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nuclear fuel elements

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View Engineering Separations Unit Operations for Nuclear Processing By Reid Peterson

Engineering Separations Unit Operations for Nuclear Processing

Engineering Separations Unit Operations for Nuclear Processing

By Reid Peterson

View Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2 By V. A. Vinogradov

Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2

Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2

By V. A. Vinogradov

View Analysis of spent fuel heatup following loss of water in a spent fuel pool By H. P. Nourbakhsh

Analysis of spent fuel heatup following loss of water in a spent fuel pool

Analysis of spent fuel heatup following loss of water in a spent fuel pool

By H. P. Nourbakhsh

View Monitoring Nuclear Weapons and Nuclear-Explosive Materials By National Research Council,Policy and Global Affairs,Committee on International Security and Arms Control

Monitoring Nuclear Weapons and Nuclear-Explosive Materials

Monitoring Nuclear Weapons and Nuclear-Explosive Materials

By National Research Council,Policy and Global Affairs,Committee on International Security and Arms Control

View Nuclear fuel elements By Brian R. T. Frost
Cover of Nuclear fuel elements by brian r. t. frost

Nuclear fuel elements

By Brian R. T. Frost

View Nuclear heat transport By M. M. El-Wakil
Cover of Nuclear heat transport by m. m. el-wakil

Nuclear heat transport

By M. M. El-Wakil

View Burn-up determination by high resolution gamma spectrometry By Ronald S. Forsyth

Burn-up determination by high resolution gamma spectrometry

Burn-up determination by high resolution gamma spectrometry

By Ronald S. Forsyth

View Fundamental aspects of nuclear reactor fuel elements By Donald R. Olander
Cover of Fundamental aspects of nuclear reactor fuel elements by donald r. olander

Fundamental aspects of nuclear reactor fuel elements

By Donald R. Olander

View Back end of the nuclear fuel cycle By International Symposium on the Back End of the Nuclear Fuel Cycle : Strategies and Options (1987 Vienna, Austria)

Back end of the nuclear fuel cycle

Back end of the nuclear fuel cycle

By International Symposium on the Back End of the Nuclear Fuel Cycle : Strategies and Options (1987 Vienna, Austria)

View Nuclear Rocket Engine Reactor By Anatoly Lanin
Cover of Nuclear Rocket Engine Reactor by anatoly lanin

Nuclear Rocket Engine Reactor

By Anatoly Lanin

View Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant By Christopher Fred Boyd

Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant

Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant

By Christopher Fred Boyd

View Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency)) By Iaea

Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))

Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))

By Iaea

View Scientific Issues in Fuel Behavior: A Report by an Nea Nuclear Science Committee Task Force By Nea
Cover of Scientific Issues in Fuel Behavior: A Report by an Nea Nuclear Science Committee Task Force by nea

Scientific Issues in Fuel Behavior: A Report by an Nea Nuclear Science Committee Task Force

By Nea

View Illicit trafficking in nuclear materials By Bruce Hoffman

Illicit trafficking in nuclear materials

Illicit trafficking in nuclear materials

By Bruce Hoffman

View Proceedings of the NEA Seminar on the Storage of Spent Fuel Elements, Madrid, June, 1978 = By NEA Seminar on the Storage of Spent Fuel Elements (1978 Madrid, Spain)

Proceedings of the NEA Seminar on the Storage of Spent Fuel Elements, Madrid, June, 1978 =

Proceedings of the NEA Seminar on the Storage of Spent Fuel Elements, Madrid, June, 1978 =

By NEA Seminar on the Storage of Spent Fuel Elements (1978 Madrid, Spain)

View MTR-type fuel element model experiments at reactor DR 3 By Ingv Rasmussen

MTR-type fuel element model experiments at reactor DR 3

MTR-type fuel element model experiments at reactor DR 3

By Ingv Rasmussen

View Ceramic fuel elements By Robert B. Holden

Ceramic fuel elements

Ceramic fuel elements

By Robert B. Holden

View Topical Meeting on Advances in Fuel Management, March 2-5, 1986, Pinehurst Hotel & Country Club, Pinehurst, North Carolina By Topical Meeting on Advances in Fuel Management (1986 Pinehurst)
Cover of Topical Meeting on Advances in Fuel Management, March 2-5, 1986, Pinehurst Hotel & Country Club, Pinehurst, North Carolina by topical meeting on advances in fuel management (1986 pinehurst)

Topical Meeting on Advances in Fuel Management, March 2-5, 1986, Pinehurst Hotel & Country Club, Pinehurst, North Carolina

By Topical Meeting on Advances in Fuel Management (1986 Pinehurst)

View Building a nuclear bomb By United States. Congress. House. Committee on Homeland Security. Subcommittee on the Prevention of Nuclear and Biological Attack

Building a nuclear bomb

Building a nuclear bomb

By United States. Congress. House. Committee on Homeland Security. Subcommittee on the Prevention of Nuclear and Biological Attack

View COBRA-IV comparison with the Ward 11:1 scale LMFBR air flow tests By K. L Basehore

COBRA-IV comparison with the Ward 11:1 scale LMFBR air flow tests

COBRA-IV comparison with the Ward 11:1 scale LMFBR air flow tests

By K. L Basehore

View Probability and consequences of misloading fuel in a PWR By David J. Diamond

Probability and consequences of misloading fuel in a PWR

Probability and consequences of misloading fuel in a PWR

By David J. Diamond

View Post-irradiation examination of overheated fuel bundles By D. F. Sears

Post-irradiation examination of overheated fuel bundles

Post-irradiation examination of overheated fuel bundles

By D. F. Sears

View Transient-overpower test E8 on FFTE-type low-power-irradiated fuel By Argonne National Laboratory. Reactor Analysis and Safety Division

Transient-overpower test E8 on FFTE-type low-power-irradiated fuel

Transient-overpower test E8 on FFTE-type low-power-irradiated fuel

By Argonne National Laboratory. Reactor Analysis and Safety Division

View Assessment of grade H-451 graphite for replaceable fuel and reflector elements in HTGR By G. B. Engle

Assessment of grade H-451 graphite for replaceable fuel and reflector elements in HTGR

Assessment of grade H-451 graphite for replaceable fuel and reflector elements in HTGR

By G. B. Engle