United Kingdom
Irradiation damage in graphite. The works of Professor B.T. Kelly
Marsden, B.J. (AEA Technology, Risley (United Kingdom). Graphite Section)
IAEA-TECDOC--901, pp:17-46
Graphite core design in UK reactors
Davies, M.W. (NNC Ltd, Knutsford, Cheshire (United Kingdom). Nuclear Engineering
Div.)
IAEA-TECDOC--901, pp:47-56
The decommissioning of commercial magnox gas cooled
reactor power stations in the United Kingdom
Holt, G. (Magnox Electric plc. Berkeley Centre, Berkeley (United Kingdom))
IAEA-TECDOC--1043, pp:71-83
Progress in the development of tooling and dismantling
methodologies for the Windscale advanced gas cooled
reactor (WAGR)
Cross, M.T.; Wareing, M.I.; Dixon, C.
(Decommissioning and Waste Management
(North) Group, AEA Technology plc,
Windscale, Seascale, Cumbria (United
Kingdom))
IAEA-TECDOC--1043, pp:85-104
The development of direct core monitoring in Nuclear Electric plc
Curtis, R.F.; Jones, S. (Berkeley Technology Centre, Nuclear Electric plc., Berkeley
(United Kingdom). Remote Operation Section) Reed, J.; Wickham, A.J. (Berkeley Technology Centre, Nuclear Electric plc., Berkeley (United Kingdom). Fuel and Core
Section)
IAEA-TECDOC--901, pp:91-104
Application of a method for assessing probability of graphite core brick failure
Judge, R.C.B. (AEA Technology, Harwell (United Kingdom))
IAEA-TECDOC--901, pp:117-124
AGR core safety assessment methodologies
McLachlan, N.; Reed, J.; Metcalfe, M.P. (Nuclear
Electric plc, Berkeley (United Kingdom). Berkeley
Technology Centre)
IAEA-TECDOC--901, pp:125-136
Assessments of the stresses and deformations in an RBMK graphite moderator brick
Jones, C.J.; Davies, M.A.; Marsden, B.J. (AEA Technology, Risley (United Kingdom));
Bougaenko, S.E.; Baldin, V.D.; Demintievski, V.N.; Rodtchenkov, B.S.; Sinitsyn, E.N. (Research and Development Inst. of Power Engineering (RDIPE), Moscow (Russian Federation))
IAEA-TECDOC--901, pp:137-149
The seismic assessment of radially keyed graphite moderator cores
Steer, A.G.; Payne, J.F.B. (Nuclear Electric plc,
Berkeley (United Kingdom). Berkeley Technology Centre)
IAEA-TECDOC--901, pp:151-159
Radiolytic graphite oxidation revisited
Minshall, P.C.; Sadler, I.A.; Wickham, A.J.
(Nuclear Electric plc, Berkeley (United Kingdom).
Berkeley Technology Centre)
IAEA-TECDOC--901, pp:181-191
Gas cooled reactor decommissioning. Packaging of waste
for disposal in the United Kingdom deep repository
Barlow, S.V.; Wisbey, S.J.; Wood, P. (United Kingdom Nirex Ltd, Oxfordshire (United Kingdom))
IAEA-TECDOC--1043, pp:203-211
Evaluation of graphite safety issues for the British production
piles at Windscale: Graphite sampling in preparation for the
dismantling of Pile 1 and the further safe storage of Pile 2
Marsden, B.J.; Preston, S.D.; Wickham, A.J.
(AEA Technology plc, Warrington (United Kingdom)); Tyson, A. (Process and Radwaste Chemistry Dept., AEA TEchnology plc, Windscale (United Kingdom))
IAEA-TECDOC--1043, pp:213-223
Influence of air oxidation on thermal shock resistances of nuclear carbon materials
Kurumada, A.; Oku, T. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Harada,
K. (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Kawamata, K. (Ibaraki Univ., Ibaraki (Japan). Faculty Engineering); Sato, S. (Iwaki Meisei Univ., Fukushima (Japan)); Hiraoka, T. (Tokyo Tanso Co. Ltd., Kagawa (Japan)); McEnaney, B. (Bath Univ. (United Kingdom). School of Materials Science)
IAEA-TECDOC--901, pp:215-224
Graphite core stability during 'care and maintenance' and
'safe storage'
Wickham, A.J.; Marsden, B.J. (AEA Technology plc, Warrington, Cheshire (United Kingdom)); Sellers, R.M. (Liabilities and Decommissioning Div., Magnox Electric plc, Berkeley Centre, Berkeley, Gloucestershire (United Kingdom)); Pilkington, N.J. (AEA Technology plc, Harwell, Didcot, Oxfordshire (United Kingdom))
IAEA-TECDOC--1043, pp:225-232
Calculation of neutron fluxes and radioactivities in and
around the Tokai-1 reactor pressure vessel
Currie, I.D.; Smith, P.N. (NNC Ltd,
Knutsford (United Kingdom)); Shirakawa, M.
