Published October 2001
| Version v1
Miscellaneous
Determination of lithium oxide for evaluating the metal conversion rate of uranium oxide
- 1. KAERI, Taejon (Korea, Republic of)
- 2. Mokpo National Univ., Mokpo (Korea, Republic of)
Description
Lithium oxide content was quantitatively analyzed by the acid-base titration method following hydrogen gas measurement for evaluating metal conversion rate of spent nuclear fuel in DOR(direct oxide reduction) process. The main error was estimated to come from the sample weighing step in glove box and hydrogen gas measurement step. Weighing 200 mg sample in glove box gave 1.6% error, and measuring hydrogen gas showed big standard deviation equivalent to 4 - 10% value of measured hydrogen volume. The analysis process of lithium oxide was effectively improved by understanding the causes of error and its impacts
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society autumn meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [7 p.]
Conference
- Title
- 2001 autumn meeting of the Korean Nuclear Society
- Dates
- 24-26 Oct 2001
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33065617
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ERRORS; GLOVEBOXES; HYDROGEN; LITHIUM OXIDES; REDUCTION; REPROCESSING; TITRATION; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALKALI METAL COMPOUNDS; CHALCOGENIDES; CHEMICAL ANALYSIS; CHEMICAL REACTIONS; ELEMENTS; EQUIPMENT; LABORATORY EQUIPMENT; LITHIUM COMPOUNDS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; QUANTITATIVE CHEMICAL ANALYSIS; SEPARATION PROCESSES; URANIUM COMPOUNDS; VOLUMETRIC ANALYSIS
Optional Information
- Notes
- 5 refs, 2 figs, 2 tabs