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Safety analysis report for the mixed waste storage facility and portable storage units at the Idaho National Engineering Laboratory (INEL ; INEL-96/0214-Rev.3; DE97052942)

Safety analysis report for the mixed waste storage facility and portable storage units at the Idaho National Engineering Laboratory (INEL ; INEL-96/0214-Rev.3; DE97052942)
紙図書
Peatross, R.Idaho National Engineering Lab.1997.4.14.
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Assessment of aircraft impact probabilities at the Idaho Chemical Processing Plant (INEL ; INEL-96/0110-Rev.3;DE96010355)

Assessment of aircraft impact probabilities at the Idaho Chemical Processing Plant (INEL ; INEL-96/0110-Rev.3;DE96010355)
紙図書
Lee, L.G., Mines, J.M., Webb, B.B.Idaho National Engineering Lab.1996.4.
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Application of ultrasound in solvent extraction of nickel and gallium (INEL ; INEL-96/0229; DE96014095)

Application of ultrasound in solvent extraction of nickel and gallium (INEL ; INEL-96/0229; DE96014095)
紙図書
Pesic, B.Aerojet Nuclear Co., Idaho National Engineering Lab.1996.7.
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Preparation of a radiodiagnostic agent containing 99mTc-d,1-4,8-diaza-3,6,6,9-tetramethylundecane-2,10-bisoxime complex (CZ PATENT APPLICATION ; CZ PATENT APPLICATION 5927-90)

Preparation of a radiodiagnostic agent containing 99mTc-d,1-4,8-diaza-3,6,6,9-tetramethylundecane-2,10-bisoxime complex (CZ PATENT APPLICATION ; CZ PATENT APPLICATION 5927-90)
紙図書
Idaho National Engineering Lab., Idaho Falls (USA)(Idaho National Engineering Lab., Idaho Falls (USA))1993.
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Volcanic hazards of the Idaho National Engineering Laboratory and adjacent areas (INEL ; INEL-94/0276; DE98052557)

Volcanic hazards of the Idaho National Engineering Laboratory and adjacent areas (INEL ; INEL-94/0276; DE98052557)
紙図書
Hackett, WR., Smith, R.P.Lockheed Martin Idaho Technologies Co., Idaho National Engineering Lab.1994.12.
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Reclamation of nitrate ions from anion exchanger after elution of uranium (CS PATENT APPLICATION ; CS PATENT APPLICATION PV 6880-88.Y)

Reclamation of nitrate ions from anion exchanger after elution of uranium (CS PATENT APPLICATION ; CS PATENT APPLICATION PV 6880-88.Y)
紙図書
Idaho National Engineering Lab., Idaho Falls (USA)(Idaho National Engineering Lab., Idaho Falls (USA))1991.
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A directed radioluminescent light source (CS PATENT APPLICATION ; CS PATENT APPLICATION PV 1533-85)

A directed radioluminescent light source (CS PATENT APPLICATION ; CS PATENT APPLICATION PV 1533-85)
紙図書
Idaho National Engineering Lab., Idaho Falls (USA)(Idaho National Engineering Lab., Idaho Falls (USA))1989.
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Removable of trace radionuclides and chemical contaminants from waste evaporator condensates by electrodialysis (WINCO ; WINCO-1045)

Removable of trace radionuclides and chemical contaminants from waste evaporator condensates by electrodialysis (WINCO ; WINCO-1045)
紙図書
Del Debbio, J.A.Idaho National Engineering Lab.1986.9.
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Representative element modeling of fracture systems based on stochastic analysis (EGG ; EGG-M-33885)

Representative element modeling of fracture systems based on stochastic analysis (EGG ; EGG-M-33885)
紙図書
Clemo, T.M.Idaho National Engineering Lab.1986.
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Long-term materials testing of transportable storage cask containment and basket materials (SAND ; SAND-88-1916C; TTC-0820; CONF-881011-14; DE88013369)

Long-term materials testing of transportable storage cask containment and basket materials (SAND ; SAND-88-1916C; TTC-0820; CONF-881011-14; DE88013369)
紙図書
Ottinger, C.A., Mings, W.J.Sandia National Labs., Idaho National Engineering Lab.1988.1.
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Observations of plant decons (EGG ; EGG-M-04285; CONF-850279-2; DE85014575)

