Published 2010 | Version v1
Miscellaneous

Plutonium rock-like oxide fuel (ROXf) system, their once-through burning and usage

  • 1. Brno Univ. of Tech., Brno (Czech Republic)

Description

'Full text:' The ROXf is a kind of inert matrix fuel U238-free matrices, it has a high plutonium transmutation capability. The ROXf consists of chemically stable phases of fluorite 'stabilized ZrO2 or ThO2 and spinel MgAl2O4. In this fuel, PuO2 is solidified in a fluorite phase. With U238-Free matrices, a large part of the plutonium can be burned after irradiation in conventional LWRs. The spent ROXf consists of natural analogous geologically stable phases , and is disposed directly as high level wastes 'HLWs' after about 50 years cooling. From the high plutonium burn up rate and the high stability of the fuel, the ROXf-LWRs system has proliferation resistance and environmental safety. Characteristics of two types of ROXf , Zr- ROX and Th -ROX with weapons-Pu ,in an LWR core arrangement are evaluated by cell burn up calculations and 2-D core calculations using the SRAC code system and JENDL-3 nuclear library. In an LWR of moderator to fuel volume ratio = 1.9 , which corresponds to current PWRs , Pu transmutation rates with the two types of ROXf are large enough and more than 80% and 99% of Pu and Pu239 , respectively, can be burned. The calculated kinetic parameters indicate less moderate characteristics of ROX cores, especially with Zr-ROX .The fertile Th232 in Th-ROX works like U238 in the UO2 fuel, making kinetic parameters more moderate and reactivity drop due to burn up smaller than that Zr-ROX. The neutron capture of Th232 to generate U233, causes the safeguards problem. Thus , the characteristics of Zr-ROX as a typical example, were investigated in this study. (author)

Part of:
Uranium 2010: The Future is U. Proceedings Volume 1 and 2

Additional details

Publishing Information

Publisher
The Canadian Inst. of Mining, Metallurgy and Petroleum
Imprint Place
Westmount, Quebec (Canada)
ISBN
1-894475-97-6
Imprint Title
Uranium 2010: The Future is U. Proceedings Volume 1 and 2
Imprint Pagination
2 v.
Journal Page Range
(v.2) p. 229

Conference

Title
3. International Conference on Uranium; 40. Annual Hydrometallurgy Meeting
Acronym
Uranium 2010 The Future is U
Dates
15-18 Aug 2010
Place
Saskatoon, Saskatchewan (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
48061188
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BURNUP; COMPUTERIZED SIMULATION; NUCLEAR FUELS; PLUTONIUM; RADIOACTIVE WASTE DISPOSAL; TRANSMUTATION; WATER COOLED REACTORS
Descriptors DEC
ACTINIDES; ELEMENTS; ENERGY SOURCES; FUELS; MANAGEMENT; MATERIALS; METALS; RADIOACTIVE WASTE MANAGEMENT; REACTOR MATERIALS; REACTORS; SIMULATION; TRANSURANIUM ELEMENTS; WASTE DISPOSAL; WASTE MANAGEMENT

Optional Information

Notes
Short communication. Abstract available only, full text entered in this record.