(Fuji Electric Co., Ltd, Tokyo (Japan));
Yamamoto, T. (Japan Atomic Power Co. (Japan))
IAEA-TECDOC--1043, pp:239-256
Blunt indentation of core graphite
Hartley, M.; McEnaney, B. (Bath Univ. (United Kingdom). School of Materials Science)
IAEA-TECDOC--901, pp:263-273
A systematic study of acoustic emission from nuclear graphites
Neighbour, G.B.; McEnaney, B. (Bath Univ.
(United Kingdom). School of Materials Science)
IAEA-TECDOC--901, pp:299-311
The interaction of strain, the coefficient of thermal expansion and dimensional changes in graphite
Marsden, B.J.; Preston, S.D.; Davies, M.A. (AEA
Technology, Risley (United Kingdom));
McLachlan, N. (Nuclear Electric plc, Berkeley
(United Kingdom). Berkeley Technology Centre)
IAEA-TECDOC--901, pp:313-319
Gaseous diffusion and pore structure in nuclear graphites
Mays, T.J.; McEnaney, B.; Kelly, B.T. (Bath Univ. (United Kingdom). School of Materials
Science)
IAEA-TECDOC--901, pp:329-335
Operating Experience with the Dragon High Temperature Reactor Experiment
R. A. Simon, DRAGON Operation Branch/EC (retired), Belgium and P. D. Capp, DRAGON Operations Branch/UKAEA (retired), United Kingdom
HTR-2002, pp:1-6
The relation between irradiation induced dimensional change and the coefficient of thermal expansion: A new look
G. Hall, B. J. Marsden, A. Fok and J. Smart, Nuclear Graphite Technology Group, University of Manchester, United Kingdom
HTR-2002, pp:1-5
A High Temperature Reactor for Ship Propulsion
P. Lobet, R. Seigel, Ecole de Application Militaries de l Energie Atomique, France and A. C. Thompson, R. J. Beadnell and P. A. Beeley, HMS Sultan, Nuclear Department, United Kingdom
HTR-2002, pp:1-6
Analysis of Operational Transients in a Fluidized Bed Nuclear Reactor
A. Agung, D. Lathouwers, T. H. J. J. van der Hagen, H. van Dam, Interfaculty Research Institute, Delft University of Technology, The Netherlands and C. C. Pain, C. R. E. Oliviera, A. J. H. Goddard, Department of Earth Science and Engineering, Imperial College of Science, Technology and Medicine, United Kingdom
HTR-2002, pp:1-5
EC-Funded Project (HTR-L) for the Definition of a European Safety Approach for HTR’s
S. Ehster, FRAMATOME-ANP, France, M. T. Dominguez, Empresarios Agrupados Internacional SA, I. Coe, NNC Ltd., United Kingdom, G. Brinkmann, FRAMATOME-ANP GmbH, Germany, W. von Lensa, Research Centre Jülich, Germany, W. van der Mheen, Nuclear Research and Consultancy Group, The Netherlands, C. Allessandroni, Ansaldo Nucleare, Italy and J. Pirson, Tractebel Energy Engineering, Belgium
HTR-2002, pp:1-6
Graphite Materials Testing in the ATR for Lifetime management of Magnox Reactors
S. B. Grover, Idaho National Engineering and Environmental Laboratory, USA and M. P. Metcalfe, British Nuclear Fuels plc, Research and Technology, Berkeley Centre, United Kingdom
HTR-2002, pp:1-7
Results From EU 5Th Framework HTR Projects HTR-M & HTR-M1
D.E. Buckthorpe,NNC Ltd, Knutsford, UNITED KINGDOM plus contributions from the HTR-M & M1 partners
HTR-2004, pp:1-15
Fracture Behaviour Of Nuclear Graphite
Andrew Hodgkins, James Marrow, Paul Mummery, Laurent Babout, Manchester Materials Science Centre, Manchester, UNITED KINGDOM; Barry Marsden, Alex Fok, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM
HTR-2004, pp:1-5
The Use Of X-Ray Microtomography To Determine Relationships Between Microstructure and Mechanical Behaviour of Nuclear Graphite
Laurent Babout, Andrew Hodgkins, Richard Dewhurst, T.James Marrow, Paul M. Mummery, School of Materials, University of Manchester, Manchester, UNITED KINGDOM; Alex Fok, Barry Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM
