-
2
-
-
0343819906
-
A participant-observer study of ergonomics in engineering design: How constraints drive design process
-
DOI 10.1016/S0003-6870(99)00017-4, PII S0003687099000174
-
Burns, C., &, Vicente, K. J., (2000). A participant-observer study of ergonomics in engineering design: How constraints drive design process. Applied Ergonomics, 31, 73-82. (Pubitemid 30035363)
-
(2000)
Applied Ergonomics
, vol.31
, Issue.1
, pp. 73-82
-
-
Burns, C.M.1
Vicente, K.J.2
-
3
-
-
0003611326
-
-
Hillsdale, NJ: Lawrence Erlbaum Associates Inc.
-
Card, S. K., Moran, T. P., &, Newell, A., (1983). The psychology of human-computer interaction. Hillsdale, NJ: Lawrence Erlbaum Associates Inc.
-
(1983)
The Psychology of Human-computer Interaction
-
-
Card, S.K.1
Moran, T.P.2
Newell, A.3
-
4
-
-
76249131728
-
Human-system interface challenges in nuclear power plant control rooms
-
July 2009, San Diego, CA, pp
-
Chang, J., Liao, H., &, Zeng, L., (2009). Human-system interface challenges in nuclear power plant control rooms. Proceedings of HCI (Human-Computer Interaction) International 2009, July 2009, San Diego, CA, pp. 729-737.
-
(2009)
Proceedings of HCI (Human-Computer Interaction) International 2009
, pp. 729-737
-
-
Chang, J.1
Liao, H.2
Zeng, L.3
-
5
-
-
4544328028
-
Assessment of human-machine interface design for a Chinese nuclear power plant
-
Chen, X., Zhou, Z., Gao, Z. G., Wu, W., Nakagawa, T., &, Matsuo, S., (2005). Assessment of human-machine interface design for a Chinese nuclear power plant. Reliability Engineering and System Safety, 87, 37-44.
-
(2005)
Reliability Engineering and System Safety
, vol.87
, pp. 37-44
-
-
Chen, X.1
Zhou, Z.2
Gao, Z.G.3
Wu, W.4
Nakagawa, T.5
Matsuo, S.6
-
6
-
-
79957938397
-
Designing to avoid human error consequences
-
Safety, and System Development, Paper Session 5
-
Chen-Wing, S. L. N., &, Davey, E. C., (1998). Designing to avoid human error consequences. Proceedings of the Workshop on Human Error, Safety, and System Development, Paper Session 5.
-
(1998)
Proceedings of the Workshop on Human Error
-
-
Chen-Wing, S.L.N.1
Davey, E.C.2
-
7
-
-
76249105670
-
Criteria for operator review of workplace changes
-
Toronto, Ontario, CA
-
Davey, E., (2000). Criteria for operator review of workplace changes. Canadian Nuclear Society Conference, Toronto, Ontario, CA.
-
(2000)
Canadian Nuclear Society Conference
-
-
Davey, E.1
-
10
-
-
32044448417
-
-
Idaho National Laboratory NUREG/CR-6883, U.S. Nuclear Regulatory Commission. Washington, DC
-
Idaho National Laboratory. (2005). The SPAR-H human reliability analysis method. NUREG/CR-6883, U.S. Nuclear Regulatory Commission. Washington, DC.
