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, NASA/TM-2003-212S96 A Power Conversion Concept for the Jup iter Icy Moons Orbiter Lee S. Mason Glenn Research Center, Cleveland, Ohio September 2003 AlAJ\-2003-6007 https://ntrs.nasa.gov/search.jsp?R=20030105581 2020-08-07T00:16:16+00:00Z
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Page 1: A Power Conversion Concept for the Jupiter Icy Moons Orbiter€¦ · The Jupiter Icy Moon Orbiter (lIMO) nusslOn is an element of NASA's Project Prometheus Program. The HMO mi sion

,

NASA/TM-2003-212S96

A Power Conversion Concept for the Jupiter Icy Moons Orbiter

Lee S. Mason Glenn Research Center, Cleveland, Ohio

September 2003

AlAJ\-2003-6007

https://ntrs.nasa.gov/search.jsp?R=20030105581 2020-08-07T00:16:16+00:00Z

Page 2: A Power Conversion Concept for the Jupiter Icy Moons Orbiter€¦ · The Jupiter Icy Moon Orbiter (lIMO) nusslOn is an element of NASA's Project Prometheus Program. The HMO mi sion

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-- -- --

NASA/TM-2003-212S96

A Power Conversion Concept for the Jupiter Icy Moons Orbiter

Lee S. Mason Glenn Research Center, Cleveland, Ohio

Prepared for the First International Energy Conversion Engineering Conference

AIAA-2003-6007

cosponsored by the American Institute of Aeronautics and Astronautics (AIAA), the American Society of Mechanical Engineers (ASME), and the Institute of Electrical and Electronics Engineers (IEEE) Portsmouth, Virginia, August 17-21, 2003

National Aeronautics and Space Administration

Glenn Research Center

September 2003

Page 4: A Power Conversion Concept for the Jupiter Icy Moons Orbiter€¦ · The Jupiter Icy Moon Orbiter (lIMO) nusslOn is an element of NASA's Project Prometheus Program. The HMO mi sion

Acknowledgments

This work was performed for NASA Headquarters, Office of Space Science (Code S) under the Project Prometheus Program. The study was supported by personnel from the Jet Propulsion Laboratory, Glenn Research Center, Marshall Space Flight Center, Los Alamos National Laboratory, Sandia National Laboratory, and Oak Ridge National Laboratory. The PMAD concept was developed principally by the Electrical Systems Development

Branch at GRC, and in particular James Soltis, Arthur Birchenough, and Greg Kimnach. The ion propulsion concept was developed under the guidance of Steve Oleson with support from the GRC On-Board Propulsion Branch.

NASA Center for Aerospace Information 7121 Standard Drive Hanover, MD 21076

This report contains preliminary findings, subject to revision as

analysis proceeds.

Available from

National Technical Information Service 5285 Port Royal Road Springfield, VA 22100

Available electronically at h ttp: //glu·s.grc.nasa.gov

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A POWER CONVERSION CONCEPT FOR THE JUPITER ICY MOONS ORBITER

Lee S. Mason' Nati onal Aeronautics and Space Administration

Glenn Research Center Cleveland , Ohi o 44 135

Phone : 2 16- 977- 7106, Email : [email protected]

SUMMARY The Jupiter Icy Moon Orbi ter (JIMO) i a bold new mission under development by the Office of Space Science at NASA Headquarters. HMO is examining the potential of Nuclear Electri c Propulsion (NEP) technology to effic iently deliver c ientific pay loads to three Jov ian moons: Calli sto, Ganymede, and Europa. A critical element of the NEP vehicle is the reactor power system, consisting of the nuclear reactor, power conversion, heat rejection, and power management and distribution (PMAD). The emphasis of this paper is on the non-nuclear e lements of the reac tor power system.

The assumed power level fo r the NEP vehicle was 100 kWe, and a liquid-metal cooled reactor concept was assumed for the study, although both heat-pipe and gas-cooled reactors are poss ible alternati ves . The power conversion system consists of two, independent 100 kWe Brayton cyc le converters, prov iding LOO% converter redundancy. The converter design is based on state-of-the-art superalloy hot-end constructi on permitti ng turbine inlet temperatures of LI50K and cycle effic iencies in excess of 20%. The onl y moving part is a single-shaft, radi al turbo-compressor which is su pported by gas fo il bearings. The rotary alternator delivers high vo ltage, three-phase AC to the PMAD subsystem. The PMAD concept includes two completely redundant modules, each capable of deli vering 100 kWe to the spacecraft. Either PMAD modu le can service the full suite of thruster power process ing units, the pacecraft bus, and the power system paras itic loads. The waste heat rejection system inc ludes a pumped liquid-metal heat transport loop and water heat pipe radiator panels. The heat transport loop interfaces wi th the Brayton gas coolers, allowing either or both B rayton units to utili ze the full radi ator surface. The rad iator cons ists of two planar wings, each having a eries of stai r-cased deployable rectangular panels that are contained within the radiati on shield half-angle and provide two-s ided heat rejection. This paper di cusses some of the key trade-offs considered in arri ving at the baseline concept and provides a summary of the power system performance and mass .

* Research Engineer.

NASAffM-2003-212596

INTRODUCTION The Jupiter Icy Moon Orbiter (lIMO) nusslOn is an element of NASA 's Project Prometheus Program. The HMO mi sion is studying the potential of Nuclear Electric Propulsion (NEP) to deli ver scientif ic pay loads to the Jovian moons of Calli sto, Ganymede, and Europa. A NEP vehicle concept was developed, and trade studies were performed, to acco mplish JIMO. The power and propulsion module consisted of a 100 kWe reactor power system and a 6800 second specific impulse, ion propulsion sys tem. A general block di agram fo r the NEP vehicle concept is shown in Figure I .

