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A simplified method to estimate beryllium burn up in breeder blankets of a fusion reactor and its impact on a tritium breeding

Abstract

The integral-differential equation of neutron balance for the beryllium burn up in breeder blankets of a fusion reactor is written and solved analytically to estimate the beryllium depletion in blankets having the beryllium as neutron multiplier. The beryllium depletion in the first and the second beryllium layers behind the first wall of a Japanese layered pebble bed blanket proposed for the ITER breeding blanket is estimated to be about 9% and 6.5% after the 3 MW {center_dot} a/m{sup 2} fluence of 14-MeV neutrons on the first wall, respectively. The corresponding decrease of local tritium breeding ratio at the toroidal midplane was calculated to be barely less than 0.5%. The beryllium depletion in the breeder blanket of a DEMO fusion reactor is expected to be by 3 to 7 times larger than that for the ITER design, subject to the blanket design, the neutron fluence, etc. This beryllium depletion may decrease the tritium breeding ratio well below 1%, the margin above which the subject is to be addressed seriously. (author).
Authors:
Zimin, S [1] 
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
Dec 01, 1993
Product Type:
Technical Report
Report Number:
JAERI-M-93-245
Reference Number:
SCA: 700420; PA: JPN-94:003277; EDB-94:078727; ERA-19:020453; NTS-95:006004; SN: 94001202320
Resource Relation:
Other Information: PBD: Dec 1993
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; BREEDING BLANKETS; TRITIUM; TRITIUM RECOVERY; BERYLLIUM; FAST NEUTRONS; NUMERICAL SOLUTION; DAMAGING NEUTRON FLUENCE; 700420; PLASMA-FACING COMPONENTS
OSTI ID:
10149401
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE94765547; TRN: JP9403277
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
23 p.
Announcement Date:
Jul 05, 2005

Citation Formats

Zimin, S. A simplified method to estimate beryllium burn up in breeder blankets of a fusion reactor and its impact on a tritium breeding. Japan: N. p., 1993. Web.
Zimin, S. A simplified method to estimate beryllium burn up in breeder blankets of a fusion reactor and its impact on a tritium breeding. Japan.
Zimin, S. 1993. "A simplified method to estimate beryllium burn up in breeder blankets of a fusion reactor and its impact on a tritium breeding." Japan.
@misc{etde_10149401,
title = {A simplified method to estimate beryllium burn up in breeder blankets of a fusion reactor and its impact on a tritium breeding}
author = {Zimin, S}
abstractNote = {The integral-differential equation of neutron balance for the beryllium burn up in breeder blankets of a fusion reactor is written and solved analytically to estimate the beryllium depletion in blankets having the beryllium as neutron multiplier. The beryllium depletion in the first and the second beryllium layers behind the first wall of a Japanese layered pebble bed blanket proposed for the ITER breeding blanket is estimated to be about 9% and 6.5% after the 3 MW {center_dot} a/m{sup 2} fluence of 14-MeV neutrons on the first wall, respectively. The corresponding decrease of local tritium breeding ratio at the toroidal midplane was calculated to be barely less than 0.5%. The beryllium depletion in the breeder blanket of a DEMO fusion reactor is expected to be by 3 to 7 times larger than that for the ITER design, subject to the blanket design, the neutron fluence, etc. This beryllium depletion may decrease the tritium breeding ratio well below 1%, the margin above which the subject is to be addressed seriously. (author).}
place = {Japan}
year = {1993}
month = {Dec}
}