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E 1.99: conf-790602-18
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Simple procedure for determining implications of design changes on fast reactor fuel cycle cost and breeding performance |
1 |
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E 1.99:conf-790602-19
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LOFT blowdown experiment safety analysis methodology |
1 |
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E 1.99:conf-790602-20
|
Improved RELAP4 BWR jet pump model |
1 |
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E 1.99:conf-790602-24
|
LOFT zero power/power range physics testing measurements versus calculations. |
1 |
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E 1.99:conf-790602-25
|
Design and operation of a dry spent fuel storage installation |
1 |
|
E 1.99:conf-790602-26
|
Unique features of the LOFT startup program |
1 |
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E 1.99:conf-790602-27
|
Sensitivity of decay power to uncertainties in estimated decay data |
1 |
|
E 1.99:conf-790602-28
|
Pre-LOCE thermal safety analysis of the LOFT reactor L2-2 experiment |
1 |
|
E 1.99: conf-790602-29
|
SOAR (Solar Assisted Reactor) power system |
1 |
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E 1.99:conf-790602-30
|
Evaluations of alternatives for management of INEL transuranic waste |
1 |
|
E 1.99: conf-790602-31
|
Design of a negative ion neutral beam system for TNS |
1 |
|
E 1.99: conf-790602-32
|
Stainless steel blanket concept for tokamaks |
1 |
|
E 1.99: conf-790602-33
|
Enhanced fuel production in thorium fusion hybrid blankets utilizing uranium multipliers |
1 |
|
E 1.99: conf-790602-34
|
Potential commercial reactor based on a small tokamak hybrid design |
1 |
|
E 1.99: conf-790602-35
|
Design of an advanced bundle divertor for the Demonstration Tokamak Hybrid Reactor |
1 |
|
E 1.99:conf-790602-36
|
Whole-core thermal-hydraulic transient code development and verification for LMFBR analysis |
1 |
|
E 1.99: conf-790602-37
|
Investigations in granite at Stripa, Sweden for nuclear waste storage |
1 |
|
E 1.99: conf-790602-39
|
Fusion reactors for synthetic fuels |
1 |
|
E 1.99:conf-790602-40
|
Nonintrusive local density determination in discontinuous fields by gammas or neutrons |
1 |
|
E 1.99:conf-790602-41
|
Doppler effect measurements on solid and liquid Sn. [24 keV] |
1 |