The emphas is of thi s paper is on the non-nuclear elements of the reactor power system including the power conversion, heat rejecti on, and power management and di stribution (PMAD). A liquid-metal (li thium) cooled reactor concept was assumed fo r the study, although both hea t-pipe and gas-cooled reactors are possible alternati ves. The reactor include a truncated conical radi ation shield with a 10 degree half angle that attenuates induced radi ation levels to 25 krad and I x I 0" neutrons/cm2 at the pay load located 30 meters from the reactor. The reactor also includes a liquid-metal to ga heat exchanger that acco mmodates the integration of a Clo ed Brayton Cycle (CBC) power conversion system. The CBC conversion system was selected for the study based on its high effi ciency and

Figure I. NEP Vehicle Block Diagram

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suitability for the power level of interest. Stirling and thermoelectric convers ion technologies are also under considerati on. The heat rejection and PMAD concepts are oriented to CBC power conversion, although aspects of the designs wou ld be app licable to the other convers ion options.

TRADE STUDIES There were many conceptual des ign trade tudies that were conducted related to the power subsystems. System-level studies examined design and off-des ign operating modes, determined startup requirements, eva luated subsystem redundancy options, and quantified the mass and radi ator area of reactor power ystems from 20 to 200 kWe. The majority of thi s

activity centered around Brayton cycle analysi s and optimization, aimed at defIning cycle performance and subsystem interface requirements. In the Brayton converter subsystem, studies were performed to in vestiga te converter packaging options, and assess the induced torque effects on pacecraft dynamics due to rotating machinery. In the heat rejecti on subsystem (HRS), design trades were conducted on heat transport approaches , material and fluid options, and deployed radiator geometri es . In the PMAD subsystem, the overall electri ca l architecture was defined and trade studies examined distribution approaches, voltage levels, and cabling options.

REACTOR POWER SYSTEM The power system conceptual design process is iterative and in volves technology assessments, systems ana lysis, subsystem des ign, and vehicle integrati on studies. Technology assess ments provide a basis for selecting des ign parameters that are consistent with launch date. Some example of important design parameters are reactor outl et temperature, radiator panel area l mass (defined as mass per unit area or kg/m\ and alternator output voltage. These must be selected based on current Technology Readiness Levels (TRL) and reali stic projecti ons for technology advancement prior to launch. Systems analysis is conducted using the technology design parameters as inputs to analytical mode ls to arrive at an initial concept. Subsystem design prov ides further definition and serves to either substantiate or revise the design parameter assumptions. Fina ll y, vehic le integration studies examine the feas ibility of the design working within the spacecraft and mission framework . At each stage in the proce , new information usuall y causes the designers to reassess previous assumptions and adjust the overa ll concept. The sections below describe some of the system-level trades conducted during the study.

Cycle Analysis The power systems analysis was performed using a Glenn Research Center computer model called

NASAlTM- 2003-212596 2

NUCOPT, which accounts for the reactor, power conversion, heat rejecti on, and PMAD subsystems. ' The Brayton cycle state point di agram at the conclusion of the study proce S is shown in Figure 2. The Bray ton converter interfaces to the reactor through the heat source heat exchanger (HSHX), to the ma in radi ator through the gas cooler, and to the PMAD through the alternator. An inert gas mi xture (HeX e) is used as the Brayton working fluid . The onl y moving part is a sing le-shaft, radi al turbo-compressor which is supported by gas fo il bearings.

The power sy tem design inc luded two independent 100 kWe converters, based on a proposed mi ssion requirement to provide "fail-op" redundancy (defin ed as continued full power capab ility after component failure) in the power conversion subsy tem. The HSHX gas outlet temperature was set at 1150 K, allowing the use of nickel-based superall oys for the hot-end converter components. Figure 3 revea ls an aspect of the cyc le optimization process-showing reactor power, radiator area, and power conversion ma s sensiti vity to compressor in let temperature. The minimum mass des ign point occurs at a compressor inlet temperature of 4 11 K. The cycle analysis assumed component efficienc ies of 90% for the turbine, 80% fo r the compressor, and 92% for the alternator, and the recuperator effecti veness was set at 95 %. Bearing and

Figure 2. Brayton Cycle Diagram

700

600 / \ V

500

Reactor V -p"""" ~ -;;::...c Power ConverSIOfl

Mass

400

300

~ r-- r---. ~ f---Radlalor

-~ Nea

200

100

300 420

Compressor Inl81 Temperature (K)

Figure 3. Brayton Cycle Optimization

3300

3200

3100

3000

2900

2800

2700

2600

500

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alternator wi ndage losses were 2.5 and 3.4 kWt, respectively. Insul ation losses were estimated at 16.4 kWt. The design point Brayton cycle effic iency was 21.7% and the total end- to-end power system efficiency was 20.2%, resulting in a required reactor thermal power of 496 kWt.

Brayton heat rejection is accompli shed with a pumped NaK heat transport loop and a two-sided main radiator having a total surface area of 170 m' . The total waste heat load was 364 kWt, comprised of 350 kWt from the gas cooler and 14 kWt from an alternator bleed cooler. The alternator bleed coo ler provides waste heat diss ipation for bearing, windage, and alternator electromagnetic losses. The radiator area was determined based on an effective ink temperature of 200 K, fin effectiveness of 92%, and surface emissivity of 0.9.

The three-phase alternator produces 105 kWe at 45000 rpm, 600 Vrms line-to-line, and 1.5 kHz. The 95 % efficient PMAD system deli ver 100 kWe to the loads over a 30 meter transmi sion di stance. The PMAD includes power and control e lectronics, swi tchgear, and cab ling. A lso included is a full power shunt Parasitic Load Radiator (PLR) and a eparate PMAD thermal control radiator. The PLR has an effective temperature of 773 K and a urface area of 6 m' . The 6.4 m' PMAD radiator mai ntains an electroni cs cold-p late temperature at 333 K under a 3.2 kWt heat load.

