A heavy-water-cooled research reáctor is fueled with natural- Im metal rods 0.9 in. in diameter clad with 0.05-in.-thick aluminum. The maximum temperature in the fuel at a certain cross section in the rod is 700°F. The coolant bulk temperature at the cross section is 180°F. The heat-transfer coefficient is 5000 Btu/hr ft2 °F. Determine for the above cross section (a) the neutron flux (thermal); (b) the specific power, kw/kg fuel; (c) the maximum cladding temperature; (d) the maximum coolant temperature; (e) the minimum coolant pressure to avoid boiling; and (f) the theoretical maximum flux beyond which the above maximum fuel
A heavy-water-cooled research reáctor is fueled with natural- Im metal rods 0.9 in. in diameter clad with 0.05-in.-thick aluminum. The maximum temperature in the fuel at a certain cross section in the rod is 700°F. The coolant bulk temperature at the cross section is 180°F. The heat-transfer coefficient is 5000 Btu/hr ft2 °F. Determine for the above cross section (a) the neutron flux (thermal); (b) the specific power, kw/kg fuel; (c) the maximum cladding temperature; (d) the maximum coolant temperature; (e) the minimum coolant pressure to avoid boiling; and (f) the theoretical maximum flux beyond which the above maximum fuel
Elements Of Electromagnetics
7th Edition
ISBN:9780190698614
Author:Sadiku, Matthew N. O.
Publisher:Sadiku, Matthew N. O.
ChapterMA: Math Assessment
Section: Chapter Questions
Problem 1.1MA
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![A heavy-water-cooled research reactor is fueled with natural-uranium metal rods 0.9 in.
in diameter clad with 0.05-in.-thick aluminum. The maximum temperature in the fuel at a
certain cross section in the rod is 700°F. The coolant bulk temperature at the cross section is
180°F. The heat-transfer coefficient is 5000 Btu/hr ft2 °F. Determine for the above cross
section (a) the neutron flux (thermal); (b) the specific power, kw/kg fuel; (c) the maximum
cladding temperature; (d) the maximum coolant temperature; (e) the minimum coolant pressure
to avoid boiling; and (f) the theoretical maximum flux beyond which the above maximum fuel
temperature cannot be maintained.](/v2/_next/image?url=https%3A%2F%2Fcontent.bartleby.com%2Fqna-images%2Fquestion%2Ff6c78e0d-45e3-4b40-8014-ce6a6227df1a%2Ff8ddde99-7625-4085-9b18-77174336cedd%2Fjets29m_processed.jpeg&w=3840&q=75)
Transcribed Image Text:A heavy-water-cooled research reactor is fueled with natural-uranium metal rods 0.9 in.
in diameter clad with 0.05-in.-thick aluminum. The maximum temperature in the fuel at a
certain cross section in the rod is 700°F. The coolant bulk temperature at the cross section is
180°F. The heat-transfer coefficient is 5000 Btu/hr ft2 °F. Determine for the above cross
section (a) the neutron flux (thermal); (b) the specific power, kw/kg fuel; (c) the maximum
cladding temperature; (d) the maximum coolant temperature; (e) the minimum coolant pressure
to avoid boiling; and (f) the theoretical maximum flux beyond which the above maximum fuel
temperature cannot be maintained.
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