JASPER Experimental data book (VII); Gap streaming Experiment

Takemura, Morio*

JNC TJ9450 2000-002, 112 Pages, 2000/03

JNC-TJ9450-2000-002.pdf:2.55MB

This report is intended to make it easier to apply the measured data obtained from the Gap Streaming Experiment, which was conducted at the Oak Ridge National Laboratory (ORNL) during about two months beginning at the start of March, 1992 as the sixth one of a series of eight experiments planned for the Japanese-American Shielding Program for Experimental Research (JASPER) which was started in 1986. For this reason. the information presented includes specifications and measurement data for all configurations, compositions of all materials, characteristics of the measurement system. and daily-basis records of measurements. The Gap Streaming Experiment was planned to obtain the data of neutron streaming characteristics in the inclosure system above the core of an advanced fast reactor for verification and improvement of the analysis method to be applied to the shielding design. A iron-lined solid or slit concrete assembly was placed, with or without a spectrum modifier forming soft incident neutron spectrum, behind the TSR-II reactor of Tower Shielding Facility. Inserting central cylinders and cylindrical sleeves gave various gap width and offset in the slit concrete assembly. Neutron flux was measured behind the configurations with various types of detectors. The integral neutron flux in wide energy region was measured on radial traverse and on the axis behind the concrete assembly in almost all configurations. Neutron spectrum and fine radial distribution in high energy region was measured further in case of hard incident neutron spectrum, Information presented in this report is based mainly on a report issued by ORNL (ORNL/TM-12140. "Measurements for the JASPER Program Gap Streaming Experiment"). Additional information reported by the assignee is utilized also.

Revise of a basic data base for shielding design

*; Takemura, Morio*

JNC TJ9440 2000-005, 157 Pages, 2000/03

JNC-TJ9440-2000-005.pdf:3.7MB

With use of the two-dimensional discrete ordinates code DORT and the standard groupwise shielding design library JSSTDL produced from the latest evaluated nuclear data library JENDL-3.2, experimental analyses for the representative configurations in the Radial Shield Attenuation Experiment of the JASPER were performed. The results were compared with those obtained with use of traditional method DOT3.5/JSDJ2 for the previous JASPER experimetal analyses. In general, the change of the cross section library gives higher results and the change of the transport code gives lower results. Finally the new analysis method gives better agreement with the experimental results and also less deviations of calculational errors between various detectors. Experimental analyses for the thick concrete configulation in the Gap Streaming Experiment of the JASPER was also performed with the new analysis method, after solving the poor agreement found in last year with the original JASPER experimental analyses. The same tendency due to the library change was confirmed with the above mentioned analyses of the Radial Shield Attenuation Experiment. Compilation of the input data necessary for future reanalyses of important configurations in JASPER experiments were continued through the above-mentioned experimental analyses and related informations were added for repletion of the database preserved in a computer disk holding previously accumulated data. Input data descriptions were made for auxiliary routines needed for the experimental analyses and their sample data were compiled and stored in the database.

Super-Phenix Benchmark used for Comparison of PNC and CEA Calculation Methods,and of JENDL-3.2 and CARNAVAL IV Nuclear Data

Hunter

PNC TN9410 98-015, 81 Pages, 1998/02

PNC-TN9410-98-015.pdf:3.15MB

The study was carried out within the framework of the PNC-CEA collaboration agreement. Data were provided, by CEA, for an experimental loading of a start-up core in Super-Phenix. This data was used at PNC to produce core flux snapshot calculations. CEA undertook a comparison of the PNC results with the equivalent calculations carried out by CEA, and also with experimental measurements from SPX. The resu1ts revealed a systematic radial flux tilt between the calculations and the reactor measurements, with the PNC tilts only 30-401 of those from CEA. CEA carried out an analysis of the component causes of the radial tilt. It was concluded that a major cause of radia1 tilt differences between the PNC and CEA calculations lay in the nuclear datasets used: JENDL-3.2 and CARNAVAL IV. For the final stage of the study, PNC undertook a sensitivity analysis, to examine the detailed differences between the two sets of nuclear data. The PNC flux calculations modelled SPX in both 2D (RZ) and 3D (hex-Z) geometries, using the diffusion programs CITATION and MOSES. The sensitivity analysis of the differences between the JENDL-3.2 and CARNAVAL IV nuclear datasets used the SAGEP calculational route. Both datasets were condensed to a single, non-standard, set of energy group boundaries. There were some incompatibilities in the cross-section formats of the two datasets. The sensitivity analysis showed that a relatively small number of nuclear data items contributed the bulk of the radial tilt difference between calculations with JENDL-3.2 and with CARNAVAL IV. A direct comparison between JENDL-3.2 and CARNAVAL IV data revealed the following. The Nu values showed little difference (<5|%). The only large fission cross-section differences were at low energy (<30% otherwise, with <10% typical). Although down-scattering reactions showed some large fractional differences, absolute differences were negligible compared with in-group scattering; for in-group scattering fractional ...

Improvement of the density limit with an external helical field on JFT-2M tokamak

Tamai, Hiroshi; Shoji, Teruaki; Nagashima, Keisuke; Miura, Yukitoshi; Yamauchi, Toshihiko; Ogawa, Hiroaki; Kawashima, Hisato; Matsuda, Toshiaki; Mori, Masahiro; *; et al.

Journal of Nuclear Materials, 220-222, p.365 - 369, 1995/00

https://doi.org/10.1016/0022-3115(94)00656-3

no abstracts in English

Thickness of EB velocity shear at the plasma edge in the JFT-2M H-mode

Ida, Katsumi*; Miura, Yukitoshi; Ito, Kimitaka; Ito, Sanae*; Fukuyama, Atsushi*; JFT-2M Group

Plasma Physics and Controlled Fusion, 36(7A), p.A279 - A284, 1994/07

https://doi.org/10.1088/0741-3335/36/7A/041

no abstracts in English

Measurement of radial thermal expansivity of carbon fiber

Saito, Tamotsu; Nomura, Shinzo; Imai, Hisashi

Tanso, 146, p.22 - 26, 1991/00

https://doi.org/10.7209/tanso.1991.22

no abstracts in English

User's Manual of the REFLA-1D/MODE4 Reflood Thermo-hydrodynamic Analysis Code : Incorporation of Local Power Effect Model and Fuel Temperature Profile Effect Model into REFLA-1D

; ; ; ; Murao, Yoshio

JAERI-M 85-210, 147 Pages, 1986/01

JAERI-M-85-210.pdf:3.57MB

no abstracts in English

Shielding design in the reactor vessel for the next generation sodium-cooled fast reactor, 2; Improvement of shielding design methods for optimizing radial neutron shieldings

Hibi, Koki*; Fukuchi, Ikuo*; Masuyama, Daisuke*; Sugino, Kazuteru; Oki, Shigeo

no journal, , 

no abstracts in English

Advancement of detailed core bowing analysis code for fast reactor, 4; Overall plan for thermal bowing experiments of simulated subassemblies

Ota, Hirokazu*; Ogata, Takanari*; Kusumi, Koji*; Ohgama, Kazuya; Yamano, Hidemasa; Futagami, Satoshi; Nakagawa, Naoki*; Kawabata, Ryo*; Gima, Hiromichi*; Matsubara, Shinichiro*

no journal, , 

no abstracts in English