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                             62 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A direct-cycle gas turbine power plant for near-term application: MGR-GT Lidsky, L.M.
 1991
 16 1-2 p. 177-186
10 p.
 artikel
2 Aerosol formation by graphite corrosion in case of water and air ingress to the core of a high-temperature reactor Kugeler, K.
 1991
 16 1-2 p. 491-499
9 p.
 artikel
3 Analytical method and result of off-site exposure during normal operation of High Temperature engineering Test Reactor (HTTR) Sawa, K.
 1991
 16 1-2 p. 459-470
12 p.
 artikel
4 An economic assessment of the U.S. MHTGR design Mears, L.Daniel
 1991
 16 1-2 p. 529-545
17 p.
 artikel
5 A safety yardstick for evaluating nuclear power reactors Northup, T.E.
 1991
 16 1-2 p. 395-405
11 p.
 artikel
6 Behavior of HTGR coated fuel particles in high-temperature tests Chernikov, A.S.
 1991
 16 1-2 p. 295-308
14 p.
 artikel
7 Concepts of nuclear heat supply for production of aluminum oxide and for refineries Schad, M.K.
 1991
 16 1-2 p. 565-571
7 p.
 artikel
8 Construction and operational experience with small and medium power reactors and expected improvements Dastidar, P.
 1991
 16 1-2 p. 7-13
7 p.
 artikel
9 Depressorization accident analysis for the FTTR by the TAC-NC Kunitomi, K.
 1991
 16 1-2 p. 471-480
10 p.
 artikel
10 Design and safety consideration in the High-Temperature engineering Test Reactor (HTTR) Saito, Shinzo
 1991
 16 1-2 p. 449-458
10 p.
 artikel
11 Design requirements for high-temperature metallic component materials in the U.S. modular hgtr Shenoy, A.S.
 1991
 16 1-2 p. 327-335
9 p.
 artikel
12 Design status of the HTR 500 power plant and the HTR module power plant Arndt, Erhard
 1991
 16 1-2 p. 201-219
19 p.
 artikel
13 Development prospects of high-temperature gas-cooled reactors and their role in nuclear power Ponomarev-Stepnoy, N.N.
 1991
 16 1-2 p. 119-127
9 p.
 artikel
14 Editorial Board 1991
 16 1-2 p. IFC-
1 p.
 artikel
15 Environmental aspects of MHTGR operation Neylan, A.J.
 1991
 16 1-2 p. 441-448
8 p.
 artikel
16 Evolution of HTGR coated particle fuel design Stansfield, O.M.
 1991
 16 1-2 p. 33-45
13 p.
 artikel
17 Foreword Dean, R.A.
 1991
 16 1-2 p. xi-
1 p.
 artikel
18 Fort St. Vrain operations and future Brey, H.L.
 1991
 16 1-2 p. 47-58
12 p.
 artikel
19 HTGR fuel and fuel elements Chernikov, A.S.
 1991
 16 1-2 p. 263-274
12 p.
 artikel
20 Integrated design of prestressed cast-iron pressure vessel and passive heat removal system for the reactor cell of a 200 mwth modular reactor Beine, B.
 1991
 16 1-2 p. 337-344
8 p.
 artikel
21 Introduction Schulten, Rudolf
 1991
 16 1-2 p. xiii-xv
nvt p.
 artikel
22 Investigation of radiation stability of HTGR coated fuel particles and spherical fuel elements Chernikov, A.S.
 1991
 16 1-2 p. 287-293
7 p.
 artikel
23 Key questions facing the NRC on the MHTGR Rogers, Kenneth C.
 1991
 16 1-2 p. 345-351
7 p.
 artikel
24 LEU-HTR critical experiment program for the proteus facility in Switzerland Brogli, R.
 1991
 16 1-2 p. 507-519
13 p.
 artikel
25 Main design aspects of an advanced nuclear plant for the Venezuelan Orinoco Oil Belt development Carvajal-Osorio, Hernan
 1991
 16 1-2 p. 555-564
10 p.
 artikel
26 Market prospects of Modular HTR in EEC countries Albisu, F.
 1991
 16 1-2 p. 547-553
7 p.
 artikel
27 MHTGR desalination for Southern California General atomics,
 1991
 16 1-2 p. 593-610
18 p.
 artikel
28 MHTGR fuel performance and supporting data base Goodin, D.T.
 1991
 16 1-2 p. 187-199
13 p.
 artikel
29 MHTGR radionuclide source terms for use in siting Inamati, S.B.
 1991
 16 1-2 p. 425-431
7 p.
 artikel
30 Modeling of fission product release from HTR fuel for risk analysis Bolin, J.M.
 1991
 16 1-2 p. 433-439
7 p.
 artikel
31 NRC review of U.S. advanced reactors King, Thomas L.
 1991
 16 1-2 p. 353-358
6 p.
 artikel
32 Outlook for MHTGR project development Hoffman, D.P.
 1991
 16 1-2 p. 107-110
4 p.
 artikel
33 Passive heat removal from the core of small and medium sized pebble bed reactors Kugeler, K.
 1991
 16 1-2 p. 521-528
8 p.
 artikel
34 Perspectives on the U.S. energy situation and the role of the modular HTGR Heins, Gordon L.
 1991
 16 1-2 p. 1-6
6 p.
 artikel
35 Physical and chemical analysis of interaction between oxide fuel and pyrocarbon coating of coated particles Lyutikov, R.A.
