Assumptions and Criteria for Performing a Feasability Study of the Conversion of the High Flux Isotope Reactor Core to Use Low-Enriched Uranium Fuel

Primm, R.T.; Ellis, Ronald J.; Gehin, Jess C; Moses, D.L.; Binder, Jeffrey L.; Xoubi, Ned

doi:10.2172/890007

Cited by 13 publications

(15 citation statements)

References 7 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…The LEU fuel currently under consideration is a high-density monolithic alloy, U-10Mo, which contains 90 wt % uranium and 10 wt % natural molybdenum. It has a density of 17.02 g/cm 3 and an enrichment of 19.75 wt % 235 U. As included in the key top-level assumptions established to guide the HFIR conversion study, 3 there shall be no change in the physical dimensions of the core or fuel geometry, no reduction in the core power or core lifetime, and no major changes to the current control and protection systems, and the margins of safety in the bases of the currently approved Technical Safety Requirements 4 shall be maintained.…”

Section: Background On the Hfir Conversion Studymentioning

confidence: 99%

“…It has a density of 17.02 g/cm 3 and an enrichment of 19.75 wt % 235 U. As included in the key top-level assumptions established to guide the HFIR conversion study, 3 there shall be no change in the physical dimensions of the core or fuel geometry, no reduction in the core power or core lifetime, and no major changes to the current control and protection systems, and the margins of safety in the bases of the currently approved Technical Safety Requirements 4 shall be maintained. The fuel meat is the region that will need to be changed when the current HEU fuel is replaced with LEU fuel, with no changes to the basic geometry of the fuel plate.…”

Section: Background On the Hfir Conversion Studymentioning

confidence: 99%

“…3. The program requires, as input, reactor geometry, a 2-D (radial and axial) power profile as a function of irradiation time, and manufacturing uncertainty factors.…”

Section: Thermal Hydraulic Analyses-the Hfir Steady State Heat Transfmentioning

confidence: 99%

“…Since almost no data are available, the uncertainty values associated with the current HEU fuel and documented in Ref. 3 were used in the analyses reported here.…”

Section: Thermal Hydraulic Analyses-the Hfir Steady State Heat Transfmentioning

confidence: 99%

See 3 more Smart Citations

Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor

Ilas¹,

Primm²

2009

View full text Add to dashboard Cite

Section: Background On the Hfir Conversion Studymentioning

confidence: 99%

Section: Background On the Hfir Conversion Studymentioning

confidence: 99%

“…3. The program requires, as input, reactor geometry, a 2-D (radial and axial) power profile as a function of irradiation time, and manufacturing uncertainty factors.…”

Section: Thermal Hydraulic Analyses-the Hfir Steady State Heat Transfmentioning

confidence: 99%

“…Since almost no data are available, the uncertainty values associated with the current HEU fuel and documented in Ref. 3 were used in the analyses reported here.…”

Section: Thermal Hydraulic Analyses-the Hfir Steady State Heat Transfmentioning

confidence: 99%

See 2 more Smart Citations

Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor

Ilas¹,

Primm²

2009

View full text Add to dashboard Cite

“…This can be done by increasing the coolant channel width provided thermal -conditions allow such reduction . [4] . …”

Section: Heu To Leu Fuel Conversion Studymentioning

confidence: 99%

Feasibility Study of the (10mw) MTR Heu to Leu Conversion

Sattar¹

2008

JNUS

View full text Add to dashboard Cite

Material test reactor (MTR) is a pressurized, reflected, open pool -type, light -water moderated and cooled heterogeneous system designed for operation at a maximum steady -state power level of "10MW" thermal. This reactor regionized by a consultant's group from IAEA member state, which has been meeting regularly to discuss the technical issue of core conversion. A conversion feasibility study, which involves both HEU (93 % U 235 ) and LEU (30 % U 235 ) fuels, is currently being performed. In order to determine core excess reactivity, Wims-D4 and Daixy codes would used to justify the conversion study from HEU to LEU, which limited by two options; the first one depends on increasing the amount of U 235 (no redesign of fuel element), the second option depend on decreasing either the plate cladding or fuel meat thickness while increasing the width of the coolant gap (redesign of fuel element).

show abstract

Fuel cycle depletion validation and code-to-code verification studies for High Flux Isotope Reactor highly and low-enriched uranium fuel designs

Chandler

Bae

Betzler

et al. 2023

Annals of Nuclear Energy

View full text Add to dashboard Cite

Assumptions and Criteria for Performing a Feasability Study of the Conversion of the High Flux Isotope Reactor Core to Use Low-Enriched Uranium Fuel

Cited by 13 publications

References 7 publications

Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor

Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor

Feasibility Study of the (10mw) MTR Heu to Leu Conversion

Fuel cycle depletion validation and code-to-code verification studies for High Flux Isotope Reactor highly and low-enriched uranium fuel designs

Contact Info

Product

Resources

About