The Space Nuclear Thermal Propulsion (SNTP) Program is an initiative within the US Air Force to acquire and validate advanced technologies that could be used to sustain superior capabilities in the area or space nuclear propulsion. The SNTP Program has a specific objective of demonstrating the feasibility of the particle bed reactor (PBR) concept. The term PIPET refers to a project within the SNTP Program responsible for the design, development, construction, and operation of a test reactor facility, including all support systems, that is intended to resolve program technology issues and test goals. A nuclear test facility has been designed that meets SNTP Facility requirements. The design approach taken to meet SNTP requirements has resulted in a nuclear test facility that should encompass a wide range of nuclear thermal propulsion (NTP) test requirements that may be generated within other programs. The SNTP PIPET project is actively working with DOE and NASA to assess this possibility

Beck, David F.

English

NASA Technical Reports Server

N93-26963
SPACE
US AIR FORCE
Phillips Eaboratory
Grumman,.Babcock & Wilcox
Brookha_/en & Sandla National Labs
Air Force Facility
DavidF. Beck
PIPET_roj_t Manager
S_d/a NationalLaboratories
The Space Nuclear Thermal Propulsion (SNTP) program is an initiative within the
U.S. Air Force to acquire and validate advanced technologies that could be used to
sustain superior capabilities in the area of space nuclear propulsion. The SNTP pro-
gram has a specific objective of demonstrating the feasibility of the particle bed
reactor (PBR) concept.
NP-TIM-92 765 Facilities
https://ntrs.nasa.gov/search.jsp?R=19930017779 2020-03-17T05:24:50+00:00Z
The term PIPET refers to a project within the SNTP program responsible for the
design, development, construction and operation of a test reactor facility, including
all support systems, that is intended to resolve program technology issues and test
goals.
Facilities 766 NP-'r_t-92
Experiment Data Flow
I Parametors _Limits
Fuel Padiclo
Hot Frtt
Cold Fdt
End Fittings
Dill off:
Coating=
Tamp Capability
Strength
Pressure Drops
MIchanical Perf
Cycling Capability
Plrlllrlltl¢l
Umlts
Data on:
Cowo_on Satoty (FSN_]
PR Operating Margins
Pressure Drops Design Margins
Mechanical Perf Controls
Cycling Capability Thermal/Hydraulics
Tromp CapabHny
GTA
Data on:
Thermal/Hydraulics Controls
Corrosion Design Margins
Neutrontcs Safety
Moderator Mechanical
Pressure Drops Perf.
The PIPET project will provide the necessary capability to complete the final steps
in the SNTP program nuclear test plan.
No known reactor facility in the world is capable of providing prototypical test con-
ditions for SNTP PBR fuel or fuel elements. Although certain nuclear tests (pre-
PIPET) within the current SNTP program may probe the design envelope of the fuel
and fuel element, the best that can be accomplished is very short run times and very
low flow conditions for sub-sized or nonstandard fuel element designs (e.g., PNT
and NET). The high-power densities that make the PBR so attractive will never be
tested to prototypical design conditions until the PIPET element-test reactor is built.
No operational reactor facility in the U.S. is capable of testing a flight-like NTP
reactor core or engine under power (some limited capability exists in the CIS, but
even this does not include any cryogenic hydrogen support and is not currently con-
figured for propulsion type testing). No facility in the world is capable of providing
nuclear test support for NTP reactors or engines under the current and rightful con-
tern for protecting the environment and public health. The investment in building a
high power density fuel element test reactor can be leveraged into a facility that can
also provide test support in meeting certain NTP ground test requirements.-
NP-TIM-92 767 Facilities
DATA l INGIIIIIIRING I
t elll_rrllRl
' I PII A_q_ll"lll
:'
....................... : : "'_ -I
............................... m l..,_.__ __ ,..,,_o_2
NTI
INPRAITRUCTURIE
PIPET TEST REACTOR SYSTEM
The PIPET system includes:
l) Major interfaces with the host site for utilities & logistics support.
2) Facilities including a control bunker, a receiving and assembly building, tem-
porary dry storage areas for irradiated materials, a disassembly building, and
test cell(s).
3) A reactor coolant supply system consisting of a cryogenic hydrogen supply
and hydrogen effluent treatment system.
Facilities 768 l_-'rIM-92
CONTnOL^R_CLESTO_E eASEUN_E t.Ua_T
_E^TM_NTSYSTEM AOOmO_U.
BUNKER RE,_CTOR/E NGINE
__ ' BASEUNE I EFFtUEhrr
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at j
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._L ..................... SECURITY BOUNDARY ............ -_ ..... "_t-
/-
NOT SHOWN: ENGINEERING EVALUATION OPTIONAL ENGINE