HTR-2004, pp:1-10
The Relationship Between Strength and Modulus In Nuclear Graphite
S.L. Fok, Barry Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM; T.James Marrow, Paul M. Mummery, Manchester Materials Science Centre, University of Manchester, Manchester, UNITED KINGDOM
HTR-2004, pp:1-9
Stress Wave Propagation Following Primary Cracking In Cylindrical Specimens of Brittle Materials
Wei-jing He, Shi-ping Yao, Siu-lun Fok, J.D. Jackson, J.R. Wright, Nuclear Graphite Research Group, Manchester, UNITED KINGDOM
HTR-2004, pp:1-10
The Effect of Softening on The Predicted Strength of Brittle Materials Using a Continuum Damage Mechanics Failure Model
Li Shi, Haiyan Li, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA; S.L. Fok, B.J. Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM
HTR-2004, pp:1-8
An Experimental Study on The Porosity Networks In Nuclear Graphite
S.L. Fok, B.J. Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM; Libin Sun, Institute of Nuclear and New Energy Technology, Beijing, CHINA; James Marrow, Andrew Hodgkins, Manchester Materials Science Centre, Manchester, UNITED KINGDOM
HTR-2004, pp:1-7
Radioactive Waste Arising from HTR
J. Fachinger, H. Brücher, W. von Lensa, Institute for Safety Research and Reactor Technology, Forschungszentrum Jülich, Jülich, GERMANY; J.M. Turner, A. Nuttall, NNC Limited, Knutsford, UNITED KINGDOM; C. Bourdeloie, CEA Saclay, Gif sur Yvette, FRANCE; G. Brinkmann, Framatome-DE KWU NGES3, Erlangen, GERMANY
HTR-2004, pp:1-13
Criteria for the selection of graphites for HTR integral block fuel elements
Knowles, A.N. (UKAEA, Northern Div., Risley, Warrington, UK)
IWGHTR--3, pp:7-20
The uncertain future for nuclear graphite disposal: Crisis or opportunity?
A.J. Wickham, G.B. Neighbour, M. Dubourg
TCM-Manchester99, pp:13-28
Advanced gas-cooled reactors (AGR)
Yeomans, R.M. (South of Scotland Electricity Board, Hunterston Power Station, West Kilbride, Ayshire, UK)
IWGGCR--1, pp:17-38
The integrity of CAGR moderator bricks
Prince, N. (UKAEA Risley Nuclear Power Development establishment); Brocklehurst, J.E
IWGGCR--11, pp:20-28
The radiological environmental impact of a commercial advanced gas cooled reactor
Dawson, J.W. (Central Electricity Generating Board, Barnwood (UK).
Generation Development and Construction Div.); Youell, F.P. (National
Nuclear Corp. Ltd., Knutsford (UK))
IAEA-TECDOC--358, pp:21-33
A comparison of predicted and measured graphite moderator behaviour during 16 years' operation of the Windscale advanced gas-cooled reactor
Prince, N. (Thermal Reactor Development Directorate, UKAEA, Northern Div., Risley, Warrington, UK)
IWGHTR--3, pp:21-35
The assessment of the integrity of AGR core during an earthquake
Smith, C.R. (National Nuclear Corp. Ltd., Risley (UK))
IWGGCR--11, pp:29-36
Design, construction and operating experience of boilers at Wylfa power station
Razzell, R.N. (Wylfa Power Station, Central Electricity Generating Board, Gwynedd (United Kingdom))
IWGGCR--15, pp:29-39
Technical assessment of the significance of Wigner energy for disposal of graphite wastes from the Windscale piles
R.M. Guppy, J. McCarthy, S.J. Wisbey
TCM-Manchester99, pp:29-46
Design and performance of the helically coiled boilers of two AGR power stations in the United Kingdom
El-Nagdy, M.; Papa, A.D. (Babcock Energy Ltd., London (United Kingdom))
IWGGCR--15, pp:39-48
Graphite structure and its relation to mechanical engineering design
Brocklehurst, J.E.; Kelly, B.T. (UKAEA Springfields Nuclear Power Development Labs.)