 1991
 16 1-2 p. 501-506
6 p.
 artikel
36 Preface Simnad, M.T.
 1991
 16 1-2 p. ix-x
nvt p.
 artikel
37 Present status of htgr development program in Japan Saito, Shinzo
 1991
 16 1-2 p. 129-136
8 p.
 artikel
38 Present status of research and development for HTR in China Dazhong, Wang
 1991
 16 1-2 p. 159-167
9 p.
 artikel
39 Prospects for HTGRs in developing countries Kupitz, J.
 1991
 16 1-2 p. 169-176
8 p.
 artikel
40 Prospects of SMSNR development in Switzerland and the influence of the evolution of district heating networks Foskolos, K.
 1991
 16 1-2 p. 573-581
9 p.
 artikel
41 Reactor tests and postirradiation examination of htgr fuel elements and coated particles Degaltsev, Yu.G.
 1991
 16 1-2 p. 275-285
11 p.
 artikel
42 Research and development programs for HTGRs in JAERI Nishiguchi, Isoharu
 1991
 16 1-2 p. 251-262
12 p.
 artikel
43 Safety aspects and safety research Kroger, W.
 1991
 16 1-2 p. 381-393
13 p.
 artikel
44 Status and prospects of the HTR-500 based on the THTR-300 operation experience and recent R&D work Theymann, Walter
 1991
 16 1-2 p. 111-117
7 p.
 artikel
45 Structural graphite for high-temperature gas-cooled reactors Virgiliev, Yu.S.
 1991
 16 1-2 p. 309-315
7 p.
 artikel
46 Structure-stable alloy for structural components of the high-temperature gas-cooled reactor with coolant temperature of 950 °C Dushin, Y.A.
 1991
 16 1-2 p. 317-326
10 p.
 artikel
47 Studies on the concepts of HTGR plants viable in Japan Part II: Discussion of the results An, Shigehiro
 1991
 16 1-2 p. 143-153
11 p.
 artikel
48 Studies on the concepts of HTGR plants viable in Japan Part I: Outline of the activities An, Shigehiro
 1991
 16 1-2 p. 137-141
5 p.
 artikel
49 Summary of Gas-Cooled reactor programs Goodjohn, A.J.
 1991
 16 1-2 p. 79-106
28 p.
 artikel
50 Survey on the activities in Switzerland in the field of HTGR-development Sarlos, G.
 1991
 16 1-2 p. 155-158
4 p.
 artikel
51 The approach to multimodule control of the MHTGR Woodworth, Calvin M.
 1991
 16 1-2 p. 243-249
7 p.
 artikel
52 The AVR power plant in its last year of operation Marnet, C.
 1991
 16 1-2 p. 71-77
7 p.
 artikel
53 The early history of high-temperature helium gas-cooled nuclear power reactors Simnad, Massoud T.
 1991
 16 1-2 p. 25-32
8 p.
 artikel
54 The influence of chemical state of the fission products on the filter properties of the graphite components Barthels, H.
 1991
 16 1-2 p. 481-489
9 p.
 artikel
55 The licensing experience of the Modular High-Temperature Gas-Cooled Reactor (MHTGR) Silady, F.A.
 1991
 16 1-2 p. 417-424
8 p.
 artikel
56 The materials program for the HTR in the frg: Integrity concept, status of the development of high temperature materials and design codes Nickel, H.
 1991
 16 1-2 p. 221-242
22 p.
 artikel
57 The nuclear battery: A very small reactor power supply for remote locations Kozier, K.S.
 1991
 16 1-2 p. 583-591
9 p.
 artikel
58 Theoretical and experimental investigations into the safety behavior of small HTRs under natural convection conditions Barthels, H.
 1991
 16 1-2 p. 371-380
10 p.
 artikel
59 The safety approach of the Modular High-Temperature Gas-Cooled Reactor (MHTGR) Silady, F.A.
 1991
 16 1-2 p. 407-416
10 p.
 artikel
60 The safety of modular high-temperature gas-cooled reactors Kasten, Paul R.
 1991
 16 1-2 p. 359-369
11 p.
 artikel
61 THTR commissioning and operating experience Baumer, R.
 1991
 16 1-2 p. 59-70
12 p.
 artikel
62 Trends in nuclear power reactor design and technology Kupitz, J.
 1991
 16 1-2 p. 15-23
9 p.
 artikel
                             62 gevonden resultaten
 
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