JP2022541774A - 放射性廃棄物の放射性核種含有量監視方法 - Google Patents
放射性廃棄物の放射性核種含有量監視方法 Download PDFInfo
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- 238000000034 method Methods 0.000 title claims abstract description 54
- 238000012544 monitoring process Methods 0.000 title claims abstract description 20
- 239000002901 radioactive waste Substances 0.000 title abstract description 31
- 230000000694 effects Effects 0.000 claims abstract description 55
- 238000005259 measurement Methods 0.000 claims abstract description 37
- 239000013598 vector Substances 0.000 claims abstract description 26
- 239000007788 liquid Substances 0.000 claims abstract description 15
- 238000012360 testing method Methods 0.000 claims abstract description 10
- 230000005251 gamma ray Effects 0.000 claims abstract description 9
- 230000004913 activation Effects 0.000 claims abstract description 8
- 239000002826 coolant Substances 0.000 claims abstract description 8
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- 238000012512 characterization method Methods 0.000 claims description 14
- 238000001730 gamma-ray spectroscopy Methods 0.000 claims description 9
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- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 5
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- 229910000831 Steel Inorganic materials 0.000 claims description 3
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- 238000010248 power generation Methods 0.000 description 5
- 238000013459 approach Methods 0.000 description 3
- 239000000203 mixture Substances 0.000 description 3
- 230000005255 beta decay Effects 0.000 description 2
- 238000004364 calculation method Methods 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 238000000084 gamma-ray spectrum Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000000611 regression analysis Methods 0.000 description 2
- 238000001228 spectrum Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000002940 Newton-Raphson method Methods 0.000 description 1
- 230000005262 alpha decay Effects 0.000 description 1
- 230000005250 beta ray Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010219 correlation analysis Methods 0.000 description 1
- 238000002790 cross-validation Methods 0.000 description 1
- 230000001066 destructive effect Effects 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000005253 gamme decay Effects 0.000 description 1
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- 239000010850 non-combustible waste Substances 0.000 description 1
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- G—PHYSICS
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- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/167—Measuring radioactive content of objects, e.g. contamination
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/36—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
- G01T1/362—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry with scintillation detectors
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
Description
液体鉛冷却器を備えた高速炉の運転中、RAWの放射性核種含有量の電流監視は、核種ベクトル法を用いたルーチン特性評価段階で実施される。このメインステージの前には、ルーチン特性評価ステージを正当化し準備するために、RAWの流れや核種ベクトルパラメータの特定を含む一連の予備調査を行う準備ステージがある。
u_(K_(i,k) )=√(u_(A_(i,k))^2+u_(A_(r,k))^2 ) k番目のサンプルにおけるi番目の放射性核種の計算された比率の相対標準不確かさ、 u_(A_(i,k) )、u_(A_(r,k) ) - k番目のサンプルにおけるi番目のHD-RNと基準放射性核種の比放射能の相対的な標準不確かさで、測定値の重み付けとして使用される。
Claims (4)
- 流れの中のRAWを日常的に特性評価する後続段階では、流れの中の核種ベクトルを定めるためのテストサンプルを作成するためにサンプルが採取され、テストサンプル中の放射性核種の比放射能はガンマ線を伴って崩壊し、ガンマ・スペクトロメトリ分析を用いて定められる。基準放射性核種と対象となる難検出性放射性核種(HD-RN)を選択し、それらの比放射能と基準放射性核種の放射能に対する比放射能の標準不確かさを決定し、RAWの特性評価の段階では、RAW中の基準放射性核種のみの比放射能をガンマスペクトロメトリによる非破壊測定で測定し、準備段階で得られた特定された核種ベクトルの特性に基づいて、RAWの流れの中のターゲットHD-RNの放射能を計算するが、その際、鉛冷却材の放射化生成物207Biを参照放射性核種として使用し、その比放射能を0.662keV線に沿って8%以上の解像度でガンマ線スペクトロメトリ複合体を用いて測定し、 662keV線に沿って8%以上の解像度でガンマ線スペクトル複合体を用いてその比放射能を測定し、アルファ線とベータ線を伴う崩壊をする210Pb、202Pb、205Pbを核種ベクトルのターゲットリスト(HD-RN)に含め、液体シンチレーション分光計を用いてその比放射能を測定し、テストサンプル中のガンマ線放出核種の比放射能に関するデータを液体シンチレーション分光計の測定値の処理に使用する一方、処理は,一般化された最小二乗法を用いて行われ,測定値の重みとして基準放射性核種の比放射能の測定の不確かさ値とHD-RNを同時に考慮することを特徴とする液体鉛冷却器を備えた高速炉の使用済み核燃料(NSF)を処理する際に生成されるRAWの放射性核種含有量を監視する方法であって、RAWの流れを特定し、その核種ベクトルを定める準備段階を含む方法。
