Civil Engineering Design for Decommissioning of Nuclear by A.A. Paton, P. Benwell, T.F. Irwin, I. Hunter

By A.A. Paton, P. Benwell, T.F. Irwin, I. Hunter

35 9.2 average PWR Station structure 36 9.3 areas of maximum Radiological threat 38 9.4 Decommissioning situations forty 9.5 present Structural positive factors of a PWR that can relief Decommissioning forty two 9.6 Structural beneficial properties that may be brought into destiny PWR Stations to assist Decommissioning forty three 10. REFERENCES forty four eleven. ACKNOWLEDGEMENTS forty five 12. TABLES AND FIGURES forty five APPENDIX A - SUPPLEMENTARY details ninety eight 1 1. creation 1.1 This document describes the paintings conducted via Taylor Woodrow building constrained (!WC) in a examine aimed toward opting for positive factors that could be included on the layout level of destiny nuclear energy vegetation to facilitate their eventual decommissioning and, in so dOing, advertise financial and radiological advantages on the decommissioning level. 1.2 For the needs of this examine, decommissioning of a nuclear facility ability these measures taken on the finish of the facility's working lifestyles to take away it from the location and restoration the positioning to eco-friendly box stipulations, and, whereas so doing, make sure the persisted safeguard of the general public from any residual radioactivity or different strength risks found in or emanating from the power. the final decommissioning method comprises eventual dismantling and demolition and should additionally comprise, the place attainable and acceptable, the intermediate steps of renewal and refurbishing.

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This scheme has the advantages of buried, and therefore, protected insulation. The insulation debonds the grout and could be considered in conjunction wi th the planes of weakness philosophy. The major disadvantage is the effect of high temperature directly on the liner. 1 The need to protect the inner layer of concrete of a PCRV from the excessive heat generated by the reactor core has led to the development of a highly efficient but very intricate insulating system. The use of stainless steel and the welded fabrication of such a system complicates the decommissioning of a liner in active areas.

M. The Control of Cobalt Content in Reactor Grade Steels. European Applied Research Reports Vol. 2, 1983. 6. NEMET, J. and FRITZ, K. Concept, Construction, Testing and Operational Safety of a PCPV with Elastic Hot Liner and Adjustable Wall Temperature. Proc. of 5th International Conference on Structural Mechanics in Reactor Technology. Berlin, August 1979. 7. WOOLLAM, P. B. G. Neutron Induced Activation, Waste Disposal and Radiation Levels for the Reactor Island Structure of a Decommissioned Magnox Power Station.

The remaining principal components of the NSSS are the reactor coolant pumps (Rep), the steam generators (SG) and the pressuriser. 1 As with the AGR, when considering PWR decommissioning, there are three major sources of radiological hazard, namely, radioactive source materials, activated materials and contaminated materials. In the PWR these hazards can be identified as follows: (a) Radioactive Source Materials These consist of the fuel assemblies which must be removed from the reactor via the existing fuel handling route before any decommissioning work can begin, after the reactor has been brought to a normal cold shutdown condition.

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