A proposed regulation would limit the release of 1291 to the environment to 0.005 Ci/GWe-yr of nuclear power produced. This corresponds to an overall 129 1 retention factor of about 250 for the LWR fuel cycle. Technologies available and under development for removing iodine from offgas and waste water streams in an LWR nuclear fuel reprocessing plant and for converting iodine to stable forms and retaining it for interim and long-term storage, transportation and isolation are discussed. Possible developments are reviewed. Technologies available for retaining iodine from off-gas and excess water streams appear adequate, when properly combined, to meet the proposed regulation in an LWR fuel reprocessing plant, though additional work on solid sorbents is needed. Demonstrations under plant conditions are needed to define and resolve problems not met in laboratory experiments and to define practical operating conditions. Criteria for storage and disposal forms for retained iodine are needed to guide effective development of such forms. Because no disposal form for 129r is likely to survive in any environment for even one half-life (1.6 x 10 7 yr), work on a disposal form should seek forms that disintegrate as slowly as possible to maximize dilution before the isotope reaches the biosphere. iii SUMMARY INTRODUCTION BACKGROUND. CONTENTS REMOVAL OF IODINE FROM OFF-GAS STREAMS. MERCURE X PROCESS [Hg(N0 3)2-HN0 3 J SCRUBBING IODOX PROCESS FOR IODINE RETENTION SOLID SORBENTS FOR IODINE REMOVAL Silver-Doped Gels and Oxides. Metal-Exchanged Zeolite Sorbents SUMMARY OF IODINE RETENTION TECHNOLOGY REMOVAL OF IODINE FROM EXCESS WATER. RETENTION OF IODINE BY SOLID SORBENTS. PREVENTING IODINE •VOLATILIZATION DURING ~~ATER EVAPORATION .
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