Method of recovering neptunium from spent nuclear fuel
An improved Purex wet recovery process including the step of extracting and separating uranium and plutonium simultaneously from the fission products in the presence of nitric acid and nitrous acid by using a multistage extractor unit having an extracting section and a washing section is provided fo...
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| creator | NEMOTO SINICHI TSUBOYA TAKAO HOSHINO TADAYA TANAKA CHUZABURO |
| description | An improved Purex wet recovery process including the step of extracting and separating uranium and plutonium simultaneously from the fission products in the presence of nitric acid and nitrous acid by using a multistage extractor unit having an extracting section and a washing section is provided for separating and recovering neptunium simultaneously with uranium and plutonium contained in spent nuclear fuel. The improved method comprises the steps of maintaining the nitrous acid concentration in said extracting section at a level suited for effecting oxidation of neptunium from (V) to (VI) valence, while lowering the nitrous acid concentration in said washing section so as to suppress reduction of neptunium from (VI) to (V) valence, and maintaining the nitric acid concentration in said washing section at a high level. |
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The improved method comprises the steps of maintaining the nitrous acid concentration in said extracting section at a level suited for effecting oxidation of neptunium from (V) to (VI) valence, while lowering the nitrous acid concentration in said washing section so as to suppress reduction of neptunium from (VI) to (V) valence, and maintaining the nitric acid concentration in said washing section at a high level.</description><language>eng</language><subject>CHEMISTRY ; CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATERTREATMENT OR WASTE MANAGEMENT ; COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSESC01D OR C01F ; DECONTAMINATION ARRANGEMENTS THEREFOR ; FERROUS OR NON-FERROUS ALLOYS ; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC ; GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS ; INORGANIC CHEMISTRY ; METALLURGY ; NUCLEAR ENGINEERING ; NUCLEAR PHYSICS ; NUCLEAR REACTORS ; PHYSICS ; PRETREATMENT OF RAW MATERIALS ; PRODUCTION AND REFINING OF METALS ; PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULARRADIATION OR PARTICLE BOMBARDMENT ; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS ; TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE ; TREATING RADIOACTIVELY CONTAMINATED MATERIAL ; TREATMENT OF ALLOYS OR NON-FERROUS METALS</subject><creationdate>1976</creationdate><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://worldwide.espacenet.com/publicationDetails/biblio?FT=D&date=19760608&DB=EPODOC&CC=US&NR=3962401A$$EHTML$$P50$$Gepo$$Hfree_for_read</linktohtml><link.rule.ids>230,308,780,885,25564,76547</link.rule.ids><linktorsrc>$$Uhttps://worldwide.espacenet.com/publicationDetails/biblio?FT=D&date=19760608&DB=EPODOC&CC=US&NR=3962401A$$EView_record_in_European_Patent_Office$$FView_record_in_$$GEuropean_Patent_Office$$Hfree_for_read</linktorsrc></links><search><creatorcontrib>NEMOTO; SINICHI</creatorcontrib><creatorcontrib>TSUBOYA; TAKAO</creatorcontrib><creatorcontrib>HOSHINO; TADAYA</creatorcontrib><creatorcontrib>TANAKA; CHUZABURO</creatorcontrib><title>Method of recovering neptunium from spent nuclear fuel</title><description>An improved Purex wet recovery process including the step of extracting and separating uranium and plutonium simultaneously from the fission products in the presence of nitric acid and nitrous acid by using a multistage extractor unit having an extracting section and a washing section is provided for separating and recovering neptunium simultaneously with uranium and plutonium contained in spent nuclear fuel. The improved method comprises the steps of maintaining the nitrous acid concentration in said extracting section at a level suited for effecting oxidation of neptunium from (V) to (VI) valence, while lowering the nitrous acid concentration in said washing section so as to suppress reduction of neptunium from (VI) to (V) valence, and maintaining the nitric acid concentration in said washing section at a high level.