Operating Modes Additi onal cycle analyses were performed to examine off-design operating modes for the Brayton converters. The sizing condition for the Brayton components was based on 100 kWe output, under a "converter-out" condi tion. Nominally, the two Brayton units would operate at 50% power. This is achieved by operating the units at a lower rotor speed and charge pressure. The lower rotor speed re ul ts in an alternator vo ltage decrease to 400 Vrms line-to- Iine. The major benefit of operating the units at part power is a reduction in the thermal stresses and bearing loads. However, the reactor thermal power increases to 554 kWt for the nominal operating mode, due to a modest decrease in cycle efficiency. An alternati ve approach is to operate a single unit and maintai n a cold-standby uni t.

Another operating mode that was considered was the minimum power coast mode. T his mode would be uti li zed during interp lanetary coasting (electric thrusters off) and upon arri val at the Jupiter moon cience orbits. The goal was to reduce reactor thermal power and operating temperature to minimize fission product bui ldup, thermal stress, and material creep. The HSHX gas outlet temperature was set at 950 K. The Brayton unit output power and reactor thermal power was

NASAffM-2003-2 12596 3

determined based on the need to maintain the NaK radia tor coo lant above its freezing temperature of 262 K without re-stowing radiator panel . The resulting cycle analysis, assuming off-design component efficienc ies, indicated that the system output power could be reduced to 20 kWe with a corresponding reactor thermal power of 118 kWt. Alternatively, the reactor power system could be operated at full power throughout the mission , and the PLR cou ld be utili zed to shunt any excess power not required by the loads .

Startup Power A representati ve startup approach was defined fo r the reactor power ystem, based on e lectrical power prov ided from the spacecraft bus so lar arrays and/or batteries. Startup is initi ated by energizing the PMAD controller and reactor instrumentation and control (I&C) subsystem. After the reactor is started to J 0% thermal power, the first radi ator wing is partia ll y deployed and oriented to the un for heating. The radiator wi ng is charged with coo lan t and the pump is started. Then the first Bray ton uni t is e lectrically motored (or rotated) to circul ate the HeXe working fluid fo r approximately 15 minutes before a self ­sustaining conditi on is achieved and po iti ve power is being produced. As the reactor power is increased to 50% and full deployment of the first radiator wi ng is completed, the Brayton unit ramp to nominal ope rating power. At that point, all of the spacecraft loads would be transferred from the spacecraft bus to the alternator bus. The total time to achieve bus switch-over was es timated at 4 hours, and startup energy for the power system was approx imate ly I kW-hr. Deployment of the second radiator wing and startup of the second Brayton unit would be accompli hed from the alternator bus.

A hot restart fo llowing a Brayton converter shu tdown was estimated to require less than 0.2 kW-hr. T he large thermal capac itance of the reac tor and converter unit should permit hot restarts for several hours following an unexpected shutdown, the limi ting factor being the freezing of the rad iator coolan t.

Redundancy Trades The mass of the Bray ton converters, heat rejection , and PMAD for the baseline config uration was estimated at 28 18 kg. This mass was based on two 100 kWe Bray ton unit , two 100 kWe PMAD modules, and a heat rejection subsystem capable of diss ipating the waste heat fro m a single Brayton unit at 100 kWe or two units at 50 kWe each. Alternatives to thi s config uration were evaluated relative to the full power capacity of the individual subsystems. Table I shows the mass differences fo r several alternative configurat ions. A single-string architecture would prov ide a 982 kg mass savings, whereas a configuration with full 100% redundancy in the converters, radiators, and PMAD

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would incur a 854 kg mass penalty . Configurations with greater than three Brayton units were not judged practical due to constraints in vehicle packaging and reactor interface piping.

T bl 1 M V a e ass ersus S b u system R d d e un ancy 100 kWe Net Singl e- JIMT - Ful l

Str ing Ref Red undancy

Bray tons I x IOO% I x IOO% 2x50% 2x 100% 3x 50% 2x 100%

Radiator, I x l00% 2x 50% 2xSOW; 2x50% 3x 50% 2x 100%

PMAO Ix I OO% 2x 100% 2x 50% 2x 100% 3x 50% 2x 100%

Mass (kg) 1836 21 78 2362 2818 3543 3672

Rei M ... (kg) - 982 -640 -456 0 .. 725 +854

Power Level Sca ling Figure 4 shows the mass and radiator area of the reactor power system for power levels from 20 to 200 kWe, based on the reference configurati on. The total reactor power system mass fo r the lOO kWe de ign concept wa 4 115 kg, or 4 1 kg/kWe. A 20 kWe system has a specific mass of about 100 kg/kWe, whil e a 200 kWe system has a specific rna of 32 kg/kWe due to the favorable scaling characteri stics of reactor-Brayton techno logy. Radi ator area is relati vely linear over thi s power range, since the basic cycle temperatures were not vari ed.

7000

6000

5000

~ 4000 o o ~ 3000

2000

1000

= PMAD 6402

r~HtROject _595;_ _PwrConv

5506 ~ c::::JHSHX 5051 V

r-~Sh"~ 4588- r--~ I _ Reado< 4115

./ f-~Atea -,...- I- ..,;;; r= ~ 3159 II r-2S35 ~ ~f;;;

[I!'l 170 I-2037 II I- ~~ r-- - r-- l- i-- -

~

138 • • • I .r--.t-.~ 1-.

20 40 60 SO 100 120 140 160 ISO 200

System Power (kWe)

Figure 4. System Mass Versus Power

BRA YTON SUBSYSTEM

,

420

360

300 ~

240 ! ~

180 ~

'" 120

60

The Brayton cycle analysis discussed previously provides the bas is for the Brayton subsystem des ign. The input design parameters are deri ved from previous converter development ac ti vities such as the 10 kWe Brayton Rotating Unit (BRU) , 2 kWe mini-BRU, and 25 kWe Space Station Freedom (SSF) Solar Dynamic Power Module. '-4 Despite over 30 years of NASA technology development, Bray ton power converters have never been operated in space. The BRU system, including the Brayton Heat Exchanger Unit (BHXU) recuperator/coo ler, represent the longest durati on ground test of a CBC conversion sys tem at

N ASAfTM-2003-2 12596 4

38000 hours. Both the BRU and mini-BRU units were fa bricated using ni cke l-based supera ll oys for the hot-end components which a ll ow turbine inlet temperatures of about ll50 K. Sca ling these desig ns to the lOO kWe-c1ass seems achievable within the anticipated development timeline . However, life validati on prior to launch will be a significant chall enge. The proceeding secti ons di scuss orne of the Brayton-spec ific trades conducted during the study.

