Author: B. J. Lewis
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Addendum to a proposal to power ramp previously irradiated zircaloy-4 uo2 fuel elements and to study the in-reactor post-defect behaviour
Author: B. J. Lewis
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A proposal to power ramp previously irradiated zircaloy-4/uo2 fuel elements and to study the in-reactor post-defect behaviour
Author: N. V. Ivanoff
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A proposal for the irradiation of zircaloy-4 clad, uo2 fuel elements at post-dryout sheath temperatures in the 625-675 degrees c range in the x-4 loop
Author: V. J. Langman
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A proposal to power cycle irradiated, zircaloy-clad, uo2 fuel elements using an in-reactor diameter measuring rig (irdmr) and the he-3 system in
Author: P. J. Fehrenbach
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Hot cell examination of a previously irradiated and then power ramped to defect zircaloy-4/uo2 fuel element job no. 917
Author: R. E. Moeller
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A proposal to study the effect of power ramp conditions on the dimensional stability of zircaloy-clad uo2 fuel elements
Author: P. J. Fehrenbach
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Proposal for power ramping two canflex uo2 fuel bundles irradiated at low power to an outer element burnup of ~ 150 mwh/kgu in the reactor
Author: M.R. Floyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Addendum to proposal exp-NPD-4601 : irradiation of uo2 fuel clad with annealed zirconium - 2.5 percent wt percent niobium alloy in the NPD reactor to burnups approaching 240 mwh.kgu
Author: C. E. Coleman
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR
Author: C. N. Spalaris
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 80
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 80
Book Description
Fabrication details for five zircaloy-4 clad fuel elements containing low density uo2 fuel pellets for irradiation in the NRU reactor
Author: J. D. Craigie
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description