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Nuclear reactor physics and engineering

Nuclear reactor physics and engineering
紙図書
John C. LeeJohn Wiley &Sons2020.
全国の図書館

Bridging the multimodal gap : from theory to practice : pbk

Bridging the multimodal gap : from theory to practice : pbk
紙図書
edited by Santosh Khadka, J. C. LeeUtah State University Pressc2019
全国の図書館
  • 著者標目Khadka, Santosh Lee, J. C.

Designing and implementing multimodal curricula and programs : hbk

Designing and implementing multimodal curricula and programs : hbk
紙図書
edited by J.C. Lee, Santosh KhadkaRoutledge2018
全国の図書館
  • 著者標目Lee, J. C. Khadka, Santosh

Testing of the RL10B-2 carbon-carbon nozzle extension AIAA-98-3363

Testing of the RL10B-2 carbon-carbon nozzle extension AIAA-98-3363
紙規格・テクニカルリポート類
Ellis, R. A, Lee, J. C, Payne, F. M, Lacoste, M, Lacombe, A, Joyez, P1998<M-AIAA-98-3363>
国立国会図書館

Preliminary study of current multimedia information technology ANL/DIS/CP-91926 DE97 003762 CONF-9704871

Preliminary study of current multimedia information technology ANL/DIS/CP-91926 DE97 003762 CONF-9704871
マイクロ規格・テクニカルリポート類
Lee, J. C1997<LS-DE97/003762>
国立国会図書館

Role of the body mount on the passenger compartment response of a frame/body structured vehicle in frontal crash SAE-980861

Role of the body mount on the passenger compartment response of a frame/body structured vehicle in frontal crash SAE-980861
紙規格・テクニカルリポート類
Miller, P. Michael, II, Lee, J. C, Murthy, R. Krishna, Cheng, James1998<M-SAE-980861>
国立国会図書館

Performance evaluation for conflict resolution transaction management approach ANL/DIS/CP-92960 DE97 052986 CONF-9710471

Performance evaluation for conflict resolution transaction management approach ANL/DIS/CP-92960 DE97 052986 CONF-9710471
マイクロ規格・テクニカルリポート類
Lee, J. C, Henschen, L. J1997<LS-DE97/052986>
国立国会図書館

Object-oriented hypermedia application system ANL/DIS/CP-89555 DE96 008449 CONF-96051561

Object-oriented hypermedia application system ANL/DIS/CP-89555 DE96 008449 CONF-96051561
マイクロ規格・テクニカルリポート類
Lee, J. C, McCusker-Whiting, M, Swietlik, C. E1996<LS-DE96/008449>
国立国会図書館

Hardware-in-the-loop simulation for ABS SAE-980244

Hardware-in-the-loop simulation for ABS SAE-980244
紙規格・テクニカルリポート類
Suh, M. W, Seok, C. S, Kim, Y. J, Chung, J. H, Kim, S. M, Lee, J. C, Lee. S. I1998<M-SAE-980244>
国立国会図書館

Toward automated document reformatting: A SGML markup system ANL/DIS/CP-88662 DE96 007077 CONF-96031381

Toward automated document reformatting: A SGML markup system ANL/DIS/CP-88662 DE96 007077 CONF-96031381
マイクロ規格・テクニカルリポート類
Lee, J. C, Swietlik, C. E1996<LS-DE96/007077>
国立国会図書館

Development of a carbon-carbon translating nozzle extension for the RL10B-2 liquid rocket engine AIAA-97-2672

Development of a carbon-carbon translating nozzle extension for the RL10B-2 liquid rocket engine AIAA-97-2672
紙規格・テクニカルリポート類
Ellis, R. A, Lee, J. C, Payne, F. M, Lacoste, M, Joyez, P1997<M-AIAA-97-2672>
国立国会図書館

Analysis of burnable poison in Ford Nuclear Reactor fuel to extend fuel lifetime. Final report, August 1, 1994--September 29, 1996. PROGRESS REPT DOE/ER/76027-1 DE97 003458