Converter Pac kaging The Bray ton converter subsystem consists of the turboa lternator, recuperator, and gas coo ler. Several converter layout options were considered as shown in Figure 5. The" tacked" layout approach was preferred based on a mailer cross-secti onal di ameter. This a llowed the Bray ton units to be located closer to the reactor to minimi ze interface pi ping length without ad versely effecting shield half ang le and shi eld mass. The overall assembl y with the two 100 kWe units was 1.8 m in cross-secti on diameter and 2.6 m in length .

Stacked Layout

• 1.2

t

Ring Layout

1.8

2.6 1.4

1.9 1.4

2.2

Figure 5. Converter Layo ut Options

Torque Effects A first-order analysis was perfolmed using SIMULINK to understand the effects of induced torque from rotating machinery on NEP vehicle dynamics5 The analysis considered a representati ve lOO kWe NEP vehicle with dual Brayton units. Each Brayton unit includes a 53 cm long, 23 kg rotating a embl y with two radial joull1al bearings and one ax ial thrust bearing. Primary variables included bearing sti ffness (soft and hard), rotor orientati on (parallel and transverse to vehicle truss) , and operating scenarios (counter and co-rotating). Startup and shutdown events were also analyzed.

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Table 2. Torque Study Summary Two co·rotating Brayton units SIC Max Rotor axis parallel With vehicle truss Axis To rque 2000 Iblin bearing stiffness (N' m)

Steady State Net Bias Torque RlPIY 0

Steady State Cyclical Torque Roll 0.04 (Due to assumed rOlor Imbalance)

PlY 26

Single Unit Startup Roll 20

Transient Torque PlY 17 (Nominal case, 0 to 50 krpm in 10 sec)

Single Unit Shutdown Roll 196

Transient Torque PlY 17 (Worst case. 50 krpm to 0 in 1 sec)

Spacecraft moment of inertias very prellmmary and conservative Roll; 5000 K9-m', PitchiYaw;574.000 Kg-m'

Max

Acce l

(g 's)

0

6x10·7

3x10-"

3x1 Q-4

2x10-"

3x10-3

2x10-"

A sampling of the results is prov ided in Table 2. The net bias torq ue du ring steady- tate operati on is zero. Some low level cycl ical torque is poss ible due to an assumed (very s li ght) rotor imbalance. A nominal 10 second rotor spin-up resulted in a 20 N-m transient torque . A worst-ca e, I second rotor shutdown resulted in a 196 N-m transient torque. These temporary torques would have to be countered by the vehicle 's reacti on control sys tem. Parallel versus transverse mounting had no signif icant effect on vehicle dynamics. Counter ver us co-rotating also had no signif icant effect. However, counter-rotating pairs would minimize gyroscopic precession effects on vehicle maneuvers.

Turbi ne Inlet Temperature The B rayton turbine inlet temperature (or HSHX gas outlet temperature) is a key parameter that influences performance. Higher temperatures allow increases in cycle efficiency or decreases in radi ator area, or a combination of both. However, the higher operating temperatures tend to increase mi sion risk since more advanced materials are required to handle the higher thermal stress. The baseline turbine inlet temperature was 1150 K. Temperatures above about 1200 K would requ ire refractory a ll oys fo r the hot-end components. Figure 6 shows power conver ion system ma sand rad iator area a a functi on of turbine inlet temperature. A turb ine inlet temperature of 1450 K would provide a 20% reduction in mass and a 55 % reduction in radi ator area relati ve to the 1150 K reference.

HEAT REJECTION SUBSYSTEM The HRS dominates the NEP vehicle layout, due to the large s ize of the radia tor urface. However, a precedent ex ists for large space radi ators with the International Space Stati on (ISS) Photovoltaic Radiator (PVR).6 The PVR is a pumped ammonia heat rejection system with deployable rad iator panel . A radi ator assembl y includes seven 2-sided panels in series, each measuring 1.82 by 3.35 meters, for a total surface area of approx imate ly 85 m2. The aluminum honeycomb rad iator panels are deployed using a scissor mechanism,

NASAfTM-2003-212596 5

4000

3400

3200

3000

2800

2600

2400

2200

2000

900

l'\ '\.

'\.

"" '\. .- "" "'-

Powe< "- '-...... Radiator Area Conversion

Mass ........ r--:::: , ~

--.. t--

1000 1100 1200 1300 1400

Turbine Inlel Temperature

Figure 6. Mass and Area Versus Turb ine Inlet Temperature

300

270

'40

210

180

150

120

90

60

30

1500

and the to tal heat rejecti on (pane l , fl uid loop, deployment mechanism) area l mass is 8.8 kg/m2 (based on total surface area). The individual radiator pane ls are approximately 1.8 cm thick with an areal mass of about 2.75 kg/m' (based on total surface area).

During the SP-J 00 Space Reactor Program,' advanced radiator studie were performed by four different contractor teams. The studie addressed radi ator designs for operating temperatures of 600 and 875 K. One contractor completed a successful fabricati on and test of a high temperature radi ator element utilizing a potassium heat pipe and carbon-carbon f in structure.8

The condensing section was approximately 91 cm long and 7.5 cm wide with a 2.5 cm diameter Nb- I Zr heat pipe. The integrated heat pipe and fin assembly had an area l mass of 2. 1 kg/m2 (based on total surface area).

The HRS for the NEP concept study included heat transport , radi ator panels, and deployment mechani sm. Both the ISS radi ator and the SP-100 advanced radi ator studies were leveraged in arri ving at the design concept. Some of the HRS design trades are discussed below.

