transport, not for proton reactions. But since you are interested in (p,n) … sanffs.info