IWGHTR--3, pp:42-51
The evaluation of occupational exposure on a commercial advanced gas-cooled reactor
Dawson, J.W. (Central Electricity Generating Board, Barnwood (UK).
Generation Development and Construction Div.); Youell, F.P. (National
Nuclear Corp. Ltd., Knutsford (UK)); Edwards, J. (Hinkley Point 'B' Power
Station, Bridgewater (UK))
IAEA-TECDOC--358, pp:47-60
Development of CO2 circulators
Donaldson, J. (James Howden and Co. Ltd, Renfrew (UK))
IWGGCR--17, pp:47-53
The description of Wigner energy and its release from Windscale pile graphite for application to waste packaging and disposal
P.C. Minshall, A.J. Wickham
TCM-Manchester99, pp:47-64
The early operation of the helical once-through boilers at Heysham 1 and Hartlepool
Mathews, A.J. (Heysham 1 Power Station, Central Electricity Generating Board, Heysham (United Kingdom))
IWGGCR--15, pp:49-56
Heysham II/Torness AGR steam generator
Charcharos, A.N. (National Nuclear Corporation Ltd., Knutsford (United Kingdom)); Wood, M.B.; Glasgow, J.R. (NEI Power
Projects Ltd., Gateshead (United Kingdom))
IWGGCR--15, pp:57-76
Heat treatment of graphite and resulting tritium emissions
J. Wörner, W. Botzem, S.D. Preston
TCM-Manchester99, pp:65-76
Seismic design of the Heysham 2 advanced gas cooled reactor
nuclear power station.
Allen, C.F. (Central Electricity Generating Board, Barnwood
(UK). Generation Development and Construction Div.)
IWGGCR--22, pp:66-77
Considerations on the design of a helium circulator for a high temperature modular reactor system
Dumm, K. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.)); Donaldson, J. (James Howden and Co. Ltd, Renfrew (UK))
IWGGCR--17, pp:69-76
Pyrolysis and its potential use in nuclear graphite disposal
J.B. Mason, D. Bradbury
TCM-Manchester99, pp:77-84
A method for assessing the effects of graphite property variability on core structural integrity criteria
Judge, R.C.B. (AEA Reactor Services, Risley (United Kingdom). Gas Cooled Reactor
Assessments Dept.)
IAEA-TECDOC--690, pp:78-84
Background iodine in a commercial advanced gas-cooled
reactor
Garland, J.A.; Wiffen, R.D. (AERE Harwell,
Oxon (United Kingdom)); Webster, D. (Hinkley
Point Power Station, Somerset (United
Kingdom))
IWGGCR--13, pp:81-91
Modelling of plate-out under gas-cooled reactor (GCR) accident conditions
Taig, A.R. (UKAEA Risley Nuclear Power Development Establishment, Culcheth. Safety and Reliability Directorate)
IWGGCR--2, pp:87-93
The application of fracture mechanics to the notch sensitivity of graphite
Tucker, M.O. (Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.)
IWGHTR--3, pp:88-96
Experience of iodine, caesium and noble gas release from AGR
failures
Chapman, C.J.; Harris, A.M.; Phillips, M.E.
(Central Electricity Generating Board, Berkeley
Nuclear Laboratories (United Kingdom))
IWGGCR--13, pp:92-113
Performance Review: PBMR Closed Cycle Gas Trubine Power Plant
K.N.Pradeep. Kumar, Eskom PBMR, Centurion, Pretoria, South Africa
A. Tourlidakis and P. Pilidis, Cranfield University, Bedfordshire, UK
IAEA-TECDOC--1238, pp:102-113
The roles of water addition and gas composition in AGR accident management
Dawson, J.T. (Nuclear Electric plc, Berkeley (United Kingdom)); Smith, P.N. (AEA
Technology, Winfrith (United Kingdom))
IAEA-TECDOC--784, pp:110-115
The experimental qualification of a mathematical model used to assess the AGR core seismic response
Shaw, D.C. (National Nuclear Corp. Ltd., Risley (UK))
IWGGCR--11, pp:113-119
Bubble development and fission gas release during rapid heating
of 18 GWd/TeU UO2
Small, G.J. (Materials Development Division,
AERE Harwell (United Kingdom))
IWGGCR--13, pp:114-138
Post-service examination of a 10 MW helium-helium heat exchanger and comparison with long
term behaviour in laboratory tests
Cook, R.H.; Graham, L.W. (R.M. Detection Ltd, Poole, Dorset (UK). High
Temperature Materials Programme (HTMP)); Exner, R. (Balcke-Duerr AG,
Ratingen (Germany, F.R.))