Heat Transport Approach A significant challenge for the heat rejection subsystem was to develop a heat transport approach to accommodate the dual-redundant Brayton power converter architecture. In order to maintain "fa il-op" redundancy in the conversion sys tem and avoid the need to carry twice the required radi ator area, a cross­strapped pumped heat transport loop was dev ised as shown in Figure 7 . The two Brayton gas coo lers serve as the thermal interface to the coolant loops. Each coo lant loop has dual redundant electromagneti c pumps. Each gas cooler includes two independent liquid passage , or cores , and one gas passage. During nominal operation, when both Brayton units are operating at 50% power, the liquid coolant fl ows through one of the liquid passages where the full waste heat load is transferred to the coolant. The coolant is

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P~.A 111 .. 11

r;;;-J ~

Cold

_ ........................ _ ..... _ ... _ .... _- .. - 1

· J~·]-II-I ······· II Figure 7. Radi ator Heat Transport Loop

then pumped through mani fo lds along a seri es of interconnected radiator panels, forming a radi ator wing assembly. The waste heat is transferred through heat pipes to the two- ided rad iator surface where it is rejected to space. Each radi ator wing assembly is sized to reject one-half of the total waste heat load .

In the event of a converter outage, the two pumped coo lant loops continue to operate as be fore: coolant fl ow rates and operating temperatures are maintained a t near-nominal conditi on . However, a series of cross­strapping va lves are actuated that all ow both coo lant loops to service the rema ining gas coo ler. The gas cooler heat load is increased by approx imately a fac tor of two as the operating converter 's power output is doubled to maintain full sys tem power. Both coolant loops continue to tran fer the heat to their respecti ve radi ator assemblies, which continue to diss ipate one­half of the total waste heat load.

Fluids and Materi als The reference HRS design u es NaK coo lant and water heat pipes. NaK provides a high spec ific heat coo lant over a wide temperature band suitable to the Brayton cycle conditi ons. Alternati ve coo lant options include hydrocarbons, flu orocarbons, organic , and water. The coo lan t loop containment material is stainless steel. The water heat pipes interface to the NaK coo lant through evaporator sections that are contained in the fluid loop. Heat pipes prov ide an efficient means of spreading the heat across the radi ator surface with minimal temperature drop. The heat pipes also provide greater fa ult to lerance than a system with pumped loop radi ator panels, s ince the fa ilure of an indi vidual heat pipe would have minimal system perfo rmance impacts. The use of high-pressure water as the heat pipe fluid provides good heat transfer at suitable temperatures with relatively low risk. The heat pipe fluid containment materi al is stainless or nickel-based.

NASArrM-2003-212596 6

The radi ator panels are constructed of a compos ite materi al such as carbon-carbon. Composite materi a ls provide low mass , hi gh conducti vity and reasonable stiffness . The a sumed areal mass of the heat pipe radi ator panels was 2.75 kg/m' (based on total surface area). T he to tal HRS area l mass including radi ator panels, pumped coo lant loop, and deployment system was 5 kg/m' (based on total surface area) . The mass of the pumped coo lant loop was calculated based on estimates fo r piping lengths, pump capacity, accumulator size, and fluid vo lume. The mass of the deployment system was calculated based on 30% of the radi ator panel ma s.

Radi ator Geometry and Deployment The main power conver ion radiators have a total surface area of 170 m' . Several options were considered in packaging the radiators on the NEP vehicle as shown in Figure 8. An important constraint is the reactor radi ation shi eld cone angle. Components that are out ide the shie lded cone are subjected to considerabl y hi gher induced radi ation levels. Since the radi ators are ex pected to have materi a ls and fluid s that might degrade from radiati on, a decision was made to maintain the full radi ator surface within the shie ld cone ang le. Maintaining the radi ator pane ls within the cone angle also reduces the potenti al fo r reactor radi ati on scattering at the pay load end of the vehicle.

The layouts in F igure 8 assume a 10° shield half angle and a 9 meter tota l ax ial length for the "up-front" equipment: reactor, shie ld, Brayton units, coo lant pumps and accumulators, and truss cani ster. The deployable truss has a square cross-sec ti on with a 0.7 meter side. The upper layou t was selec ted for the re ference concept. This configurati on uses a "stair­case" geo metry con isting of ten 1.5 meter panels per wing with a 10 cm gap between panels. The fir t panel has a depl oyed height of 1.5 meters, while the las t panel has a deployed height of about 4. 1 meters. The advantage of this geometry is the relati vely short overall length of the radiator panels (16 meters) which helps to reduce the mass of the radi ator piping, truss, and power cabling.

Rectangular Radiator :t= ...... , .... , .~~----~-------

'-- 21 ,- '-J ,

Figure 8. Radiator Geometry Options

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The lower layout uti li zes ten identi cal 1.5 by 2.8 meter panels per wi ng. This geometry offers greater simplic ity in panel fabrication and radiator deployment, but results in a significantly greater overall radiator length (29 meters).

Deployment of the panel is accompli shed with a scissor mechanism, similar to the ISS radiators, that is attached to the panels along the truss edge. Each radiator wing is assumed to have its own deployment mechanism, allowing the wi ngs to be deployed separately and independently fro m the truss. The separate radiator dep loyment permits greater flexibility for power system startup , as de cribed previously. It also removes the complexity of coi ncident truss deployment and reactor startup .

Figure 9 shows the effect of shield half ang le on rad iator length and relative shield mass for a range of radiator areas from 100 to 250 m2

• The curves ass ume a 9 meter "up-front" equipment length and the "sta ir­case" radiator geometry with 10 panels per wing. An increase in the shield half angle fro m 10 to 15° would reduce the overall radiator length by about 25 %. However, the relative sh ield mass would increase by about 50%.

40

35

I 30

:5 25 '" c: ..

