JP6579469B2 - Nuclear reactor decommissioning method - Google Patents
Nuclear reactor decommissioning method Download PDFInfo
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- JP6579469B2 JP6579469B2 JP2016256802A JP2016256802A JP6579469B2 JP 6579469 B2 JP6579469 B2 JP 6579469B2 JP 2016256802 A JP2016256802 A JP 2016256802A JP 2016256802 A JP2016256802 A JP 2016256802A JP 6579469 B2 JP6579469 B2 JP 6579469B2
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Description
本発明は原子炉の廃炉に関する The present invention relates to a decommissioning reactor.
原子炉内は放射線量が高く、実際には解体作業は非常に難しく作業員の健康を害することになる。したがってロボット技術等で研究されてはいるがなかなか技術の進展が進まない現状である。In the reactor, the radiation dose is high, and in fact, the dismantling work is very difficult and the health of workers is impaired. Therefore, although it has been researched with robot technology, it is difficult to make progress in technology.
実際には廃炉工事の実績は国内ではなく、特許文献の調査はできませんでした。
Actually, the decommissioning work was not done in Japan, and the patent literature could not be investigated.
いかにして原子炉内の高濃度に放射能汚染された内蔵物を外部へ排出する対策を考案する。How to devise a measure to discharge the high-concentration radioactive contamination inside the reactor to the outside.
原子炉内部に溶解液を循環させて長期間運転（溶けるのに長時間が必要）を行い、支持構造物以外の内蔵物を全て溶かして外部へ排出する手段を考案した。 We devised a means to circulate the solution inside the reactor and operate it for a long time (it takes a long time to melt) to melt all the built-in materials other than the support structure and discharge it to the outside.
休止になった原子炉からウラン燃料をまず取り出して処置することが先決であるが、取り出せない状態の場合はウランも一緒に溶解させることになる。 The first decision is to remove uranium fuel from the reactor that has been shut down and treat it, but if it cannot be removed, uranium will also be dissolved together.
本発明は原子炉内部の放射能に汚染された空間において廃炉作業を行うにあたり作業員の安全と健康を第一に考えて考案したものである。 The present invention has been devised considering the safety and health of workers first when performing decommissioning work in a space contaminated by radioactivity inside the reactor.
放射能汚染内蔵物を溶かすことにより、容易に外部へ搬出できた上、後処理及び保管管理が少量化できる。 By melting the radioactive contamination built-in, it can be easily transported to the outside, and the post-treatment and storage management can be reduced.
一番重要な要素は廃炉期間が短縮できることと、廃炉工事が低コストで工事が完了できることである。The most important factors are that the decommissioning period can be shortened and that decommissioning can be completed at low cost.
以下、本発明の実施の形態を図１〜図４の図に基づいて説明する。Hereinafter, embodiments of the present invention will be described with reference to FIGS. 1 to 4.
図−１においては原子炉の廃炉方法を溶解液循環による原子炉内容物を溶かして外部へ排出する手段を考案したフローシート（全体構成図）である。FIG. 1 is a flow sheet (overall configuration diagram) devised as a means for melting the reactor contents by dissolving solution circulation and discharging the reactor contents to the outside.
図−２においては原子炉下部に溶解混合液受槽を取り付けるために先行準備する取り付けフランジです。また沸騰水型原子炉の場合、制御棒等は切断して取り除き溶解混合液受槽外部の制御棒管口は鋼板で蓋をしておくこと。In Fig.-2, it is a mounting flange that is prepared in advance for mounting the molten mixture receiving tank at the bottom of the reactor. In the case of boiling water reactors, the control rods should be cut off and removed, and the control rod tube outside the molten mixture receiving tank should be covered with a steel plate.
図−３においては原子炉下部に溶解された混合液を流下させ溶解分離槽へ送りこむ役目を担う受槽である。In FIG. 3, it is a receiving tank which plays a role of flowing down the mixed liquid dissolved in the lower part of the nuclear reactor and sending it to the dissolving / separating tank.
図−４においては原子炉から循環されてきた溶解混合液の残渣を捕獲するために多孔板式仕切板で区画した分離槽である。また一方で下部攪拌翼による粘性検知（電流値負荷）を確認しながら外部へ排出する自動制御システムで構成されたものである。In FIG. 4, it is a separation tank partitioned by a perforated plate type partition plate in order to capture the residue of the dissolved mixed solution circulated from the nuclear reactor. On the other hand, it is composed of an automatic control system that discharges to the outside while confirming viscosity detection (current value load) by the lower stirring blade.
