Effect of aggregate specification in heavy concrete for fusion reactor shield on neutron dose evaluation
- 1. Osaka Univ., Suita (Japan). Dept. of Nuclear Engineering
Description
Heavy concrete is one of the most powerful, reliable and inexpensive radiation shield materials. It can be applied to a fusion reactor as an effective and strong shield. However, heavy concrete inherently has heterogeneous structure due to the absorber aggregates which can cause heterogeneity effect on the shielding performance. In the present study, the aggregate-specification dependent heterogeneity effect in neutron dose evaluation has been studied for D-T neutron field using measured leakage neutron spectra from heavy concrete samples with D-T neutrons and the analysis results conducted with the Monte Carlo code MCNP-CFP. From the results, the heterogeneity effect of heavy concrete could be observed in the evaluation of neutron dose equivalent. The effect was reproduced accurately by the MCNP-CFP calculation. The ratio of dose for heterogeneous heavy concrete to that of homogeneous one was mostly less than unity, and the effect became large with increase of the packing fraction, shield thickness and aggregate diameter. The reason was that the spatial distribution of the aggregates usually tends to be biased towards the center of the shield. In such a case, MCNP-CFP becomes a powerful tool to give the exact shielding performance. (author)
Availability note (English)
Available from the Internet at URL https://doi.org/10.1080/00223131.2000.10875000Additional details
Identifiers
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of ninth international conference on radiation shielding
- Imprint Pagination
- 906 p.
- Journal Page Range
- p. 798-802
Conference
- Title
- 9. international conference on radiation shielding
- Acronym
- ICRS-9
- Dates
- 17-22 Oct 1999
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51054646
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONCRETES; DOSE EQUIVALENTS; D-T REACTORS; M CODES; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON SPECTRA; NEUTRON TRANSPORT; RADIATION DOSES; RADIATION PROTECTION; SHIELDING; SHIELDING MATERIALS; SHIELDS
- Descriptors DEC
- BUILDING MATERIALS; CALCULATION METHODS; COMPUTER CODES; DOSES; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; RADIATION FLUX; RADIATION TRANSPORT; SIMULATION; SPECTRA; THERMONUCLEAR REACTORS
Optional Information
- Notes
- 6 refs., 9 figs.; This record replaces 32001171 Imprint:Published in Journal of Nuclear Science and Technology, Suppl. 1