20 ..J

.'l .. 15 :;; .. a: 10

o o

.- ~"" /-I-

""~ V "' / ~adJalO! Area-r--... 250m2 _

V~ -- 200m2 150 m2 _ - 100m2

200%

175%

150% '" '"

125% ! Q;

100% ~ .. 75% ~

Q; 50% cr

25%

5 10 15

0%

20

Shield Half Angle (deg)

Figure 9. Shield Half Angle Sensitivities

POWER MANAGEMENT AND DISTRffiUTION The PMAD subsystem is an often overlooked, but highly critical element of the reactor power system. Th is is particularly true for NEP systems that include high voltage electric thruster loads. The PMAD subsystem accepts the electrical output of the converters, modifie it as required by the bus, and distributes the power to the loads. In add ition, PMAD provides control and health monitoring for the power conversion subsystem.

Simi larly to the HRS , the International Space Station provides a u eful reference for the PMAD concept. The ISS represents the largest power system ever developed

N ASAffM-2003-212596 7

for space, with power level approaching 100 kWe at assembly complete. The ISS u e a 120 Vdc primary bus architecture with modul ar channels. The ISS PMAD system includes several components which prov ide a notional starting point for NEP designs, including remote power controllers, switchgear, and shunts. Additional PMAD technology efforts are pursuing higher vo ltage space-rated electronic components including relays , fuses, and switchgear for 270 Vdc.

A signifi cant challenge for the PMAD subsystem for the JIMO miss ion is the reactor-induced radiation env ironment, coupled with the severe natural radiation environment at Jupi ter. Total cumulated gamma dose at the electronics dose plane for the JIMO mission is estimated at approx imately 4.3 Mrad, wh ile total neutron dose is estimated at 6x 10 12 neutrons/cm2 (based on 100 mil aluminum shielding of the electronics). The contribution of the reactor to the total dose levels anticipated at the electronics is 25 krad and Ix lO I1

neutrons/cm2• This radi ation environment is well

beyond the present state-of- the-art in radiation tolerant high power PMAD components.

The PMAD subsystem concept was developed from a bottoms-up approach. The study included analysis of power electronics, swi tchgear, electrica l control, thermal control, and power cabling. The proceeding secti ons describe some of the PMAD-specific trades conducted during the study.

PMAD Architecture Before any comparati ve analysis could be performed on the PMAD subsystem, an e lectrica l architecture was required. Figure 10 shows the bas ic block diagram. Each of the two Brayton alternators has its own dedicated PMAD module, sized for 100 kWe. The alternator power is delivered to a 400 Vac, I kHz PMAD bus within the PMAD module. A buck transformer is provided at the input of the PMAD bus to reduce alternator voltage fro m 600 to 400 Vac, for the off-nominal case when a single alternator is providing the full 100 kWe system power. Additional work is needed to assess the PMAD performance for the minimum power coast mode condition, with two Brayton units at 10 kWe each.

From the PMAD bus, power is di stributed to switchgear for the electric thruster PPUs, the spacecraft bus, the PLR controller, and the power system auxiliary loads. The PMAD module also includes a start inverter for motoring the alternator during startup and a computer processor for overall PMAD control. A 333 K cold­plate provides a thermal control interface fo r the PMAD radiator.

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50 ~ ~oo Vac....uttz Nom 100 kW, 600 Vac, 15kHZ Max'

Pumps, Heatef'$, DnYes MotQfs . etc

®..kW.4CKl'llac....lJ!.tktofom...-100 kW, 6OOVac, 1.5 kHz Max'

• Buck traruformer reqUired for vOltage reduction dunng 100 kW alternator operation

..

't 'y I'i

. t.

50kW Max

PPU5 • SIC 20kW Bus Max

• • 50kW Max

PPU10 • Figure 10. PMAD Architecture

The E lectric Propulsion (EP) system includes ten PPUs and two ion thrusters per PPU. The PPU power distribution approach prov ides considerable redundancy and fault to lerance. The EP design concept includes a complete second set of thrusters to accommodate wear­out of the first set, and two redundant thrusters per set. A maximum of eight thrusters can be operated at any one time. A single PMAD module prov ides power switching to all ten PPUs at 400 Vac and 12.5 kWe per channel. During full power EP operation (i.e. 100 kWe) with both Brayton units operating at 50 kWe, each PMAD modul e powers only four of the ten PPU channels. If a si ngle Brayton unit is operating at 100 kWe, e ight of the ten PPU channels a re powered . The PPU converts the 400 Vac to 4000 Vdc via a transformer/rectifier/filter for the mai n beam power supply load. Lower power ancillary thruster loads (cathodes, heaters, etc .) are supplied via a 120 Vdc AC-DC converter in the PPU.

The PMAD subsystem delivers 120 Vdc , and up to 20 kWe to the spacecraft bus. Each PMAD module can provide up to to kWe in two 5 kWe channe l . The spacecraft bus de li vers secondary power, at lower voltages if necessary, to a ll the vehicle subsystems (e.g. communications, avionics, etc.) and to the science instrument payload. The 400 Vac PMAD bus power i converted to 120 V dc via an AC-DC converter. The PMAD switchgear interface with the spacecraft bus also serves as a power feed to the start in verte r for alternator motor startup .

The PLR contro ller provides pulse-width modulated (PWM) switching of the PLR res istor e lements to maintain constant alternator speed and load regardl ess

NASAlTM-2003-212596 8

of ex ternal power demands . This approach has been successfull y implemented on previous Brayton sy tems.

9 Each PMAD module includes a dedicated

500 Vdc PLR load bank sized to dis ipate up to 100 kWe at 773 K.

The power ystem auxi liary load bus provides e lectrical power for coolant pump, heaters, dri ve motors and instrumentat ion using a 400 Vac di stributi on system. The switchgear and cabling was ized for up to fourteen 2 kW loads, assumed to be located in the general vic inity of the Brayton units.