-
(2005)
The SPAR-H Human Reliability Analysis Method
-
-
-
11
-
-
79957939029
-
-
Institute of Nuclear Power Operations (INPO). (1999). Point Lepreau 1, 4/26/1999: Containment isolation system button-up during degassing of the degasser condenser [908-990426-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (1999). Point Lepreau 1, 4/26/1999: Containment isolation system button-up during degassing of the degasser condenser [908-990426-1]. Retrieved August 14, 2008, from
-
-
-
-
12
-
-
79957949018
-
-
Institute of Nuclear Power Operations (INPO). (2000). Gentilly 2, 11/26/2000: Recirculated service water diesel motor pump 7131-P36 damaged [851-001126-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2000). Gentilly 2, 11/26/2000: Recirculated service water diesel motor pump 7131-P36 damaged [851-001126-1]. Retrieved August 14, 2008, from
-
-
-
-
13
-
-
79957950131
-
-
Institute of Nuclear Power Operations (INPO). (2002a). Cooper 1, 2/12/2002: Unintended increase in reactor power due to misoperation of reactor recirculation pump speed control [298-020212-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2002a). Cooper 1, 2/12/2002: Unintended increase in reactor power due to misoperation of reactor recirculation pump speed control [298-020212-1]. Retrieved August 14, 2008, from
-
-
-
-
14
-
-
79957943728
-
-
Institute of Nuclear Power Operations (INPO). (2002b). Gentilly 2, 2/12/2002: Local radiological alert due to a moderator leak in upgrading plants [851-020212-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2002b). Gentilly 2, 2/12/2002: Local radiological alert due to a moderator leak in upgrading plants [851-020212-1]. Retrieved August 14, 2008, from
-
-
-
-
15
-
-
79957944606
-
-
Institute of Nuclear Power Operations (INPO). (2003a). Cernavoda 1, 6/12/2003: Inadvertent draining of in-service fire water tank 7140-TK1 results in start and damage of the diesel engine driven pump [121-030612-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2003a). Cernavoda 1, 6/12/2003: Inadvertent draining of in-service fire water tank 7140-TK1 results in start and damage of the diesel engine driven pump [121-030612-1]. Retrieved August 14, 2008, from
-
-
-
-
16
-
-
79957968118
-
-
Institute of Nuclear Power Operations (INPO). (2003b). Duane Arnold 1, 12/30/2003: High temperature in fuel pool because of procedure use problem [331-000111-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2003b). Duane Arnold 1, 12/30/2003: High temperature in fuel pool because of procedure use problem [331-000111-1]. Retrieved August 14, 2008, from
-
-
-
-
17
-
-
79957968817
-
-
Institute of Nuclear Power Operations (INPO). (2004a). Millstone 2, 3/15/2004: Automatic reactor scram after a steam generator feed pump trip [336-040315-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2004a). Millstone 2, 3/15/2004: Automatic reactor scram after a steam generator feed pump trip [336-040315-1]. Retrieved August 14, 2008, from
-
-
-
-
18
-
-
79957968352
-
-
Institute of Nuclear Power Operations (INPO). (2004b). Nine Mile Point 1, 5/4/2004: Two control rods scrammed during rod scram timing test [220-040504-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2004b). Nine Mile Point 1, 5/4/2004: Two control rods scrammed during rod scram timing test [220-040504-1]. Retrieved August 14, 2008, from
-
-
-
-
19
-
-
79957969043
-
-
Institute of Nuclear Power Operations (INPO). (2004c). Point Lepreau 1, 6/6/2004: Primary heat transport (PHT) thermal transient [908-040606-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2004c). Point Lepreau 1, 6/6/2004: Primary heat transport (PHT) thermal transient [908-040606-1]. Retrieved August 14, 2008, from
-
-
-
-
20
-
-
79957960533
-
-
Institute of Nuclear Power Operations (INPO). (2004c). Point Lepreau 1, 6/6/2004: Primary heat transport (PHT) thermal transient [908-040606-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2004c). Point Lepreau 1, 6/6/2004: Primary heat transport (PHT) thermal transient [908-040606-1]. Retrieved August 14, 2008, from
-
-
-
-
21
-
-
79957935988
