Chemical Engineering 412

Transcription

1 Chemical Engineering 412 Introductory Nuclear Engineering Lecture 19 Nuclear Power Plants I Nuclear Power Plants: LWRs

2 Spiritual Thought 2 You have a cool, rockin day, brutha!

3 Critical Bare Reactor Summary / cos 3.64 / 3.63 cos J / J / 3.85 cos cos cos / 1.57 cos f R f R f R f R f R E R P R r r A R sphere VE P H z R A H z R D cylinder E R P R A R D cylinder VE P c z b y a x A c b a D plate ae P a x A a D plate Σ Σ + Σ Σ + + Σ π π π π π π π π π π π geometry Buckling (BB gg 2 ) Flux A φ av Ω = φ max

4 Operating Nuclear Reactors Source: IAEA PRIS database, Feb. 25, 2014; note: includes 40 reactors in Japan that have not operated in two years.

5 Under Construction Source: IAEA PRIS database, Feb. 25, 2014; note: includes 40 reactors in Japan that have not operated in two years.

6 Source: IAEA PRIS database, Feb. 10, 2014; includes 40 reactors in Japan that have not operated in two years. Global Nuclear Capacity Total = 372 GW e

7 Nuclear Power Production Nuclear Electricity Supplied [GW.h] Source: IAEA PRIS database, annual production as of 25 Feb. 2014

8 Power Produced Source: IAEA PRIS database, as of 25 Feb. 2014

9 Global Trend Source: IAEA PRIS database, 25 Feb. 2014

10 Share of Nuclear Power Source: IAEA PRIS database, Feb. 10, 201

11 Nuclear Power Plant Age Average age = 28 years Source: IAEA PRIS database, Feb. 25, 2014; includes 40 reactors in Japan that have not operated in two years.

12 Reactor Under Construction Source: IAEA PRIS database, Feb. 10, 2014

13 Permanently Shutdown Reactors Source: IAEA PRIS database, Feb. 10, 2014

14 Nuclear Incremental Additions Total capacity is sum of these data. Source: IAEA PRIS database

15 Power Dynamics Source: IAEA PRIS database, 2013

16 Net Operating Capacity Source: IAEA PRIS database, 2013

17 Global Capacity and Contribution Source: IAEA PRIS database, 2013

18 US Power Plants 100 plants in 31 states operated by 30 utilities with combined capacity and generation of 98.6 GW and 800 GWh, respectively, with average capacity factors slightly over 90%. 5 reactors under construction on 3 sites.

19 US Sites Under Construction Site Technology MWe gross Watts Bar 2, TN Westinghouse PWR Vogtle 3, GA Vogtle 4, GA Westinghouse AP1000 Westinghouse AP (1177 net) 1200 (1117 net) 1200 (1117 net) Proponent or utility Tennessee Valley Authority Southern Nuclear Operating Company Southern Nuclear Operating Company Construction start 2007 re-start (1983 original) March 2013 Nov 2013 Loan guarantee; start operation on line Dec 2015 has loan g'tee, late 2017 has loan g'tee, late 2017 V.C.Summer 2, SC Westinghouse AP (1117 net) South Carolina Electric & Gas March 2013 short list loan g'tee, end 2017 V. C. Summer 3, SC AP South Carolina Electric & Gas Nov 2013 Subtotal 'under construction': 5 units (6018 MWe gross, 5645 MWe net) short list loan guarantee; early 2019

20 Pressurized Water Reactor (PWR)

21 Pressurized Water Reactor (PWR) Most widely used reactor worldwide. Water never boils in the core (which is pressurized typically atm). Heat exchanged in a second lowerpressure loop to generate turbine steam. Minimizes equipment exposure to ionizing radiation and radioactive waste production.

22 Boiling Water Reactor (BWR)

23 Boiler Water Reactor (BWR) Water boils directly in the core. Steam passes directly to turbine. After turbine, steam recondenses and returns to reactor. Large variations in heat transfer coefficients on the fuel rods. Turbine exposed to radioactive products from fluid, complicating maintenance and decommissioning.

24 Heavy Water Reactor (PHWR)

25 Heavy Water Reactor Heavy water (deuterium- or tritium-based water) passes through pressurized fuel tubes surrounded by a nonpressurized heavy water bath. Operates on natural uranium Avoids pressurized reactor vessel (major expense). Steam generated in second loop. Basis of the CANDU (Canadian) reactor designs. Variant is the heavy-water-moderated, light-water-cooled reactor (HWLWR) that uses light water in the fuel tubes and no heat exchanger.

26 Gas-cooled Reactor (GCR)

27 Gas-cooled Reactor (GCR, HTGR) Gas (He or CO 2 ) used as coolant. Graphite typically used as moderator. Graphite (which remains solid) and gas need not be pressurized No expensive pressure vessel No Blowdown in accident Gas heats steam in secondary loop. In a gas-cooled reactor (GCR), gas passes through holes in graphite moderator. In a high-temperature gas-cooled reactor (HTGR), fuel channels and gas channels are drilled in graphite core.

28 Liquid-metal fast breeder reactor

29 Liquid Metal Fast Breeder Reactor (LMFBR) Fast-neutron-based reactor scheme. No moderator (no light elements). Na or K-Na molten metal used as coolant. No pressurization, very high heat transfer coefficients. Na becomes radioactive and Na and K react violently with water (moderately with air). Second Na heat exchanger isolates Na/K coolant in core from turbine steam. New fuel to consumed fuel ratio raises from in typical reactors to over 1 if designed as a breeder reactor. One in commercial operation (in Russia), though they are aggressively pursuing new designs.

30 Light-water-cooled graphite moderated reactor (LGR)

31 Light-water-cooled graphite moderated reactor (LGR) Soviet-designed reactor, called RBMK (reactory bolshoi moshchnosti kanalnye high-powered pressure-tube reactor). Fuel in fuel pressurized fuel channels in graphite block. Steam passes directly to turbine. Fuel can be exchanged without reactor shutdown. Capable of operation on natural uranium. All systems since Chernobyl use higher (2.4%) uranium enrichment.

32 Research Reactor Startup

33 Typical PWR Specs

34 Reactor Core

35 Fuel Assembly

36 Steam Generator (Heat Exchanger)

37 Overall Equipment Arrangement

38 Pressurizer

39 PWR Steam Cycle

40 BWR Specifications

41 BWR Core

42 BWR Fuel Assembly

43 Generations I-IV

44 Generation I Test reactors and small-scale systems

45 Generation II Most current commercial reactors Largely adopted from ship propulsion systems 60s-70s technologies Perhaps more complex than needed

46 Generation III/III+ Perturbations on Generation II reactors Safer Less complex More economical

47 The AP1000 (Gen III+) Design

48 Westinghouse SMR 48