IWGGCR--18, pp:124-130
Advanced gas cooled reactors - Designing for safety
Keen, Barry A. (Engineering Development Unit, NNC Limited, Booths Hall, Knutsford, Cheshire (United Kingdom))
IAEA-TC--389.26, pp:125-137
Coolant chemistry of the advanced carbon dioxide cooled reactor
Faircloth, R.L.; Norwood, K.S.; Prior, H.A. (UKAEA Atomic Energy Research Establishment, Harwell)
IWGGCR--2, pp:125-131
Advanced gas-cooled reactor design approach to safety
Ingham, E.L. (AGR Systems Reliability, National Nuclear Corp., Ltd., Knutsford (UK))
IAEA-TECDOC--358, pp:133-154
Nuclear graphite ageing and turnaround
B.J.Marsden(AEA Technology plc, UK),G.N.Hall,J Smart(University of Manchester, UK)
IAEA-TECDOC--1210, pp:133-153
Development of graphite for fuel element sleeves in advanced gas cooled reactors
Burridge, D.P.; Naylor, J.E. (British Nuclear Fuels plc, Salwick (United Kingdom). Fuel
Engineering Dept.)
IAEA-TECDOC--690, pp:134-139
Release of fission products during and after oxidation of
trace-irradiated uranium dioxide at 300-900 deg. C
Wood, P.; Bannister, G.H. (Central Electricity
Generating Board, Berkeley Nuclear Laboratories
(United Kingdom))
IWGGCR--13, pp:139-154
Heysham II/Torness power stations: Seismic qualification of
core structures and boilers
Shepherd, D.J. (National Nuclear Corp. Ltd., Knutsford (UK))
IWGGCR--22, pp:140-148
Derivation of a radionuclide inventory for irradiated graphite-chlorine-36 inventory determination
F.J. Brown, J.D. Palmer, P. Wood
TCM-Manchester99, pp:143-152
Steam generator materials constraints in UK design gas-cooled reactors
James, D.W. (Operational Engineering Division (Midlands Area), Central Electricity Generating Board, Bristol (United Kingdom))
IWGGCR--15, pp:149-155
Single phase and two phase erosion corrosion in broilers of gas-cooled reactors
Harrison, G.S.; Fountain, M.J. (Operational Engineering Division (Northern Area), Central Electricity Generating Board, Manchester (United Kingdom))
IWGGCR--15, pp:156-163
Plugging of feed inlet tube upstands with Ni/Ti shape memory alloy plugs - Heysham 1 power station
Mathews, A.J. (Heysham 1 Power Station, Central Electricity Generating Board, Heysham (United Kingdom))
IWGGCR--15, pp:163-168
VEC - A transient whole circuit model for AGRs
Facer, R.I. (AGR Systems, National Nuclear Corp., Ltd., Knutsford (UK))
IAEA-TECDOC--358, pp:165-181
Nuclear Graphite for High Temperature Reactors
B.J. Marsden, AEA Technology
Risley, Warrington
Cheshire, WA3 6AT, UK
IAEA-TECDOC--1238, pp:174-189
Achieving optimum graphite performance in AGR core and fuel
Norfolk, D.J.; Johnston, G.O.; Tucker, M.O. (Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.)