-
-
Institute of Nuclear Power Operations (INPO). (2005b). Susquehanna 2, 5/27/2005: B circulating water pump shutdown instead of B condensate pump [388-050527-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2005b). Susquehanna 2, 5/27/2005: B circulating water pump shutdown instead of B condensate pump [388-050527-1]. Retrieved August 14, 2008, from
-
-
-
-
22
-
-
79957958121
-
-
Institute of Nuclear Power Operations (INPO). (2005c). Gentilly 2, 7/12/2005: 3481-TK2 tank draining and 3481-P1 and P2 pump cavitations [851-050530-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2005c). Gentilly 2, 7/12/2005: 3481-TK2 tank draining and 3481-P1 and P2 pump cavitations [851-050530-1]. Retrieved August 14, 2008, from
-
-
-
-
23
-
-
79957961873
-
-
Institute of Nuclear Power Operations (INPO). (2006). Perry 1, 7/9/2006: Reactor operation in unanalyzed region [440-060709-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2006). Perry 1, 7/9/2006: Reactor operation in unanalyzed region [440-060709-1]. Retrieved August 14, 2008, from
-
-
-
-
24
-
-
79957964672
-
-
Institute of Nuclear Power Operations (INPO). (2007a). Monticello, 3/14/2007: Half scram due to cold water transient during valve operation at Monticello Nuclear Generating Plant [263-070314-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2007a). Monticello, 3/14/2007: Half scram due to cold water transient during valve operation at Monticello Nuclear Generating Plant [263-070314-1]. Retrieved August 14, 2008, from
-
-
-
-
25
-
-
79957962536
-
-
Institute of Nuclear Power Operations (INPO). (2007b). Trillo 1, 11/28/2007: During routine tests, start-up of emergency diesel generator GY60 activated by reactor protection system [715-071128-1]. Retrieved August 14, 2008, from
-
Institute of Nuclear Power Operations (INPO). (2007b). Trillo 1, 11/28/2007: During routine tests, start-up of emergency diesel generator GY60 activated by reactor protection system [715-071128-1]. Retrieved August 14, 2008, from
-
-
-
-
26
-
-
53049086582
-
-
Basic safety principles for nuclear power plants (IAEA Safety Series No. 75-INSAG-3). Vienna, Austria: IAEA
-
International Atomic Energy Agency (IAEA). (1988). Basic safety principles for nuclear power plants (IAEA Safety Series No. 75-INSAG-3). Vienna, Austria: IAEA.
-
(1988)
International Atomic Energy Agency (IAEA)
-
-
-
27
-
-
0005025428
-
-
Human reliability analysis in probabilistic safety assessment for nuclear power plants: A safety practice (IAEA Safety Series No. 50-P-10). Vienna, Austria: IAEA
-
International Atomic Energy Agency (IAEA). (1996). Human reliability analysis in probabilistic safety assessment for nuclear power plants: A safety practice (IAEA Safety Series No. 50-P-10). Vienna, Austria: IAEA.
-
(1996)
International Atomic Energy Agency (IAEA)
-
-
-
29
-
-
79957966447
-
Models in process control
-
In T. IvergÃrd & B. Hunt (Eds.), (2nd ed., pp.) Boca Raton, FL: CRC Press.
-
IvergÃrd, T., &, Hunt, B., (2008). Models in process control. In, T. IvergÃrd, &, B. Hunt, (Eds.), Handbook of control room design and ergonomics: A perspective for the future (2nd ed., pp. 11-42) Boca Raton, FL: CRC Press.
-
(2008)
Handbook of Control Room Design and Ergonomics: A Perspective for the Future
, pp. 11-42
-
-
Ivergãrd, T.1
Hunt, B.2
-
30
-
-
0003747804
-
-
et al. New York: Pergamon Press.
-
Kemeny, J. G., Babbitt, B., Haggerty, P. E., Lewis, C., Marks, P. A., Marrett, C. B., et al. (1979). The need for change: The legacy of TMI-Report of the president's commission on the accident at Three Mile Island. New York: Pergamon Press.
-
(1979)
The Need for Change: The Legacy of TMI - Report of the President's Commission on the Accident at Three Mile Island
-
-
Kemeny, J.G.1
Babbitt, B.2
Haggerty, P.E.3
Lewis, C.4
Marks, P.A.5
Marrett, C.B.6
-
32
-
-
33750371219
-
An intelligent human-machine system based on an ecological interface design
-
Naito, N., Itoh, J., Monta, K., &, Makino, M., (1995). An intelligent human-machine system based on an ecological interface design. Nuclear Engineering and Design, 154, 97-108.
