Report
Radiochemical analyses of several spent fuel Approved Testing Materials
| العنوان: | Radiochemical analyses of several spent fuel Approved Testing Materials |
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| المؤلفون: | Guenther, R. J., Blahnik, D. E., Wildung, N. J. |
| المساهمون: | United States. Department of Energy. |
| المصدر: | Other Information: PBD: Sep 1994 |
| بيانات النشر: | Pacific Northwest Laboratory |
| سنة النشر: | 1994 |
| المجموعة: | University of North Texas: UNT Digital Library |
| مصطلحات موضوعية: | Uranium Isotopes, Iodine 129, Plutonium Isotopes, Americium 241, 38 Radiation Chemistry, Radiochemistry, And Nuclear Chemistry, Compiled Data 052000, Cesium 135, Cesium 137, Gadolinium Oxides, Cooper Reactor, Technetium 99, Uranium Dioxide, Properties Of Radioactive Materials, Calvert Cliffs-1 Reactor, Standards, Fission Products, 12 Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities, Radioactive Waste Management, Tin 126, Irradiation, Neptunium 237, Selenium 79, Curium 244, Experimental Data, Strontium 90, Curium 243, Carbon 14 |
| Time: | 400702 |
| الوصف: | Radiochemical characterization data are described for UO{sub 2} and UO{sub 2} plus 3 wt% Gd{sub 2}O{sub 3} commercial spent nuclear fuel taken from a series of Approved Testing Materials (ATMs). These full-length nuclear fuel rods include MLA091 of ATM-103, MKP070 of ATM-104, NBD095 and NBD131 of ATM-106, and ADN0206 of ATM-108. ATMs 103, 104, and 106 were all irradiated in the Calvert Cliffs Nuclear Power Plant (Reactor No.1), a pressurized-water reactor that used fuel fabricated by Combustion Engineering. ATM-108 was part of the same fuel bundle designed as ATM-105 and came from boiling-water reactor fuel fabricated by General Electric and irradiated in the Cooper Nuclear Power Plant. Rod average burnups and expected fission gas releases ranged from 2,400 to 3,700 GJ/kgM. (25 to 40 Mwd/kgM) and from less than 1% to greater than 10%, respectively, depending on the specific ATM. The radiochemical analyses included uranium and plutonium isotopes in the fuel, selected fission products in the fuel, fuel burnup, cesium and iodine on the inner surfaces of the cladding, {sup 14}C in the fuel and cladding, and analyses of the gases released to the rod plenum. Supporting examinations such as fuel rod design and material descriptions, power histories, and gamma scans used for sectioning diagrams are also included. These ATMs were examined as part of the Materials Characterization Center Program conducted at Pacific Northwest Laboratory provide a source of well-characterized spent fuel for testing in support of the US Department of Energy Office of Civilian Radioactive Waste Management Program. |
| نوع الوثيقة: | report |
| وصف الملف: | 121 p.; Text |
| اللغة: | English |
| Relation: | other: DE95000772; rep-no: PNL--10113; grantno: AC06-76RL01830; osti: 10186049; https://digital.library.unt.edu/ark:/67531/metadc1403330/; ark: ark:/67531/metadc1403330 |
| DOI: | 10.2172/10186049 |
| الاتاحة: | https://doi.org/10.2172/10186049 https://digital.library.unt.edu/ark:/67531/metadc1403330/ |
| رقم الانضمام: | edsbas.996445DF |
| قاعدة البيانات: | BASE |
| DOI: | 10.2172/10186049 |
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