図−１の符号の説明
１は取付けフランジ、２は溶解混合液受槽、３は溶解液分離槽、
４は受槽Ａ、５は受槽Ｂ、６は多管式熱交換器Description of reference numerals in FIG. 1 1 is a mounting flange, 2 is a solution mixture receiving tank, 3 is a solution separation tank,
4 is a receiving tank A, 5 is a receiving tank B, 6 is a multi-tube heat exchanger
図−２の符号の説明
１は胴板、２は取付けフランジ、３はマンホール口、４は溶解液入口、Description of symbols in FIG. 2 1 is a body plate, 2 is a mounting flange, 3 is a manhole port, 4 is a solution inlet,
図−３の符号の説明
１は受溶解混合液受槽の鏡板、２は取付けフランジ、３は外套、４は攪拌翼、
５は下部攪拌装置、６はマンホール口、７は蒸気入口、８は蒸気出口Description of reference numerals in FIG. 3 1 is the end plate of the receiving solution mixture receiving tank, 2 is a mounting flange, 3 is a jacket, 4 is a stirring blade,
5 is a lower stirrer, 6 is a manhole port, 7 is a steam inlet, 8 is a steam outlet
図−４の符号の説明
１は胴板、２は上部外套、３は下部外套、４は多孔板式仕切板、
５は下部攪拌翼、６は中間攪拌翼、７は上部攪拌装置、８はマンホール口、
９はドレーン口、１０は溶解液入口、１１は溶解液送り口、
１２は溶解液戻り口、１３は溶解混合液戻り口、１４は蒸気入口、
１５は蒸気出口、１６は蒸気入口、１７は蒸気出口、１８は安全弁口、
１９はブラケット、２０は支柱、Description of symbols in FIG. 4 1 is a body plate, 2 is an upper jacket, 3 is a lower jacket, 4 is a perforated partition plate,
5 is a lower stirring blade, 6 is an intermediate stirring blade, 7 is an upper stirring device, 8 is a manhole port,
9 is a drain port, 10 is a solution inlet, 11 is a solution feed port,
12 is a solution return port, 13 is a solution mixture return port, 14 is a steam inlet,
15 is a steam outlet, 16 is a steam inlet, 17 is a steam outlet, 18 is a safety valve,
19 is a bracket, 20 is a support,
Claims (1)
逆王水（濃塩酸と濃硝酸の体積比１：３）
王 水（濃塩酸と濃硝酸の体積比３：１）In the present invention, the melt is circulated between the nuclear reactor and the melt separation tank so that the structure inside the reactor is gradually melted, and then guided to the melt mixture receiving tank attached to the lower part of the reactor. The dissolved solution sent to the liquid separation tank is divided into upper and lower sections by the perforated plate partition plate of the solution separation tank, so that the mixed impurities are separated into the lower tank, and the solution to be circulated in the present invention has the following volume. A method of decommissioning a nuclear reactor that employs the reverse aqua regia or aqua regia indicated by the ratio, and further uses a product coated with a corrosion-resistant glass lining for the equipment and piping of the solution circulation line excluding the nuclear reactor.
Reverse aqua regia (volume ratio of concentrated hydrochloric acid to concentrated nitric acid 1: 3)
Omizu (volume ratio of concentrated hydrochloric acid to concentrated nitric acid 3: 1)
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| JP6579469B2 true JP6579469B2 (en) | 2019-09-25 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| JPS56111499A (en) * | 1980-02-06 | 1981-09-03 | Kobe Steel Ltd | Method of processing spent fuel insertion for pwr type reactor |
| FR2739216B1 (en) * | 1995-09-22 | 1997-10-24 | Commissariat Energie Atomique | METHOD OF TREATING METALLIC ALUMINUM-BASED FUELS AND / OR NUCLEAR TARGETS WITH TETRAMETHYLAMMONIUM HYDROXIDE SOLUTIONS |
| US6652661B2 (en) * | 2001-10-12 | 2003-11-25 | Bobolink, Inc. | Radioactive decontamination and translocation method |
| JP2013217705A (en) * | 2012-04-05 | 2013-10-24 | Toshiba Corp | Failed fuel take-out method in nuclear power plant |
| JP5961572B2 (en) * | 2012-06-28 | 2016-08-02 | 日立Ｇｅニュークリア・エナジー株式会社 | Treatment of damaged or molten nuclear fuel |
| TWI458957B (en) * | 2012-09-06 | 2014-11-01 | Atomic Energy Council | Method of separate amorphous from radioactive iron oxides for nuclear power plants |
| JP2014085325A (en) * | 2012-10-26 | 2014-05-12 | Mitsubishi Heavy Ind Ltd | Waste liquid treating system and waste liquid treating method |
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