United Kingdom
Problems experienced during operation of the prototype fast reactor, Dounreay, 1974-1994
Cruickshank, A.; Judd, A.M. (British Nuclear Fuels Ltd., Risley, Warrington (United Kingdom))
IAEA-TECDOC--1180, pp:16-48
Creep/fatigue damage prediction of fast reactor components using shakedown methods
Buckthorpe, D.E. (NNC Ltd, Knutsford, Cheshire (United Kingdom))
IAEA-TECDOC--933, pp:47-73
BNFL's view of the thorium development programme
Wilson, P.D. (British Nuclear Fuels plc, Sellafield, Seascale (United Kingdom))
IAEA-TECDOC--1319, pp:60-68
Advanced fuel technology - A UK perspective
Bull, A.J. (British Nuclear Fuels plc, Preston (UK). Springfields Works)
IAEA-TECDOC--577, pp:62-65
A review of the United Kingdom fast reactor programme 1993-1994
Bramman, J. (AEA Technology, Risley (United Kingdom))
IAEA-TECDOC--791, pp:64-68
Acoustic leak detection experiments performed in PFR, March 1993 to June 1994
Currie, R. (Reactor Technology Dept., Dounreay (United Kingdom))
IAEA-TECDOC--946, pp:65-78
High power accelerator developments at the Rutherford Appleton Laboratory
P. Drumm (CLRC Rutherford Appleton Laboratory, Chilton, Didcot, United Kingdom)
IAEA-TECDOC--1365, pp:65-69
1995 benchmark data based on experimental results from the prototype fast reactor at Dounreay
Currie, R.;Wright, P.J.;Widdowson, I.R.;Ramsay, P.;Shallcross, R.E. (AEA Technology, Risley (United Kingdom))
IAEA-TECDOC--946, pp:79-98
Analysis methods for predicting the behaviour of isolators and formulation of simplified models for use in predicting response of structures to earthquake type input
Tun Abdul Razak Research Centre (United Kingdom)
IAEA-TECDOC--1288, pp:79-103
A review of the United Kingdom fast reactor programme
Bramman, J. (AEA Technology, Risley (United Kingdom). Reactor Services)
IAEA-TECDOC--741, pp:82-84
A simple procedure for the combination of fuel pin, sub-assembly and reactor uncertainties in fast reactor clad hot spot temperature assessment
Linning, D.L. (UKAEA Reactor Group, Risley)
IAEA-TECDOC--166, pp:85-88
Multiaxial creep-fatigue rules
Spindler, M.W.; Hales, R.; Ainsworth, R.A. (Nuclear Electric plc, Barnwood (United Kingdom))
IAEA-TECDOC--933, pp:87-96
Hot-spot analysis procedures for fast reactors
Linning, D.L.; McAreavey, G.; Rowlinson, B. (UKAEA Reactor Group, Risley)
IAEA-TECDOC--166, pp:89-109
The objectives of design stage hot-spot analysis
Gatley, J.A. (Nuclear Power Group Ltd., Risley (UK))
IAEA-TECDOC--166, pp:110-113
UK development of a strain based creep-fatigue assessment procedure for fast reactor design
Picker, C. (AEA Technology, Risley (United Kingdom))
IAEA-TECDOC--933, pp:131-169
Preliminary studies of the arisings and treatment of secondary wastes in waste partitioning schemes
Arm, S.T.; Bush, R.P.; Mills, A.L. (AEA Technology, Harwell (United Kingdom))
IAEA-TECDOC--783, pp:177-181
A review of the UK fast reactor programme
Picker, C. (AEA Technology plc., Risley, Warrington, Cheshire (United Kingdom));Ainsworth, K.F. (British Nuclear Fuels plc., Risley, Warrington, Cheshire (United Kingdom))
IAEA-TECDOC--1015, pp:191-197
A review of the UK fast reactor programme
Ainsworth, K.F. (British Nuclear Fuels plc, Risley (United Kingdom)); Picker, C. (AEA Technology, Risley (United Kingdom))
IAEA-TECDOC--876, pp:208-217
Benchmark on tee junction: Fatigue damage analysis
Lewis, M.W.J. (AEA Technology pls (United Kingdom))
IAEA-TECDOC--1318, pp:227-253
Assessment of creep-fatigue damage using the UK strain based procedure
Bate, S.K. (AEA Technology plc, Plant Support Services, Risley, Warrington, Cheshire (United Kingdom))
IAEA-TECDOC--933, pp:229-241
Creep-fatigue assessment of a thermina test specimen using the R5 procedure
Booth, P.; Budden, P.J. (Nuclear Electric plc, Barnwood (United Kingdom)); Bate, S.K. (AEA Technology, Risley (United Kingdom))
IAEA-TECDOC--933, pp:261-279
Potential advantages and drawbacks of the thorium fuel cycle in relation to current practice: A BNFL view
Wilson, P.D. (BNFL, Sellafield, Seascale (United Kingdom)); Ainsworth, K.F. (BNFL, Risley, Warrington, Cheshire (United Kingdom))
IAEA-TECDOC--1319, pp:305-315
Development requirements in reprocessing thorium fuels
Wilson, P.D. (British Nuclear Fuels plc, Sellafield, Seascale, Cumbria (United Kingdom))
IAEA-TECDOC--1319, pp:343-355
Thermal striping benchmark exercise: Thermal hydraulic analysis of the Phenix fast reactor secondary pipework T-junction
Stainsby, R.; Martin, D. (AEA Technology plc, Risley, Warrington, Cheshire (United Kingdom))
IAEA-TECDOC--1318, pp:2060-226
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