IWGGCR--11, pp:176-181
Boiler referruling on the Hartlepool and Heysham 1 advanced gas-cooled reactors
Newell, J.E. (Generation Development and Construction Division, Central Electricity Generating Board, Barnwood (United Kingdom))
IWGGCR--15, pp:188-194
AGR fuel pin pellet-clad interaction failure limits and activity release fractions
Hughes, H. (UKAEA, Springfields (United Kingdom));
Hargreaves, R. (UKAEA, Windscale (United Kingdom))
IWGGCR--8, pp:189-200
Safety design features for current UK advanced gas-cooled reactors
Yellowlees, J.M.; Cobb, E.C. (Nuclear Power Co. (Risley) Ltd. (UK))
IWGGCR--1, pp:191-198
Management of UKAEA graphite liabilities
M. Wise
TCM-Manchester99, pp:191-204
A review of irradiation creep in reactor graphite
Kelly, B.T. (AEA Technology, Salwick (United Kingdom))
IAEA-TECDOC--690, pp:200-204
Design and development of steam generators for the AGR power stations at Heysham II/Torness
Charcharos, A.N.; Jones, A.G. (National Nuclear Corp. Ltd.,
Cheshire (United Kingdom))
IWGGCR--9, pp:204-217
Radioactive graphite management at UK Magnox nuclear power stations
G. Holt
TCM-Manchester99, pp:205-213
Monitoring and performance analysis of AGR boilers during commissioning and power raising
El-Nagdy, M.; Harrison, R.M. (Babcock Power Ltd., Nuclear
Engineering Dept., London (United Kingdom))
IWGGCR--9, pp:218-234
The application of release models to the interpretation of rare
gas coolant activities
Wise, C. (Central Electricity Generating Board,
Berkeley Nuclear Laboratories (United
Kingdom))
IWGGCR--13, pp:221-235
Experience with the commissioning of helically coiled advanced gas cooled reactor boilers
Kettle, D.B. (CEGB, Generation Development and Construction
Div., Gloucester (United Kingdom))
IWGGCR--9, pp:235-244
Aseismic design of the Heysham II Nuclear Power Station
Day, J.W. (Central Electricity Generating Board, Barnwood, England)
IWGGCR--6, pp:237-274
Investigations of the gas-side heat transfer and flow characteristics of steam generators in AGR stations
Lis, J. (Central Electricity Research Laboratories, Leatherhead,
Surrey (United Kingdom))
IWGGCR--9, pp:245-265
Behaviour of particles in a commercial advanced gas-cooled
reactor
Garland, J.A.; Wells, A.C.; Hedgecock, J.B.
(AERE Harwell (United Kingdom))
IWGGCR--13, pp:250-261
Attachment of gaseous fission products to aerosols
Skyrme, G. (Central Electricity Generating Board,
Berkeley Nuclear Laboratories (United
Kingdom))
IWGGCR--13, pp:262-274
The variation of particle gas-borne concentration with time in a
gas cooled reactor
Reed, J.; Hall, D.; Reeks, M.W. (Central
Electricity Generating Board, Berkeley Nuclear
Laboratories (United Kingdom))
IWGGCR--13, pp:275-298
Modelling of caesium deposition in CAGR reactor circuits
Phillips, M.E. (Central Electricity Generating
Board, Berkeley Nuclear Laboratories (United
Kingdom))
IWGGCR--13, pp:299-317
Interim dry fuel storage for magnox reactors
Bradley, N. (National Nuclear Corporation, Risley,
Warrington (United Kingdom)); Ealing, C. (GEC Energy
Systems Ltd, Whetstone, Leicester (United Kingdom))
IWGGCR--8, pp:315-332
Modelling of iodine chemistry and plate-out in a CAGR
Clough, P.N.; Hood, E.M. (Safety and Reliability
Directorate, UKAEA, Culcheth (United
Kingdom))
IWGGCR--13, pp:318-328
Progress in the measurement of fuel temperature coefficients in CAGRs
Bridge, M.J.; George, T.A. (Central Electricity Generating Board, Berkeley
(UK). Berkeley Nuclear Labs.)
IAEA-TECDOC--358, pp:325-336
Safety assessment principles for reactor protection systems in the United Kingdom
Philp, W
IAEA-TC--389.26, pp:340-367
Decontamination of CAGR gas circulator components
Rogers, L.N.; Hooper, A.J. (Central Electricity
Generating Board, Berkeley Nuclear Laboratories
(United Kingdom))
IWGGCR--13, pp:385-401
UK regulatory aspects of prestressed concrete pressure vessels for gas-cooled reactor nuclear power stations
Watson, P.S. (HM Nuclear Installations Inspectorate (HMNII), Health and Safety Executive (United Kingdom))
IAEA-TC--389.26, pp:395-407
Manufacture of steam generator units and components for the AGR power stations at Heysham II and Torness
Glasgow, J.R.; Parkin, K. (N.E.I. Nuclear Systems Ltd.,
Gateshead, Tyne and Wear (United Kingdom))
IWGGCR--9, pp:562-570
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