BUILDING INTEGRATION
TEST CELL FOR
NON-NUCLEAR
FLOW TESTS
SNTP Baseline Facility Conceptual Site Plan Illustrating Laydown Space for
Optional Expansions
One location for the PIPET test station supported by the SNTP program Environ-
mental Impact Statement is a "green-field" location on the Nevada Test Site (NTS).
This would involve essentially all new construction, with designs developed to meet
program requirements.
NP-TIM-92 769 Facilities
HANGER
The second alternative site for the PIPET facility is a location within Test Area
North (TAN) of the Idaho National Engineering Laboratory (INEL). This would in-
volve renovation, adaptation and use of existing structures such as the Contained
Test Facility (CTF) and TAN 607 Hot Shop Complex.
Facititim 770 NP-'i'iM-92
vent
/
Secondary
Confinamen
Filters
f
hydrogen from
redundant coolant
supply
//_-tor.---L--
Ir o,._J,
_,, nozzle exP
V
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Confinement
Barrier
Secondary
Confinement
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; // Fuel
I Coatings
) , ,o.lspo.,(e.g. hydrogen
flare st|ok or
llqueflcatlon
stage)
Multlple
Stage
FlltraUon
Depiction of the Use of Multiple Physical Barriers and Single-Failure Criteria in
Preventing the Unmitigated Release of Fission Products
The Space Nuclear Thermal Propulsion program is committed to achieving the
highest practicable levels of safety both in program activities and in the ultimate
safety both in program activities and in the ultimate product of the program. Safe-
ty considerations will include: protection of the health and safety of the public;
protection of the health and safety of all employees where program activities are
done; protection of the environment and lands from contamination or damage as a
result of program activities; and protection of the property and facilities used in
the program. Unmitigated release of fission products is prevented by use of con-
cepts such as 'defense in depth.' This includes administrative, physical, and
operational controls and measures. Physical conla'ols for ground testing on NTP
concepts involve multiple barriers including fuel coatings, primary confinement
systems, and secondary confinement systems. Physical barriers to be employed
that will prevent the unmitigated release of fission products are diagrammed
above. As implemented for the SNTP program, the primary confinement barrier
around the reactor looks much like a reactor vessel in a conventional power plant
design, but is functionally much different. The mechanical structure used to sup-
port and direct flow through the multiple stage filtration system also serves as the
balance of the primary confinement barrier. The secondary barrier includes the test
cell structures, which may serve multiple functional needs (for example, weather
protection and shielding).
NP-TIM-92 771 Facilities
T¢_ Arlh:Je
Pdmmry _ Conilnement
"F 1.114,INIIIlll[lil IIII-1"
,_elt_n A.A
Simplified Drawing of the Test Bed Preliminary Design
The test reactor by design contains two major subsystems -- a test bed and a test article.
The test bed nominally provides:
1. A primary fission product confinement barrier.
2. Interfaces between the test article and other programmatic equipment (for example, cool-
ant supply, effluent treatment, and instrumentation and controls).
3. An experiment volume in which the test article (fueled portion of the reactor) is tested.
4. Independent reactivity systems to bring the overall reactor system to the desired preopera-
tional reactivity state; control startup, shutdown, and operational transients; and provide scram
capability.
Test articles are designed for ease of removal to enable rapid test turnaround, ease of reconfigura-
tion, and minimal worker exposures. Reactivity controls within the test bed are designed for
ease of removal, _ that test articles containing their own reactivity control mechanisms can take
advantage of the confinement and programmatic equipment interfaces without having to relay on
other design features. Test article design options can thus be seen to include:
1. A hybrid core design where a previously qualified test article design has a single fuel ele-
ment replaced with a new design.
2. A new test article that makes use of all the inherent features found in the test bed.
3. A new test article with integral reactivity control systems, only making use of the confine-
ment barrier and subsystem interfaces of the test bed.
4. Replacement of the entire test bed/test article assembly with a new reactor design.
F,tcilititm 772 t_-Ttm-92
- -. Coolant$-pply Syo*,,m ...........................
¢ > :........................................
.............. liJLII
Inl*__ , roSt_kRUe
1"" I I Cr_,og..l¢ |
I Mixer --.--/
1 I Cryogenic
2 Adsorber
ATM