Analysis of burnable poison in Ford Nuclear Reactor fuel to extend fuel lifetime. Final report, August 1, 1994--September 29, 1996. PROGRESS REPT DOE/ER/76027-1 DE97 003458
マイクロ規格・テクニカルリポート類
Burn, R. R, Lee, J. C1996<LS-DE97/003458>
国立国会図書館

Simulation-based diagnostics and control for nuclear power plants. Final report, April 15, 1992--April 14, 1995. PROGRESS REPT DOE/ER/75712-3 DE96 001985

Simulation-based diagnostics and control for nuclear power plants. Final report, April 15, 1992--April 14, 1995. PROGRESS REPT DOE/ER/75712-3 DE96 001985
マイクロ規格・テクニカルリポート類
Lee, J. C1995<LS-DE96/001985>
国立国会図書館

User's manual ACE/ONED (Version 1.0) KAERI/TR-631/96 DE96 634437

User's manual ACE/ONED (Version 1.0) KAERI/TR-631/96 DE96 634437
マイクロ規格・テクニカルリポート類
Lee, K. B, Lee, J. C, Song, J. S, Lee, C. K, Ji, S. K1996<LS-DE96/634437>
国立国会図書館

Buffer reduction in an attribute-based concurrent transaction processing system ANL/DIS/CP-86615 DE95 014224 CONF-95071351

Buffer reduction in an attribute-based concurrent transaction processing system ANL/DIS/CP-86615 DE95 014224 CONF-95071351
マイクロ規格・テクニカルリポート類
Henschen, L. J, Lee, J. C1995<LS-DE95/014224>
国立国会図書館

Probabilistic techniques using Monte Carlo sampling for multi- component system diagnostics ANL/IFR/CP-85456 DE95 012283 CONF-95042025

Probabilistic techniques using Monte Carlo sampling for multi- component system diagnostics ANL/IFR/CP-85456 DE95 012283 CONF-95042025
マイクロ規格・テクニカルリポート類
Aumeier, S. E, Lee, J. C, Akcasu, A. Z1995<LS-DE95/012283>
国立国会図書館

Use of silicide fuel in the Ford Nuclear Reactor - to lengthen fuel element lifetimes ANL/TD/CP-88124 DE96 005087

Use of silicide fuel in the Ford Nuclear Reactor - to lengthen fuel element lifetimes ANL/TD/CP-88124 DE96 005087
マイクロ規格・テクニカルリポート類
Bretscher, M. M, Snelgrove, J. L, Burn, R. R, Lee, J. C1995<LS-DE96/005087>
国立国会図書館

Forwards revised "Rept of Reactor Operation for Jan-Dec 1998 for Ford Nuclear Reactor Michigan Memorial - Phoenix Project Univ of MI,Ann Arbor," correcting omission of Section 5.0.

Forwards revised "Rept of Reactor Operation for Jan-Dec 1998 for Ford Nuclear Reactor Michigan Memorial - Phoenix Project Univ of MI,Ann Arbor," correcting omission of Section 5.0.
紙図書
LEE, J. C.MICHIGAN, UNIV. OF, ANN ARBOR, MI1999/05/11.
全国の図書館
  • 著者標目LEE, J. C.

RO update:on 981028,reactor was shutdown upon discovery that RB ventilation dampers would not automatically close.Damper cylinder was repaired on 981102 & reactor operation resumed on 981103.

RO update:on 981028,reactor was shutdown upon discovery that RB ventilation dampers would not automatically close.Damper cylinder was repaired on 981102 & reactor operation resumed on 981103.
紙図書
LEE, J. C.MICHIGAN, UNIV. OF, ANN ARBOR, MI1998/11/25.
全国の図書館
  • 著者標目LEE, J. C.

RO 20:on 980925,Reactor Operators made error at Ford Nuclear Reactor in implementing calorimetry procedures to raise power level.Upon discovery of error made in linear level setpoint reactor power was reduced by 1% to compensate.

RO 20:on 980925,Reactor Operators made error at Ford Nuclear Reactor in implementing calorimetry procedures to raise power level.Upon discovery of error made in linear level setpoint reactor power was reduced by 1% to compensate.
紙図書
LEE, J. C.MICHIGAN, UNIV. OF, ANN ARBOR, MI1998/10/09.
全国の図書館
  • 著者標目LEE, J. C.
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