Nuclear Production of Hydrogen, Fourth Information Exchange ...

More documents

Recommendations

Info

EXPERIMENTAL STUDY OF THE VAPOUR-LIQUID EQUILIBRIA OF HI-I 2-H 2O TERNARY MIXTURES Engels, H., K.F. Knoche (1986), “Vapor Pressures of the System HI/H 2 O/I 2 and H 2 ”, Int. J. Hydrogen Energy, 11, 703-707. Funk, J.E. (1976), “Thermochemical Production of Hydrogen via Multistage Water Splitting Processes”, Int. J. Hydrogen Energy, 1, 33-43. Hartmann, J.M., et al. (2009), “Speciation of the Gaseous Phase of the HI Section of the Iodine Sulphur Thermochemical Cycle by Modeling and Inversion of FTIR Spectra”, Int. J. Hydrogen Energy, 34, 162-168. Hodotsuka, M., et al. (2008), “Vapor-liquid Equilibria for the HI+H 2 O System and the HI+H 2 O+I 2 System”, J. Chem. Eng. Data, 53, 1683-1687. Larousse, B., et al. (2009), “Experimental Study of the Vapour-liquid Equilibria of HI-I 2 -H 2 O Ternary Mixtures. Part 2: Experimental Results at High Temperature and Pressure”, Int. J. Hydrogen Energy, forthcoming. Liberatore, R., et al. (2008), “Experimental Vapour-liquid Equilibrium Data of HI-H 2 O-I 2 Mixtures for Hydrogen Production by Sulphur-Iodine Thermochemical Cycle”, Int. J. Hydrogen Energy, 33, 4283-4290. Miyamoto, Y., et al. (2000), “R&D Program on Hydrogen Production System with High Temperature Cooled Reactor”, Proceedings of International Hydrogen Energy Forum 2000, Munich, Germany, Vol. 2, 271-278. Norman, J.H., et al. (1982), DOE Contract N° DE-ATO3-83SF11929, GA-A18257. O’Keefe, D., et al. (1982), “Preliminary Results from Bench Scale Testing of a Sulfur Iodine Thermochemical Water Splitting Cycle”, Int. J. Hydrogen Energy, 7, 381-392. Prosim software (n.d.), www.prosim.net. Roth, M., K.F. Knoche (1989), “Thermochemical Water Splitting Through Direct HI Decomposition from H 2 O-HI-I 2 Solutions”, Int. J. Hydrogen Energy, 14 (8), 545-549. Vitart, X., P. Carles, P. Anzieu (2008), “A General Survey of the Potential and the Main Issues Associated with the Sulfur-Iodine Thermochemical Cycle for Hydrogen Production Using Nuclear Heat”, Nuclear Energy, 50, 402-410. 198 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010
PREDICTING THE ENERGY EFFICIENCY OF A RECUPERATIVE BAYONET DECOMPOSITION REACTOR Predicting the energy efficiency of a recuperative bayonet decomposition reactor for sulphur-based thermochemical hydrogen production* Maximilian B. Gorensek, Tommy B. Edwards Computational Sciences Directorate, Savannah River National Laboratory Aiken, SC, USA Abstract High-temperature decomposition of sulphuric acid is a major step for sulphur-based thermochemical cycles such as hybrid sulphur and sulphur-iodine. It is generally also the most energy-intensive, so that the overall heat requirement for this step can determine whether a particular decomposition reactor or flow sheet design is practical. A recuperative bayonet sulphuric acid decomposition reactor has been designed by researchers at Sandia National Laboratories (SNL) that features all-silicon carbide (SiC) construction for the heated parts, can be made from readily available SiC shapes, makes the most use of heat recuperation, and has all of its fluid connections at sufficiently low temperatures that conventional seal materials can be used. Bench-scale experiments using electric resistance heaters as the energy source have verified that the design functions as intended. The purpose of this work was to apply a pinch analysis to the SNL concept, using a statistically designed set of computer model experiments to establish the limiting performance (heating target) of the reactor as a function of operating conditions. Mapping out the limiting performance helped ascertain the practical operating range, allowing the reactor to be integrated into conceptual flow sheets. Seven input variables were considered: temperature (48 to 150°C), pressure (10 to 90 bar), and acid concentration (30 to 90 wt.