-
(1995)
Nuclear Engineering and Design
, vol.154
, pp. 97-108
-
-
Naito, N.1
Itoh, J.2
Monta, K.3
Makino, M.4
-
34
-
-
0001775576
-
Heuristic evaluation
-
In J. Nielsen & R. L. Mack (Eds.), New York: John Wiley & Sons.
-
Nielsen, J., (1994). Heuristic evaluation. In, J. Nielsen, &, R. L. Mack, (Eds.), Usability inspection methods New York: John Wiley & Sons.
-
(1994)
Usability Inspection Methods
-
-
Nielsen, J.1
-
35
-
-
58149402993
-
Categorization of action slips
-
Norman, D. A., (1981). Categorization of action slips. Psychological Review, 88, 1-15.
-
(1981)
Psychological Review
, vol.88
, pp. 1-15
-
-
Norman, D.A.1
-
37
-
-
0020749236
-
Skills, rules, and knowledge: Signals, signs, and symbols, and other distinctions in human performance models
-
Rasmussen, J., (1983). Skills, rules, and knowledge: Signals, signs, and symbols, and other distinctions in human performance models. IEEE Transactions on Systems, Man, and Cybernetics, SMC 13, 257-266. (Pubitemid 13591183)
-
(1983)
IEEE Transactions on Systems, Man and Cybernetics
, vol.SMC-13
, Issue.3
, pp. 257-266
-
-
Rasmussen Jens1
-
38
-
-
0004223940
-
-
Cambridge: Cambridge University Press.
-
Reason, J. T., (1990). Human error. Cambridge: Cambridge University Press.
-
(1990)
Human Error
-
-
Reason, J.T.1
-
41
-
-
36749097361
-
Human-automation interaction
-
Sheridan, T. B., &, Parasuraman, R., (2005). Human-automation interaction. Reviews of Human Factors and Ergonomics, 1, 89-129.
-
(2005)
Reviews of Human Factors and Ergonomics
, vol.1
, pp. 89-129
-
-
Sheridan, T.B.1
Parasuraman, R.2
-
42
-
-
0011505475
-
-
Berlin: International Institute of Management.
-
Sorge, A., Hartmann, G., Warner, M., &, Nicholas, I., (1982). Microelectronics and manpower in manufacturing. Berlin: International Institute of Management.
-
(1982)
Microelectronics and Manpower in Manufacturing
-
-
Sorge, A.1
Hartmann, G.2
Warner, M.3
Nicholas, I.4
-
43
-
-
0003786918
-
-
(NUREG/CR-1278, US Nuclear Regulatory Commission). Washington, DC
-
Swain, A. D., &, Guttman, H. E., (1983). Handbook of human reliability analysis with emphasis on nuclear power plant applications (NUREG/CR-1278, US Nuclear Regulatory Commission). Washington, DC.
-
(1983)
Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications
-
-
Swain, A.D.1
Guttman, H.E.2
-
44
-
-
79957958937
-
-
ATHEANA user's guide (NUREG-1880). Washington, DC: NRC
-
U.S. Nuclear Regulatory Commission (NRC). (2007a). ATHEANA user's guide (NUREG-1880). Washington, DC: NRC.
-
(2007)
U.S. Nuclear Regulatory Commission (NRC)
-
-
-
45
-
-
79957958937
-
-
Human-system interface design review guidelines (NUREG-0700, Revision 2). Washington, DC: NRC
-
U.S. Nuclear Regulatory Commission (NRC). (2007b). Human-system interface design review guidelines (NUREG-0700, Revision 2). Washington, DC: NRC.
-
(2007)
U.S. Nuclear Regulatory Commission (NRC)
-
-
-
46
-
-
0004015006
-
-
New York: Addison-Wesley.
-
Wickens, C. D., Gordon, S. E., &, Liu, Y., (1998). An introduction to human factors to engineering. New York: Addison-Wesley.
-
(1998)
An Introduction to Human Factors to Engineering
-
-
Wickens, C.D.1
Gordon, S.E.2
Liu, Y.3
|