Safety_Series_041_1975 - gnssn - International Atomic Energy ...

More documents

Recommendations

Info

This publication is no longer valid Please see http://www.ns-iaea.org/standards/ 7 8 APPENDIX IV It must be emphasized that observance of the 'dose limits' is not enough to ensure adequate radiological protection. The ICRP recommends that the competent authority should limit releases to the environment to values below the 'radiological capacity' (i. e. to that release which corresponds to the dose limits). This derives from the concept of 'as low as is reasonably possible' (ICRP No. 22) and also allows for further installations, which should not be penalized as to their protection costs. It is thus possible to define a protection factor P = authorized release/radiological capacity, which must also be taken into account in monitoring. The working limits multiplied by this factor, DWL XP, are called Authorized Working Limits (AWL). Environmental monitoring should show that these AWL values are being observed. COMMISSION OF THE EUROPEAN COMMUNITIES Environmental monitoring programme of the Ispra Establishment 1. Radioactive effluents of the Ispra Establishment The Ispra Establishment of the Joint Research Center of the European Communities covers an area of about 1.5 km and includes few large installations and several laboratories (see Fig. 7). The main facilities are three nuclear reactors (Ispra-1, ECO and ESSOR), a hot laboratory for metallurgical studies of irradiated materials (LMA) and radiochemistry and radiobiology laboratories. The operation of these installations involves the production of radioactive wastes, part of which is released into the environment directly (gaseous effluents) or after decontamination treatment (liquid effluents). The solid wastes deriving from the latter process as well as from other operations are sealed into suitable containers (tar or concrete) and stored on the soil or buried into pits filled with concrete. The radioactive liquid effluents produced at the various facilities are sent to a treatment station, where they undergo a decontamination process and then are released into the sewer system of the Establishment. The volume of these effluents fluctuates around 2000 m3/a and the overall activity ranges from a few tens to a few hundreds of mCi/a, mainly due to 137 Cs, 60Co and 90Sr. The discharge is not continuous and consists of 20 to 40 single release operations per year.
This publication is no longer valid Please see http://www.ns-iaea.org/standards/ A PPEN D IX IV 79 FIG. 7. M ap o f th e Jo in t Research C e n ter Ispra Establishm ent (Ita ly ). Most of the activity of the gaseous effluents is due to 41A r, which is released from the stacks of the Isp ra -1 reactor and of the ESSOR reactor (~ 10 000 C i/a each). Both installations release also some hundreds of C i/a of tritium. The m etallurgical laboratory (LMA), 131 which is planned to operate in the future, will release I (order of magnitude 100 m C i/a) and 85Kr (negligible activity).
Page 1 and 2:
This publication is no longer valid
Page 3 and 4:
Page 5 and 6:
Page 7 and 8:
Page 9 and 10:
Page 11 and 12:
Page 13 and 14:
Page 15 and 16:
Page 17 and 18:
Page 19 and 20:
Page 21 and 22:
Page 23 and 24:
Page 25 and 26:
Page 27 and 28:
Page 29 and 30:
Page 31 and 32:
Page 33 and 34:
Page 35 and 36:
Page 37 and 38:
Page 39 and 40:
Page 41 and 42: This publication is no longer valid
Page 59 and 60: 1M|137CJ g 1 litre 134Cs C 3 .5 lit
Page 91: This publication is no longer valid
Page 101 and 102: T A B L E X V I (con t.) This publi
Page 109 and 110: T A B L E X V III (con t.) This pub
Page 113 and 114: T A B L E X X (con t.) This publica
Page 143 and 144:
Page 145 and 146:
Page 147 and 148:
show all

Safety_Series_041_1975 - gnssn - International Atomic Energy ...

Create successful ePaper yourself

Delete template?

Save as template?