Observations of plant decons (EGG ; EGG-M-04285; CONF-850279-2; DE85014575)
紙図書
Duce, S.W., Simpson, F.B., Mandler, J.W.Idaho National Engineering Lab.1985.
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Fuel burnup monitor for nuclear reactors (CS PATENT APPLICATION ; CS PATENT APPLICATION PV 1086-81)

Fuel burnup monitor for nuclear reactors (CS PATENT APPLICATION ; CS PATENT APPLICATION PV 1086-81)
紙図書
Idaho National Engineering Lab., Idaho Falls (USA)(Idaho National Engineering Lab., Idaho Falls (USA))1986.
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Use of a simplified pathways model to improve the environmental surveillance program at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory (INEL) (EGG ; EGG-M-24284)

Use of a simplified pathways model to improve the environmental surveillance program at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory (INEL) (EGG ; EGG-M-24284)
紙図書
Case, M.J., Rope, S.K.Idaho National Engineering Lab.1984.
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Pressurized water reactor transient identification and monitoring technique using reactor coolant pumps (EGG ; EGG-M-14784)

Pressurized water reactor transient identification and monitoring technique using reactor coolant pumps (EGG ; EGG-M-14784)
紙図書
Adams, J.P. [et al.]Idaho National Engineering Lab.1984.
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LOFT experimental measurements uncertainty analyses. Volume IV. Liquid-level transducers (NUREG ; NUREG/CR-0169-Vol.4; EGG-2037-Vol.4; DE83002126)

LOFT experimental measurements uncertainty analyses. Volume IV. Liquid-level transducers (NUREG ; NUREG/CR-0169-Vol.4; EGG-2037-Vol.4; DE83002126)
紙図書
Meachum, T.R.Idaho National Engineering Lab.1982.10.
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LOFT experimental measurements uncertainty analyses. Volume XX. Fluid-velocity measurement using pulsed-neutron activation (NUREG ; NUREG/CR-0169-Vol.20; EGG-2037; DE83000815)

LOFT experimental measurements uncertainty analyses. Volume XX. Fluid-velocity measurement using pulsed-neutron activation (NUREG ; NUREG/CR-0169-Vol.20; EGG-2037; DE83000815)
紙図書
Lassahn, G.D., Taylor, D.J.N.Idaho National Engineering Lab.1982.08.
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Conceptual design report for a Fusion Engineering Device sector-handling machine and movable manipulator system (EGG ; EGG-FT-6008)

Conceptual design report for a Fusion Engineering Device sector-handling machine and movable manipulator system (EGG ; EGG-FT-6008)
紙図書
K.D. Watts, L.S. Masson, R.S. McPhersonIdaho National Engineering Lab.1982.
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An analysis of crud contribution to the maximum permissible release rates for reactor spent fuel shipments (SAND ; SAND-88-0054C; CONF-880601-20; TTC-0772; DE88005697)

An analysis of crud contribution to the maximum permissible release rates for reactor spent fuel shipments (SAND ; SAND-88-0054C; CONF-880601-20; TTC-0772; DE88005697)
紙図書
Sandoval, R.P., Sanders, T.L., Einziger, R.E. [et al.]Sandia National Labs., Pacific Northwest Lab., Oak Ridge National Lab., Idaho National Engineering Lab.1988.1.8.
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Summary of core damage frequency from internal initiators: Peach Bottom (Sandia report ; SAND-86-1567C; CONF-861102-12; TI86013310)

Summary of core damage frequency from internal initiators: Peach Bottom (Sandia report ; SAND-86-1567C; CONF-861102-12; TI86013310)
紙図書
Kolaczkowski, A.M., Lambright, J.A., Cathey, N.Sandia National Labs., Idaho National Engineering Lab., Science Applications International Corp.1986.01.
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Calculated thermal-hydraulic response for Semiscale Mod-3 Test S-07-6 using RELAP5: a new LWR system analysis code (CONF ; CONF-801002-11)

Calculated thermal-hydraulic response for Semiscale Mod-3 Test S-07-6 using RELAP5: a new LWR system analysis code (CONF ; CONF-801002-11)
紙図書
H.H. Kuo, V.H. Ransom, D.M. SniderIdaho National Engineering Lab.1980.
全国の図書館
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