Equipment Layout and Cabling Distance The cab ling di stances indicated in Figure 10 represent a reference power distribution layout for the study. The reference layout has the PMAD sub ystem located at the pay load end of the vehicle, with 30 meters of cabling provided between the Brayton alternators and PMAD. The PMAD modul es are within c lose prox imi ty (:::; 5 meters) of the electric thruster PPUs, spacecraft bus, and PLR. The auxiliary load bus is co-located with the Brayton units at the reactor end of the vehicle. The location of the PMAD modules at the payload end of the vehicle a ll ows the electronic equipment to share shie lding with other e lectrical systems. This helps to minimjze the spot shi e lding req uired for vehic le electronics.

The power cab ling assumed for the study was tin­coated , copper conductor with Tefzel insul ati on, similar to what is used on the ISS , rated for 600 Volts and 150 °C. Table 3 provides a summary of the cable sizes. All of the cables were de-rated for current carry ing capac ity per MIL-STD-97SL, for operating

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1 -

temperature, and for bundling. The total power cabling mass for the five cable as emblies (a lternator-to­PMAD, PMAD-to-PPU, PMAD-to-bus, PMAD-to­PLR, and PMAD-to-aux) associated with one PMAD module was 77 kg. Prior to arri ving at the f inal power distribution layout, several alternati ve were considered includ ing locating the PMAD near the Bray ton al ternators. The cabling mass penalty was relati vely small at about 10%, but the radi ati on shie lding mass penalty was projected to be signifi cant.

Tab le 3. PMA D C bl S' . a e IZlng P(kWl Vo lls Ncond Amps AWG L (m)

Alt-PMAD 100 600 Vac 6 53 4 30 PMAD-PPU 125 400 Vac 30 20 10 5 PMAD-Bus 10 120 Vdc 4 42 6 5 PMAD-PLR 125 500 Vdc 20 25 6 5 PMAD-Aux 28 400 Vac 42 3 20 30

Alternator Voltage The alternator-to-PMAD cable represents the heav iest of the cab le assemblies due to its long length and large wire size. The alternator power and operating voltage dic tates the conductor current rating. For a given power level, higher alternator voltage results in a lower current rating and mass fo r the power cabling. However, the higher alternator vo ltage creates other concerns relati ve to space-rated electronic parts avail ability (switchgear, etc .) and corona arci ng.

Figure 11 shows alternator-to-PMAD cable mass as a fu nction of alternator vo ltage assuming 100 kWe dis tribution and 30 meter transmission distance. The reference case at 600 Vac a lternator output is shown at the "knee" of the cable mass curve. A 100 Vac alternator voltage would result in a 260 kg cable mass penalty. If the al ternator vo ltage was doubled to 1200 Vac, the resulting cable savings would onl y be 24 kg, and additional concerns would be raised with re pect to corona and part availability.

400

300 Oi :.

! 00 kW Cable l 30 m Transmiss ion Distance -

ETFE De-Rated Cu Conductors II) r-II) ... 200 :;;

'" :0 ... u

100

0

, ~ 1--

o 1000 2000 3000 4000

Alternator Voltage

Figure II. Cable Mass Versus Alte rnator Voltage

MASS AND EQUIPMENT LIST Table 4 presents the power conversion mass and equipment li st. The total mass was 2818 kg,. or 28 kg/kWe. The mass fracti ons for the Brayton uni ts , HRS, and PMAD are approx imate ly 45 , 30, and 25%, respectively. The reactor and shi eld subsystem adds about 1300 kg for a total power system mass of 4 115 kg, or 41 kg/kWe. The table shows the approximate locati on of the equipment on the vehicle: forebody (reactor end), truss, or aftbody (pay load end). A short description of the equipment is provided in the right-hand co lumn .

CONCLUSION The Jupiter Icy Moons Orbiter miss ion is currently under study by the Office of Space Science under the Project Prometheus Program. JIMO i examining the use of NEP to carry scientific pay loads to three Jovian moons. A potenti al power ys tem concept includes dual 100 kWe Brayton converters, a deployable pumped loop heat rejection subsystem, and a 400 Vac PMAD bus. Many trades were performed in arri ving at this

Table 4 Power Conversion Mass List Power Conversion (kg) Location 2818 100 kINe system

Brayton Power Generation 1280 1.2x1.4x2.6 m total assemb~

Turboalternators Forebody 2 136 272 50 kINe nominal.1 00 kINe max per unit Recuperators Forebody 2 243 486 He)(e to HeXe, cross·flow, Inconel Gas Coolers Forebody 2 178 355 HeXe to NaK. counter-now. stainless steel

Gas Ducting Forebody 15% 167 15% of components, Inconel and stainless steel Heat Rejection System 854

Main RadiatorWings Truss 2 234 468 2-sided. 85 m2 per wing. C-C panelswfHPs. 2 75 kglm2

Radlalor Fluid Pumps Forebody 4 24 96 2-slring. redundanl EM pumps Radiator Plumbing Truss 2 75 150 NaK-78, stainless steel pIping, accumulator

Deployment Mech. & Structure Truss 30% 140 30% of panels. scissor mechanism (i.e. ISS) Power Management & Distribution 684

Controls. Electronics. Switchgear Anbody 2 193 3B6 2 channels In one 50x50x75 cm box

Parasitic Load Radiator Anbody 2 36 72 6 m2 total surface area. 500' C Alt to PMAD Cabling Truss 2 44 8B 2X 1 00 kIN. 600 Vac. 30 m (incl cnll. ground wires)

PMAD to PPU Cabling Anbody 2 7 14 2X 125 I<VV. 400 Vac. l Och. 5 m PMAD to Bus Ca bling Anbody 2 3 6 2X 1 0 kIN, t 20 Vdc. 5 m

PMAD to PLR Cabling Anbody 2 14 28 2X 125 kIN. 500 Vdc. 5 m PMAD to Aux Cabling Truss 2 9 lB 2X 28 kIN. 400 Vac. 30 m (pumps. heaters, motors)

PMAD Radiator Anbody 2 36 72 6 m2 10tal surface area. 60 'C

NASAfTM- 2003-2 12596 9

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candidate power system concept. System-level studies examined design and off-des ign operating mode , determined startup requirements, evaluated subsystem redundancy options, and quantifi ed the mass and radiator area of reactor power systems from 20 to 200 kWe. In the Brayton converter subsystem, tudies were performed to investigate converter packagi ng option , and assess the induced torque effects on pacecraft dynamics due to rotating machinery. In the

HRS, design trades were conducted on heal tran port approaches, material and fluid option , and deployed rad iator geometrie . In the PMAD subsystem, the overall electrical arch itecture was defined and trade studies examined di tribution approaches, voltage levels, and cab ling opti on.