%) of the feed; process fluid temperatures at the inlet (600 to 740°C) and the outlet (750 to 900°C) of the catalyst bed; temperature approach to equilibrium of the decomposition reaction in the catalyst bed (-25 to 0°C); and minimum temperature difference for recuperative heat transfer (10 to 100°C). Of particular interest was the effect of temperature, which will be limited by the operating temperature of the nuclear reactor heat source. A space-filling Latin Hypercube Design was used to generate model control variable input sets that were spread throughout factor space. Statistical tools were used to develop models from the results of the simulation “experiments” and to suggest additional simulation points to explore regions of interest. Over 130 different sets of control variables were eventually simulated. Results indicate that practical operation (high temperature heat target < 400 kJ/mol SO 2 ) requires acid feed concentrations in excess of 65 wt.% H 2 SO 4 . The optimum (lowest achievable high temperature heat target of 321 kJ/mol SO 2 ) occurs at roughly 80 wt.% H 2 SO 4 at the highest pressure (90 bar) and highest peak process temperature (900°C). As the peak process temperature is decreased from 900°C, the heating target increases. Below peak process temperatures of about 700°C, heating targets well in excess of 400 kJ/mol SO 2 are predicted. This means that HTGR operating below 800°C reactor outlet temperature will not allow efficient bayonet operation. Feed and catalyst bed inlet temperatures had no effect on the heat target. Not surprisingly, a zero value of the decomposition reaction temperature approach to equilibrium and 10°C minimum temperature difference for recuperative heat transfer was found to be best. * The full paper being unavailable at the time of publication, only the abstract is included. NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 199
Page 1:
Nuclear Science 2010 Nuclear Produc
Page 4 and 5:
ORGANISATION FOR ECONOMIC CO-OPERAT
Page 7 and 8:
TABLE OF CONTENTS Table of contents
Page 9 and 10:
TABLE OF CONTENTS Y. Gong, E. Chalk
Page 11 and 12:
EXECUTIVE SUMMARY Executive summary
Page 13 and 14:
EXECUTIVE SUMMARY steam turbine, in
Page 15 and 16:
EXECUTIVE SUMMARY sulphur depositio
Page 17 and 18:
EXECUTIVE SUMMARY affords saving 35
Page 19 and 20:
EXECUTIVE SUMMARY safety assessment
Page 21:
EXECUTIVE SUMMARY The question was
Page 24 and 25:
CHANGING THE WORLD WITH HYDROGEN AN
Page 26 and 27:
Page 28 and 29:
Page 30 and 31:
Page 32 and 33:
Page 35 and 36:
NUCLEAR HYDROGEN PRODUCTION PROGRAM
Page 37 and 38:
NUCLEAR HYDROGEN PRODUCTION PROGRAM
Page 39 and 40:
FRENCH RESEARCH STRATEGY TO USE NUC
Page 41 and 42:
Page 43 and 44:
Page 45 and 46:
Page 47 and 48:
Page 49 and 50:
PRESENT STATUS OF HTGR AND HYDROGEN
Page 51 and 52:
Page 53 and 54:
Page 55 and 56:
Page 57 and 58:
Page 59 and 60:
Page 61 and 62:
STATUS OF THE KOREAN NUCLEAR HYDROG
Page 63 and 64:
Page 65 and 66:
Page 67 and 68:
Page 69 and 70:
THE CONCEPT OF NUCLEAR HYDROGEN PRO
Page 71 and 72:
Page 73 and 74:
Page 75 and 76:
Page 77:
Page 80 and 81:
CANADIAN NUCLEAR HYDROGEN R&D PROGR
Page 82 and 83:
Page 84 and 85:
Page 86 and 87:
Page 88 and 89:
Page 90 and 91:
APPLICATION OF NUCLEAR-PRODUCED HYD
Page 92 and 93:
Page 94 and 95:
Page 96 and 97:
Page 98 and 99:
Page 100 and 101:
Page 103 and 104:
STATUS OF THE INL HIGH-TEMPERATURE
Page 105 and 106:
Page 107 and 108:
Page 109 and 110:
Page 111 and 112:
Page 113 and 114:
Page 115 and 116:
Page 117 and 118:
Page 119:
Page 122 and 123:
HIGH-TEMPERATURE STEAM ELECTROLYSIS
Page 124 and 125:
Page 126 and 127:
Page 128 and 129:
Page 131:
MATERIALS DEVELOPMENT FOR SOEC Mate
Page 134 and 135:
A METALLIC SEAL FOR HIGH-TEMPERATUR
Page 136 and 137:
Page 138 and 139:
Page 140 and 141:
Page 142 and 143:
DEGRADATION MECHANISMS IN SOLID OXI
Page 144 and 145:
Page 146 and 147:
Page 149 and 150: CAUSES OF DEGRADATION IN A SOLID OX
Page 151 and 152: 70 μm CAUSES OF DEGRADATION IN A S
Page 157 and 158: NUCLEAR HYDROGEN USING HIGH TEMPERA
Page 167: SESSION III: THERMOCHEMICAL SULPHUR
Page 170 and 171: CEA ASSESSMENT OF THE SULPHUR-IODIN
Page 181: STATUS OF THE INERI SULPHUR-IODINE
Page 184 and 185: INFLUENCE OF HTR CORE INLET AND OUT
Page 194 and 195: EXPERIMENTAL STUDY OF THE VAPOUR-LI
Page 203: DEVELOPMENT OF HI DECOMPOSITION PRO
Page 206 and 207: SOUTH AFRICA’S NUCLEAR HYDROGEN P
Page 216 and 217: INTEGRATED LABORATORY SCALE DEMONST
Page 225: DEVELOPMENT STATUS OF THE HYBRID SU
Page 229 and 230: RECENT CANADIAN ADVANCES IN THE THE
Page 237 and 238: AN OVERVIEW OF R&D ACTIVITIES FOR T
Page 245 and 246: STUDY OF THE HYDROLYSIS REACTION OF
Page 251 and 252:
STUDY OF THE HYDROLYSIS REACTION OF
Page 253 and 254:
DEVELOPMENT OF CuCl-HCl ELECTROLYSI
Page 255 and 256:
Page 257 and 258:
Page 259:
Page 262 and 263:
EXERGY ANALYSIS OF THE Cu-Cl CYCLE
Page 264 and 265:
Page 266 and 267:
Page 268 and 269:
Page 271 and 272:
CaBr 2 HYDROLYSIS FOR HBr PRODUCTIO
Page 273 and 274:
Page 275 and 276:
Page 277 and 278:
Page 279 and 280:
Page 281:
SESSION V: ECONOMICS AND MARKET ANA
Page 284 and 285:
DEVELOPMENT OF THE HYDROGEN ECONOMI
Page 286 and 287:
Page 288 and 289:
Page 291 and 292:
NUCLEAR H 2 PRODUCTION - A UTILITY
Page 293 and 294:
Page 295 and 296:
Page 297 and 298:
Page 299 and 300:
Page 301 and 302:
ALKALINE AND HIGH-TEMPERATURE ELECT
Page 303 and 304:
Page 305 and 306:
Page 307 and 308:
Page 309 and 310:
THE PRODUCT OF HYDROGEN BY NUCLEAR
Page 311 and 312:
Page 313 and 314:
Page 315 and 316:
Page 317 and 318:
Page 319 and 320:
SUSTAINABLE ELECTRICITY SUPPLY IN T
Page 321 and 322:
Page 323 and 324:
Page 325 and 326:
Page 327:
Page 330 and 331:
PROHYTEC, THE FRENCH INDUSTRIAL PLA
Page 332 and 333:
Page 334 and 335:
Page 336 and 337:
NHI ECONOMIC ANALYSIS OF CANDIDATE
Page 338 and 339:
Page 340 and 341:
Page 342 and 343:
Page 344 and 345:
Page 346 and 347:
MARKET VIABILITY OF NUCLEAR HYDROGE
Page 348 and 349:
POSSIBILITY OF ACTIVE CARBON RECYCL
Page 350 and 351:
Page 352 and 353:
Page 354 and 355:
Page 357 and 358:
NUCLEAR SAFETY AND REGULATORY CONSI
Page 359 and 360:
Page 361 and 362:
Page 363:
Page 366 and 367:
TRANSIENT MODELLING OF S-I CYCLE TH
Page 368 and 369:
Page 370 and 371:
Page 372 and 373:
Page 374 and 375:
Page 376 and 377:
Page 378 and 379:
Page 380 and 381:
PROPOSED CHEMICAL PLANT INITIATED A
Page 382 and 383:
Page 384 and 385:
Page 386 and 387:
Page 388 and 389:
Page 390 and 391:
CONCEPTUAL DESIGN OF THE HTTR-IS NU
Page 392 and 393:
Page 394 and 395:
Page 396 and 397:
Page 399 and 400:
USE OF PSA FOR DESIGN OF EMERGENCY
Page 401 and 402:
Page 403 and 404:
Page 405 and 406:
Page 407 and 408:
Page 409 and 410:
HEAT PUMP CYCLE BY HYDROGEN-ABSORBI
Page 411 and 412:
Page 413 and 414:
Page 415 and 416:
Page 417:
Page 420 and 421:
HEAT EXCHANGER TEMPERATURE RESPONSE
Page 422 and 423:
Page 424 and 425:
Page 426 and 427:
Page 428 and 429:
Page 430 and 431:
Page 432 and 433:
Page 435 and 436:
ALTERNATE VHTR/HTE INTERFACE FOR MI
Page 437 and 438:
Page 439 and 440:
Page 441 and 442:
Page 443 and 444:
Page 445 and 446:
Page 447:
POSTER SESSION CONTRIBUTIONS Poster
Page 450 and 451:
ACTIVITIES OF NUCLEAR RESEARCH INST
Page 452 and 453:
ACTIVITIES OF NUCLEAR RESEARCH INST
Page 455 and 456:
A URANIUM THERMOCHEMICAL CYCLE FOR
Page 457 and 458:
A URANIUM THERMOCHEMICAL CYCLE FOR
Page 459:
MEETING ORGANISATION Annex 1: Meeti
Page 462 and 463:
LIST OF PARTICIPANTS REYTIER, Magal
Page 464 and 465:
LIST OF PARTICIPANTS BROWN, Nichola
Page 466:
LIST OF PARTICIPANTS SINK, Carl US
show all

Nuclear Production of Hydrogen, Fourth Information Exchange ...

Create successful ePaper yourself

Delete template?

Save as template?