Published May 2021 | Version v1
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Evaluation of radioactivity concentration corresponding to dose criterion for near surface disposal of radioactive waste generated from research, medical, and industrial facilities. Volume 1

Creators

  • 1. Japan Atomic Energy Agency, Decommissioning and Radioactive Waste Management Head Office, Radioactive Wastes Disposal Center, Tokai, Ibaraki (Japan)
  • 2. Inspection Development Company Ltd., Tokai, Ibaraki (Japan)

Description

JAEA has aims to carry out near surface disposal of low-level radioactive waste generated from research, medical, and industrial facilities. Therefore, radioactivity concentration corresponding to dose criteria of near surface disposal for 220 nuclides in the waste were calculated for the purpose of discussion for radioactivity limits between trench and concrete vault disposal, and key nuclides related to them. We calculated the radioactivity concentrations with consideration of not only the exposure pathways used at calculation of the radioactivity concentration limits of waste packages for near surface disposal by Nuclear Safety Commission but also ones used at the concentration limits for intermediate depth disposal. We also assumed the capacities of the disposal facilities as 44,000 m3 for pit disposal and 150,000 m3 for trench disposal. The radioactivity concentrations calculated in this report is used as the reference values because the disposal site has not been decided yet. Addition to this, the radioactivity concentrations will be revised according to circumstances of development of disposal facilities and so on. In the future, we will decide the radioactivity and radioactive concentration of a waste package described in the license application documents based on the dose assessment taken into consideration the disposal site conditions. (author)

Availability note (English)

Also available from JAEA; DOI: https://doi.org/10.11484/jaea-technology-2021-004

Abstract (Japanese)

研究施設等廃棄物の埋設処分に向けて、廃棄体等のトレンチ処分及びピット処分への区分や、重要核種を選定する際の参照値とするため、研究施設等廃棄物に含まれる可能性のある220核種について、トレンチ処分及びピット処分における基準線量相当濃度を試算した。基準線量相当濃度の試算に当たっては、廃棄物埋設施設の立地場所は様々な環境が考えられるため、原子力安全委員会がトレンチ処分及びピット処分の濃度上限値を算出するために用いられた被ばく経路に追加して、中深度処分で想定されている被ばく経路も追加した。また、埋設処分場の規模を、現在想定しているトレンチ処分約53万本、ピット処分約22万本を対象として設定した。本報告書で試算した基準線量相当濃度の結果は、立地場所が決定していない段階での廃棄体等のトレンチ処分及びピット処分への区分や、重要核種を選定する際の参照値として用いることを考えている。また、今後の処分施設のバリア機能の設置などの検討を考慮して、基準線量相当濃度の値を見直すこととする。なお、今後、立地場所の決定後、立地条件を踏まえて線量評価を行い、事業許可申請書に記載する廃棄体等の放射能及び放射能濃度を決定することとなる。(著者)

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Additional details

Additional titles

Original title (Japanese)
研究施設等廃棄物の浅地中処分のための基準線量相当濃度の検討.その1

Identifiers

DOI
10.11484/jaea-technology-2021-004;

Publishing Information

Imprint Pagination
81 p.
Report number
JAEA-Technology--2021-004

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
53075043
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Descriptors DEI
C CODES; DECOMMISSIONING; DOSE LIMITS; GROUND DISPOSAL; INVENTORIES; LOW-LEVEL RADIOACTIVE WASTES; PERMEABILITY; RADIATION DOSES; RADIATION PROTECTION; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVITY; RADIOISOTOPES; RADIONUCLIDE MIGRATION; SAFETY ANALYSIS; SITE SELECTION
Descriptors DEC
COMPUTER CODES; DOSES; ENVIRONMENTAL TRANSPORT; ISOTOPES; MANAGEMENT; MASS TRANSFER; MATERIALS; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; REACTOR LIFE CYCLE; SAFETY STANDARDS; STANDARDS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES

Optional Information

Notes
13 refs., 6 figs., 12 tabs.