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.

JASPER Experimental analyses(lX)

PNC TN9410 95-152, 211 Pages, 1995/05

PNC-TN9410-95-152.pdf:8.21MB

This report describes the results of the JASPER (Japanese-American Shielding Program for Experimental Research) post experiment analysis conducted in JFY 1994. Reviewed items were chosen by considering the past discussions. Series of the JASPER experimental analyses ('86 '94) have been terminated and the review report is being published. Major conclusions of this report are briefly as follows. (Axial Shield Experiment) Monte Carlo code "MORSE" was employed in the analysis of Homogeneous, Rod-bundle and Central blockage configuration, respectively. C/E values of streaming factor are relatively good(0.950.98) for Bonner ball response, while around 20% underestimation is found in Hornyak button response. Good agreement is not always found between MORSE and two-dimensional discrete ordinates code DOT-3.5. (IN-Vessel Fuel Storage Experiment) U.S.-proposed configurations have been reviewed to finish all experimental analyses. These configurations have 1.8m-thick Na layer prior to the IVS mockup, which may soften neutron spectrum. They show almost same C/E values (0.801.01) as the Japan-proposed ones. Analysis accuracy on the IVS mockup is found to be -10+20%. (Intermediate Heat Exchanger Experiment) Three-dimensional discrete ordinates code "TORT" was employed in the analysis of a configuration which shows a complicated neutron flux distribution due to the BC Shield Prior to the sodium region. Various parameters including those for mesh spacing techniques were optimized. There exists around 15% discrepancy between TORT and MORSE, however, it is attributed to the different ways in obtaining input neutron flux.(Gap Streaming Experiment) Basic calculations were conducted in order to investigate a standard for selecting appropriate Sn quardratures sets. In analyzing configuration where neutron streaming is evident, biased setting toward a streaming direction would be useful to evaluate more exact flux distribution. ...

Development of Shielding Design Method for Fast Reactors

Higashi, Kunio*; Shin, Kazuo*

PNC TJ2604 87-001, 31 Pages, 1987/03

PNC-TJ2604-87-001.pdf:0.59MB

no abstracts in English

None

PNC TJ265 83-01, 144 Pages, 1983/03

PNC-TJ265-83-01.pdf:2.67MB

no abstracts in English