- ガンマ分光計を用いて基準放射性核種207Biの比放射能を測定する際に、569.7keVおよび1063.7keVのガンマ放射線エネルギーに相当するする2つの完全吸収ピークにおけるパルスカウントレートの測定を特徴とする、請求項1に記載の方法。
- 基準放射性核種として60Соを使用して、構造用鋼55Fe、59Ni、63Niの放射化生成物の含有量を追加で監視することを特徴としており、その結果、基準放射性核種の比放射能の測定の不確かさ値と、測定値の重みとしてのHD-RNを同時に考慮した一般化された最小二乗法を用いて処理されること特徴とする、請求項1に記載の方法。
- 核燃料90Sr; 99Тс; 93Мо, 129I, 135Csの分裂生成物の含有量を、娘137mВаまたは137Cs (137mВа)の137Csを基準放射性核種として用いて監視することを特徴としており、その結果は、基準放射性核種の比放射能の測定の不確かさの値と、HD-RNを測定値の重みとして同時に考慮した一般化された最小二乗法を用いて処理されること特徴とする、請求項1に記載の方法。
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RU2019122722 | 2019-07-15 | ||
RU2019122722A RU2722203C1 (ru) | 2019-07-15 | 2019-07-15 | Способ контроля содержания радионуклидов в радиоактивных отходах |
PCT/RU2020/000329 WO2021010864A1 (ru) | 2019-07-15 | 2020-07-03 | Способ контроля содержания радионуклидов в радиоактивных отходах |
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JP2022541774A true JP2022541774A (ja) | 2022-09-27 |
JP7383114B2 JP7383114B2 (ja) | 2023-11-17 |
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EP (1) | EP4036608B1 (ja) |
JP (1) | JP7383114B2 (ja) |
CN (1) | CN114127584A (ja) |
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WO (1) | WO2021010864A1 (ja) |
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CN111896990B (zh) * | 2020-07-10 | 2023-01-24 | 成都理工大学 | 一种基于Frechet距离的放射源活度监测方法 |
RU2753380C1 (ru) * | 2020-10-13 | 2021-08-13 | Федеральное государственное унитарное предприятие "Научно-исследовательский технологический институт имени А.П. Александрова" | Способ определения объемной активности радионуклидов продуктов деления и активированных продуктов коррозии в водном теплоносителе первого контура ЯЭУ |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
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JPH06230186A (ja) * | 1993-02-08 | 1994-08-19 | Hitachi Ltd | 放射性廃棄物の処理システム及び処理方法 |
JPH06265639A (ja) * | 1991-11-07 | 1994-09-22 | Aloka Co Ltd | 液体シンチレータによる多核種分別測定方法 |
US20090078884A1 (en) * | 2005-07-01 | 2009-03-26 | Cheol-Su Kim | Automatic radioactivity analyzer of mixed liquid beta emitter |
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JPS51100530A (ja) | 1975-02-28 | 1976-09-04 | Nhk Spring Co Ltd | Kiokusochitsukirikurainaa |
SU1151102A1 (ru) * | 1983-12-30 | 1992-01-23 | Предприятие П/Я М-5301 | Способ контрол радионуклидов в газообразных средах по реперному изотопу |
JP5546174B2 (ja) * | 2009-07-17 | 2014-07-09 | 三菱重工業株式会社 | 放射性廃棄物の放射能濃度評価方法及び評価プログラム、並びに放射能濃度評価装置 |
RU2571309C1 (ru) * | 2014-09-03 | 2015-12-20 | Федеральное государственное бюджетное образовательное учреждение высшего профессионального образования "Юго-Западный государственный университет" (ЮЗГУ) | Способ и устройство для определения абсолютной удельной активности содержимого контейнера с радиоактивными отходами и парциальных удельных активностей отдельных радионуклидов |
JP2017116349A (ja) * | 2015-12-22 | 2017-06-29 | 株式会社東芝 | β線ガスモニタ及びβ線を放出する核種を含むガスのモニタリング方法 |
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- 2019-07-15 RU RU2019122722A patent/RU2722203C1/ru active
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- 2020-07-03 EP EP20840782.5A patent/EP4036608B1/en active Active
- 2020-07-03 JP JP2022502497A patent/JP7383114B2/ja active Active
- 2020-07-03 WO PCT/RU2020/000329 patent/WO2021010864A1/ru unknown
- 2020-07-03 CN CN202080051187.1A patent/CN114127584A/zh active Pending
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH06265639A (ja) * | 1991-11-07 | 1994-09-22 | Aloka Co Ltd | 液体シンチレータによる多核種分別測定方法 |
JPH06230186A (ja) * | 1993-02-08 | 1994-08-19 | Hitachi Ltd | 放射性廃棄物の処理システム及び処理方法 |
US20090078884A1 (en) * | 2005-07-01 | 2009-03-26 | Cheol-Su Kim | Automatic radioactivity analyzer of mixed liquid beta emitter |
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EP4036608A4 (en) | 2022-09-14 |
CN114127584A (zh) | 2022-03-01 |
WO2021010864A1 (ru) | 2021-01-21 |
EP4036608A1 (en) | 2022-08-03 |
EP4036608B1 (en) | 2024-04-24 |
JP7383114B2 (ja) | 2023-11-17 |
RU2722203C1 (ru) | 2020-05-28 |
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