REFERENCES I . Mason, L.S ., "A Comparison of Brayton and

Stirling Space Nuclear Power Systems fo r Power Levels from I Kilowatt to [0 Megawatts," NASAffM-2001-210593, January 200 1.

2. Davis, J .E., "De ign and Fabrication of the Brayton Rotating Unit," NASA CR- 1870, March 1972.

3. Dobbler, F.X., el aI. , "Analysis, Des ign, Fabrication and Testing of the Mini-Braylon Rotating Unit (Mini -BRU)," NASA CR-159441, April 1974.

NASAffM-2003-212596 10

4. Staff of the Solar Dynamic Power System Branch, "Solar Dynamic Power Sy tem Development for Space Station Freedom," NASA RP-1 3 10, Jul y 1993.

5. Yu , A. , Hewston, A., and Le, D.K., "Preliminary Torque Analysi of Closed Brayton Cycle Rotordynamics on a Conceptual Nuclear Electri c Propul sion Vehicle," NASA TM, in process.

6. Lockheed Martin Missiles and Fire Control Website, November 2002. http ://www. missi lesandfirecontrol.com! ou r _products/productdevelopmentl SPACEST A TION/producl-spacestation.htrnl

7. Truscello, V.c. and Rutger, L.L, "The SP-l00 Power System," American In titute of Phy ic Conference Proceed ings 246. 9th Symposium on Space Nuclear Power Systems. Albuquerque, NM, 1992.

8. Juhasz, AJ ., "Design Considerat ions for Lightweight Space Rad iators Based on Fabri cation and Test Experience With a Carbon-Carbon Composite Prototype Heat Pipe," NASAffP-98-2074271REVI, September 2002 .

9. Mason , L.S. , Shaltens R.K. , and Esp ino a, W.D. , "Experimental Data fo r Two Different Alternator Configurations in a Solar Brayton Power System," NASA TM-107509, Jul y 1997.

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REPORT DOCUMENTATION PAGE Form Approved

OMB No. 0704-0188

Public reporting burden tor this collection of information is estimated to average 1 hour per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information. Send comments regarding this burden estimate or any other aspect of th is collection of information, including suggestions for reducing th is burden, to Washington Headquarters Services, Directorate for Information Operations and Reports, 1215 Jefferson Davis Highway, Suite 1204, Arlington , VA 22202-4302, and to the Office of Management and Budget. Paperworl< Reduction Project (0704-0188). Washington, DC 20503.

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September 2003 Technical Memorandum 4. TITLE AND SUBTITLE 5. FUNDING NUMBERS

A Power Conversion Concept for the Jupiter Icy Moons Orbiter

6. AUTHOR(S) VVBS-22-973-90-O1

Lee S. Mason

7 . PERFORMING ORGANIZATION NAME(S) AND ADDRESS(ES) 8. PERFORMING ORGANIZATION REPORT NUMBER

National Aeronautics and Space Administration John H. Glenn Research Center at Lewis Field E- J4153 Cleveland, Ohio 44135 - 3191

9. SPONSORINGIMONITORING AGENCY NAME(S) AND ADDRESS(ES) 10. SPONSORINGIMONITORING AGENCY REPORT NUMBER

National Aeronautics and Space Administration NASA TM- 2003-2 12596 VVashington, DC 20546- 0001 AlAA-2003-6007

11 . SUPPLEMENTARY NOTES

Prepared for the First International Energy Conversion Engineering Conference cosponsored by the American Institute of Aeronautics and Astronautics (AlAA), the American Society of Mechanical Engineers (AS ME), and the Institute of Electrical and Electronics Engineers (IEEE), Portsmouth, Virginia, August 17-21,2003. Responsible person, Lee S. Mason, organization code 5490, 216- 977-7106.

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Unclassified - Unlimited Subject Category: 20 Distribution: onstandard

Avai lable electronically at ht!p://glrrs.grc.nasa.gov

This publication is available from the NASA Center for AeroS pace Information. 301 -621--0390. 13. ABSTRACT (Maximum 200 words)

The Jupiter Icy Moons Orbiter (lIMO) mission is currently under study by the Office of Space Science under the Project Prometheus Program. JIMO is examining the use of Nuclear Electric Propulsion (NEP) to carry scientific payloads to three Jovian moons. A potential power system concept includes dual 100 kVVe Brayton converters, a deployable pumped loop heat rejection subsystem, and a 400 Vac Power Management and Distribution (PMAD) bus. Many trades were performed in arriving at this candidate power system concept. System-level studies examined design and off-design operating modes, determined startup requirements, evaluated subsystem redundancy options, and quantified the mass and radiator area of reactor power systems from 20 to 200 kVVe. In the Brayton converter subsystem, studies were perfomled to investi gate converter packaging options, and assess the induced torque effects on spacecraft dynamics due to rotating machinery. In the heat rejection subsystem, design trades were conducted on heat transport approaches, material and fluid options, and deployed radiator geometries. In the PMAD subsystem, the overall electrical architecture was defi ned and trade studies examined distribution approaches, voltage levels, and cabling options.

14. SUBJECT TERMS 15. NUMBER OF PAGES

Nuclear electric power generation; Nuclear electric propulsion; Brayton cycle 16. 16

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17. SECURITY CLASSIFICATION 18. SECURITY CLASSIFICATION 19. SECURITY CLASSIFICATION 20. LIMITATION OF ABSTRACT OF REPORT OFTHIS PAGE OF ABSTRACT

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