Published September 2001 | Version v1
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Fast reactor cooled by supercritical light water

  • 1. Tokyo Univ., Nuclear Engineering Research Lab., Tokai, Ibaraki (Japan)

Description

This report introduces the result of a feasibility study of a fast reactor cooled by supercritical light water (SCFR) with once-through cooling system. It is characterized by (1) no need of steam separator, recirculation system, or steam generator, (2) 1/7 of core flow rate compared with BWR or PWR, (3) high temperature and high pressure permits small turbine and high efficiency exceeding 44%, (4) structure and operation of major components are already experienced by LWRs or thermal power plants. Modification such as reducing blanket fuels and increasing seed fuels are made to achieve highly economic utilization of Pu and high power (2 GWe). The following restrictions were satisfied. (1) Maximum linear heat rate 39 kW/m, (2) Maximum surface temperature of Inconel cladding 620degC, (3) Negative void reactivity coefficient, (4) Fast neutron irradiation rate at the inner surface of pressure vessel less than 2.0x1019 n/cm2. Thus the high power density of 167 MW/m3 including blanket is thought to contributes economy. The high conversion is attained to be 0.99 Pu fission residual rate by the outer radius of fuel rod of 0.88 mm. The breeding of 1.034 by Pu fission residual rate can be achieved by using briquette (tube-in-shell) type fuel structure. (K. Tsuchihashi)

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Part of:
Summary of the 4th workshop on the reduced-moderation water reactor

Additional details

Publishing Information

Imprint Title
Summary of the 4th workshop on the reduced-moderation water reactor
Imprint Pagination
271 p.
Journal Page Range
p. 63-75, 189-205
Report number
JAERI-Conf--2001-013

Conference

Title
4. workshop on the reduced-moderation water reactor
Dates
2 Mar 2001
Place
Tokai, Ibaraki (Japan)

Optional Information

Notes
8 refs., 7 figs., 5 tabs.; This record replaces 33023492