' ............................................ EffluentTreatment System- -'
Simplified Line Diagram Of The Baseline Reactor Coolant System
A primary coolant system has been designed that meets the safety and performance require-
ments of the SNTP program for use in the development, demonstration, and qualification of
NTP fuel elements, reactors, and engines. (Integrated stage qualification, including high-altitude
simulation, is not a requirement for the current program.) The functional requirements of the re-
actor coolant system design includes:
1. Provide an adequate, redundant, highly reliable supply of cryogenic hydrogen at required
pressures, temperatures, and flow rates (hydrogen supply - coolant supply system).
2. Interface with the primary heat source (test reactor or engine).
3. Cool the hot primary flow to temperatures compatible with structural and heat exchanger
materials. Catch any core debris material resulting from failures (planned or unplanned) and
maintain it in a coolable, subcritical configuration. Allow access for remote/robotic retrieval of
core debris. Provide initial, coarse-filtering to prevent downstream heat exchanger plugging and
act as a getter for plate out of fission products with boiling points above the cooldown tempera-
ture (debris trap).
4. Provide additional cooling of exhaust flow to temperatures compatible with downstream
particulate filters (hot gas cooler).
5. Filter out particulates entrained in the exhaust flow (procem gas filter).
6. Retain any fission products still in volatile form (for example, krypton and xenon) for a suf-
ficient time to allow for decay (cryogenic mixer/adsorber stage).
7. DLspose of cleaned effluent (flare stack).
NP-TIM-92 773 Facilities
o1E6
1E5
1E4
1E3
1E2 .
Cell A Cell C ETS-1 SNTP
I_1 LP LH2 _1 HPLH 2 mm GH2
NTP Facility Baseline Hydrogen Storage Capacities
i
The PIPET facility includes an initial, baseline coolant supply capacity designed to
envelope the minimum test duration requirements of the SNTP program. Optional
supply system expansions ate planned that will provide capability to meet maxi-
mum test duration requirements. The figure above provides a comparison between
the planned SNTP program PIPET test facility on-site hydrogen storage capacities
against the test-cell hydrogen installations of the ROVER/NERVA Program.
Facilities 774 NP-T[M-92
-.' _ 3000 mKb_.°'_h'w'
"2000[ /
_ooo
om n n n
0 200 400 600 800 1000
Reactor Power (MW_
Baseline Facility Test Durations
The planned baseline reactor coolant supply system, although designed to meet sev-
eral operating point requirements, is best represented by an extensive set of operat-
ing envelopes that are a function of mass flow rates, temperatures and pressures.
However, to illustrate the system performance, a generic NTP reactor was used to
generate a test duration envelope as a function of reactor power. This curve is,
roughly speaking, a line of constant energy. Also shown are operating points for
two conceptual PBR test article designs.
NP-TIM-92 775 Facilities
SUMMARY
• A nuclear test facility has been designed that meets SNTP facility
requirements including:
safety and environmental policies
- minimum impact on waste streams
- provisions for appropriate safeguards and security
- meets minimum SNTP performance levels
- supports expansion to maximum SNTP performance levels
• The design approach taken to meet SNTP requirements has
resulted in a nuclear test facility that should encompass a wide
range of NTP test requirements that may be generated within other
programs. The SNTP PIPET project is actively working with DOE
and NASA to assess this possibility.
Additional information concerning these facilities can be found in:
Allen, G.C. et al. (1992), "Ground Test Facilities for Evaluating Nuclear Thermal
Propulsion Engines and Fuel Elements," in Proceedings of the 1992 Nuclear
Technologies for Space Explorati.on, Jackson, WY, 16-19 August 1992, pp 514-
523.
Beck, D.E et al (1993), "Test Facilities for Evaluating Nuclear Thermal Propul-
sion Systems," to be presented at the Tenth Symposium on Space Nuclear Power
and Propulsion, Albuquerque, NM, January 1993.
Shipers, L.R., and Allen, G.C. (1992), "Handling Effluent From Nuclear Thermal
Propulsion System Ground Tests," presented at the Third Specialist Conference
on Nuclear Power Engineering in Space N_;lear Rocket Engines, Semipalatinsk-
21, Republic Kazakhs 't'tan,September.
Shipers, L.R., and Brockmann, J.E. (1993), "Effluent Treatment Options for Nucle-
ar Thermal Propulsion System Ground Tests," to be presented at the Tenth
Symposium on Space Nuclear Power and Propulsion, Albuquerque, NM, Janu-
ary 1993.
Facilitlu 776 NP-TIM-92


Space Nuclear Thermal Propulsion (SNTP) Air Force facility

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