Title of article :
Nuclear heating measurements for SS-316, copper, graphite, tungsten, chromium, beryllium in a copper centered assembly bombarded with 14 MeV neutrons and analysis
Author/Authors :
Ikeda، نويسنده , , Y. and Maekawa، نويسنده , , F. and Wada، نويسنده , , M. and Kasugai، نويسنده , , Y. and Konno، نويسنده , , C. and Uno، نويسنده , , Y. and Kumar، نويسنده , , A. and Youssef، نويسنده , , M.Z. and Abdou، نويسنده , , M.A.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 1998
Pages :
9
From page :
289
To page :
297
Abstract :
Under ITER/EDA R&D Task T-218, an experiment on nuclear heating was conducted at the Fusion Neutronics Source Facility (FNS) in JAERI in order to provide experimental data of nuclear heating for structural materials and to validate the data and methods relevant to ITER design calculations. Probe materials, SS-316, Cu, W, Zr, Be, Cr and graphite were tested in a copper centered experimental assembly bombarded with 14 MeV neutrons. A calorimetric method and TLDs were employed for total heating and γ-heating measurements, respectively. The measurements were carried out along a central axis of a copper centered experimental assembly. The total heating rate in the probe material was derived from a temperature rise measured by a thermistor attached to the probe. MCNP4A with JENDL-3.2, JENDL-Fusion File and FENDL-1 libraries were used for experimental analyses. Nuclear heating was derived with the use of KERMA factors based on JENDL-3.2 and FENDL-1. The adequacy of the KERMA data is discussed based on nuclear heating ratios of calculation to experiment (C/E).
Journal title :
Fusion Engineering and Design
Serial Year :
1998
Journal title :
Fusion Engineering and Design
Record number :
2350234
Link To Document :
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