</description><subject>CHEMISTRY</subject><subject>CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATERTREATMENT OR WASTE MANAGEMENT</subject><subject>COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSESC01D OR C01F</subject><subject>DECONTAMINATION ARRANGEMENTS THEREFOR</subject><subject>FERROUS OR NON-FERROUS ALLOYS</subject><subject>GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC</subject><subject>GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS</subject><subject>INORGANIC CHEMISTRY</subject><subject>METALLURGY</subject><subject>NUCLEAR ENGINEERING</subject><subject>NUCLEAR PHYSICS</subject><subject>NUCLEAR REACTORS</subject><subject>PHYSICS</subject><subject>PRETREATMENT OF RAW MATERIALS</subject><subject>PRODUCTION AND REFINING OF METALS</subject><subject>PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULARRADIATION OR PARTICLE BOMBARDMENT</subject><subject>TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS</subject><subject>TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE</subject><subject>TREATING RADIOACTIVELY CONTAMINATED MATERIAL</subject><subject>TREATMENT OF ALLOYS OR NON-FERROUS METALS</subject><fulltext>true</fulltext><rsrctype>patent</rsrctype><creationdate>1976</creationdate><recordtype>patent</recordtype><sourceid>EVB</sourceid><recordid>eNrjZDDzTS3JyE9RyE9TKEpNzi9LLcrMS1fISy0oKc3LLM1VSCvKz1UoLkjNK1HIK03OSU0sUkgrTc3hYWBNS8wpTuWF0twM8m6uIc4euqkF-fGpxQWJyal5qSXxocHGlmZGJgaGjsaEVQAACactHA</recordid><startdate>19760608</startdate><enddate>19760608</enddate><creator>NEMOTO; SINICHI</creator><creator>TSUBOYA; TAKAO</creator><creator>HOSHINO; TADAYA</creator><creator>TANAKA; CHUZABURO</creator><scope>EVB</scope></search><sort><creationdate>19760608</creationdate><title>Method of recovering neptunium from spent nuclear fuel</title><author>NEMOTO; SINICHI ; TSUBOYA; TAKAO ; HOSHINO; TADAYA ; TANAKA; CHUZABURO</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-epo_espacenet_US3962401A3</frbrgroupid><rsrctype>patents</rsrctype><prefilter>patents</prefilter><language>eng</language><creationdate>1976</creationdate><topic>CHEMISTRY</topic><topic>CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATERTREATMENT OR WASTE MANAGEMENT</topic><topic>COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSESC01D OR C01F</topic><topic>DECONTAMINATION ARRANGEMENTS THEREFOR</topic><topic>FERROUS OR NON-FERROUS ALLOYS</topic><topic>GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC</topic><topic>GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS</topic><topic>INORGANIC CHEMISTRY</topic><topic>METALLURGY</topic><topic>NUCLEAR ENGINEERING</topic><topic>NUCLEAR PHYSICS</topic><topic>NUCLEAR REACTORS</topic><topic>PHYSICS</topic><topic>PRETREATMENT OF RAW MATERIALS</topic><topic>PRODUCTION AND REFINING OF METALS</topic><topic>PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULARRADIATION OR PARTICLE BOMBARDMENT</topic><topic>TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS</topic><topic>TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE</topic><topic>TREATING RADIOACTIVELY CONTAMINATED MATERIAL</topic><topic>TREATMENT OF ALLOYS OR NON-FERROUS METALS</topic><toplevel>online_resources</toplevel><creatorcontrib>NEMOTO; SINICHI</creatorcontrib><creatorcontrib>TSUBOYA; TAKAO</creatorcontrib><creatorcontrib>HOSHINO; TADAYA</creatorcontrib><creatorcontrib>TANAKA; CHUZABURO</creatorcontrib><collection>esp@cenet</collection></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext_linktorsrc</fulltext></delivery><addata><au>NEMOTO; SINICHI</au><au>TSUBOYA; TAKAO</au><au>HOSHINO; TADAYA</au><au>TANAKA; CHUZABURO</au><format>patent</format><genre>patent</genre><ristype>GEN</ristype><title>Method of recovering neptunium from spent nuclear fuel</title><date>1976-06-08</date><risdate>1976</risdate><abstract>An improved Purex wet recovery process including the step of extracting and separating uranium and plutonium simultaneously from the fission products in the presence of nitric acid and nitrous acid by using a multistage extractor unit having an extracting section and a washing section is provided for separating and recovering neptunium simultaneously with uranium and plutonium contained in spent nuclear fuel. The improved method comprises the steps of maintaining the nitrous acid concentration in said extracting section at a level suited for effecting oxidation of neptunium from (V) to (VI) valence, while lowering the nitrous acid concentration in said washing section so as to suppress reduction of neptunium from (VI) to (V) valence, and maintaining the nitric acid concentration in said washing section at a high level.</abstract><oa>free_for_read</oa></addata></record> |
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| subjects | CHEMISTRY CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATERTREATMENT OR WASTE MANAGEMENT COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSESC01D OR C01F DECONTAMINATION ARRANGEMENTS THEREFOR FERROUS OR NON-FERROUS ALLOYS GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS INORGANIC CHEMISTRY METALLURGY NUCLEAR ENGINEERING NUCLEAR PHYSICS NUCLEAR REACTORS PHYSICS PRETREATMENT OF RAW MATERIALS PRODUCTION AND REFINING OF METALS PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULARRADIATION OR PARTICLE BOMBARDMENT TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE TREATING RADIOACTIVELY CONTAMINATED MATERIAL TREATMENT OF ALLOYS OR NON-FERROUS METALS |
| title | Method of recovering neptunium from spent nuclear fuel |
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