Maxwellian-averaged neutron-induced reaction cross sections and astrophysical reaction rates for = 1 keV to 1 MeV calculated from microscopic neutron cross section library JENDL-3.3

Nakagawa, Tsuneo; Chiba, Satoshi; Hayakawa, Takehito; Kajino, Toshitaka*

Atomic Data and Nuclear Data Tables, 91(2), p.77 - 186, 2005/11

https://doi.org/10.1016/j.adt.2005.08.002

no abstracts in English

Analyse on the BFS critical experiments; An analysis on the BFS-62-1 assembly

Sugino, Kazuteru; Iwai, Takehiko*;

JNC TN9400 2000-098, 182 Pages, 2000/07

JNC-TN9400-2000-098.pdf:5.74MB

In order to support the Russian excess weapons plutonium disposition, the international collaboration has been started between Japan Nuclear Cycle Development Institute (JNC) and Russian Institute of Physics and Power Engineering (IPPE). In the frame of the collaboration, JNC has carried out analyses on the BFS-62 assemblies that are constructed in the fast reactor critical experimental facility BFS-2 of IPPE. This report summarizes an experimental analysis on the BFS-62-1 assembly, which is the first core of the BFS-62 series. The core contains the enriched U0 fuel surrounded by the U0 blanket. The standard analytical method for fast reactors has been applied, which was used for the JUPITER and other experimental analyses. Due to the lack of the analytical data the 2D RZ core calculation was mainly used. The 3D XYZ core calculation was applied only for the preliminary evaluation. Further in terms of the utilization of the BFS experimental analysis data for the standard data base for FBR core design, consistency evaluation with JUPITER experimental analysis data has been performed using the cross-section adjustment method. As the result of analyses, good agreement was obtained between calculations and experiments for the criticality and the reaction rate ratio. However, it was found that accurate evaluation of the reaction rate distribution was impossible without exact consideration of the arrangement of the two types of sodium (with and without hydrogen impurity), which can be accommodated by the 3D core analysis, thus it was essentia1. In addition, it was clarifie that there was a room for an improvement of the result on the reaction rate distribution in the blanket and shielding regions. The application of the 3D core calculation improved the result on the control rod worth because 3D core model can more exactly consider the shape of the control rod. Furthermore it was judged that the result of the analysis on the sodium void reactivity .....

Measurement of activation reaction rate distributions in a lead assembly bombarded with 500-MeV protons

Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Tsujimoto, Kazufumi; Yasuda, Hideshi

Nuclear Science and Engineering, 135(1), p.23 - 32, 2000/05

https://doi.org/10.13182/NSE00-A2121

no abstracts in English

Development of a standard data base for FBR core nuclear design, 12; Analysis of FCA X-1 experiments and consistency evaluation using cross-section adjustment

Yokoyama, Kenji*; Numata, Kazuyuki*; Ishikawa, Makoto*; Oigawa, Hiroyuki; Iijima, Susumu

JNC-TY9400 2000-006, 168 Pages, 2000/04

no abstracts in English

Measurement of neutron capture cross sections of Tc-99

*

JNC TJ9400 2000-008, 61 Pages, 2000/02

JNC-TJ9400-2000-008.pdf:2.5MB

For studies on nuclear transmutation of long-lived fission products (LLFPs) in a fast reactor, detailed characteristics of reactor core such as transmutation performance have to be investigated, so accurate neutron cross section data of LLFPs become necessary. Therefore, the keV-neutron capture cross sections of Tc-99, which is one of important LLFPs, were measured in the present study to obtain the accurate data. The measurement was relative to the standard capture cross sections of Au-197. A neutron time-of-flight method was adopted with a ns-pulsed neutron source by a Pelletron accelerator and a large anti-Compton NaI(TI) gamma-ray detector. As a result, the capture cross sections of Tc-99 were obtained with the error of about 5 % in the incident neutlon energy region of 10 to 600 keV. The present data were compared with other experimental data and the evaluated values of JENDL-3.2, and it was found that the evaluations of JENDL-3.2 were 15-20 % smaller than the present measurements.

A Proposal of benchmark calculation on reactor physics for metallic fueled and MOX fueled LMFBR based upon mock-up experiment at FCA

Oigawa, Hiroyuki; Iijima, Susumu; Sakurai, Takeshi; Okajima, Shigeaki; Ando, Masaki; Nemoto, Tatsuo; Kato, Yuichi*; Osugi, Toshitaka

Journal of Nuclear Science and Technology, 37(2), p.186 - 201, 2000/02

https://doi.org/10.3327/jnst.37.186

no abstracts in English

Analysis of measurements for a Uranium-free core experiment at the BFS-2 critical assembly

Hunter

JNC TN9400 99-049, 74 Pages, 1999/04

JNC-TN9400-99-049.pdf:2.03MB

This document describes a series of calculations that were carried out to model various measurements from the BFS-58-1-I1 experiment. BFS-58-1-I1 was a mock-up of a uranium-free, Pu burning core at BFS-2, a Russian critical assembly operated by IPPE. The experiment measured values of keff, Na void reactivity worth, material sample reactivity worths and reaction rate ratios. The experiments were modelled using a number of different methods. Basic nuclear data was taken from JENDL-3.2, in either 70 or 18 groups. Cross-section data for the various material regions of the assembly were calculated by either SLAROM or CASUP; the heterogeneous structure of the core regions was modelled in these calculations, with 3 different options considered for representing the (essentially 2d) geometry of the assembly components in a 1D cell model. Whole reactor calculations of flux and keff were done using both a diffusion model (CITATION) and a transport model (TWOTRAN2), both using an RZ geometry. Reactivity worths were calculated both directly from differences in keff values and by using the exact perturbation calculations of PERKY and SN-PERT (for CITATION and TWOTRAN2, respectively). Initial calculations included a number of inaccuracies in the assembly representation, a result of communication difficulties between JNC and IPPE; these errors were removed for the final calculations that are presented. Calculations for the experiments have also been carried out in Russia (IPPE) and France (CEA) as part of an international comparison exercise, some of those results are also presented here. The calculated value of keff was 1.1%k/k higher than the measured value, Na void worth C/E values were 1.06; these results were considered to be reasonable. (Discrepancies in certain Na void values were probably due to experimental causes, though the efect should be investigated in any future experiments.) several sample worth values were small compared with calculational uncertaint

Reaction rate distribution measurement and analysis for 0.895 and 1.21GeV proton bombardment on thick tungsten target

Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Fukahori, Tokio; Sakamoto, Yukio; Yoshizawa, Nobuaki*; Furihata, Shiori*; V.I.Belyakov-Bodin*; G.I.Krupny*

Proc. of 3rd Workshop on Simulating Accelerator Radiation Environments (SARE3), p.255 - 263, 1997/00

no abstracts in English

Analysis of reaction rate distributions on a thick tungsten target bombarded with protons of 0.8 to 1.2GeV

Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Fukahori, Tokio; V.I.Belyakov-Bodin*; G.I.Krupny*; Yu.E.Titarenko*

Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.323 - 333, 1997/00

no abstracts in English

Shielding experiments with quasi-monoenergetic neutrons between 15 and 90 MeV at 90 MV AVF cyclotron facility TIARA

Sakamoto, Yukio; ; Nakane, Yoshihiro; Tanaka, Shunichi; Tanaka, Susumu; Nakamura, Takashi*; Baba, Mamoru*; *; Shin, Kazuo*

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.809 - 815, 1994/00

no abstracts in English