ML20247D498

Operations Rept of Us Army Matls Research Agency Nuclear Reactor Facility, 600615-641231

ML20247D498
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Issue date:	12/31/1964
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2;._r OPERATIONS REPORT OF THE U.

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ARMY MATERIALS RESEARCH AGENCY NUCLEAR' REACTOR FACILITY 4

l JUNE 15, 1960 TO DECEMBER 31. 1964 P

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NUCLEAR RESEARCH LABORATORY U. S. ARMY MATERIALS RESEARCH AGENCY s

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II. OPERATIONAL PROBIINS k* be; il M[ on A.

Water Leakage Through Shield

.g 1%0. Post u 4 tron tests consisting of shim rod calibrations, power

-, "g ger Initir:

riticality of the nuclear reactor was attained on 15 June

Hm calibration, temperature and void coefficients of reactivity measurements, h acc and determination of the worth of experimental facilities were conducted, i'

co3 culminating on 16 September 1%0, with completion of & T2-hour continuous of run at a power level of one megawatt.

Q M of ge nit The leakage of water through the concrete biological shield had gif ord grown progressively worse since initial criticality. The first attempt

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ah to rectify this was to drain the annulus and apply glass tape and epoxy gh dit ug resin to all vall and floor joints and to finish all surfaces of the 9

annulus with epoxy resins. This effort met with limited success. In the

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lat I annulus there is a cavity created by the humps of concrete over the slant g.

tubes as they pass through the annulus. This cavity had been provided yn..

with aluminum drain lines through the concrete humps to the main section

.h t sts of the annulus. These lines were determined to be leaking and were -

6 plugged. This considerably reduced the leakage in the shield in the y!T' to not region where the first balcony is tied to the shield which is about the y

yg same level as the bottom of the annulus (see Figure 2).

1 8 and Ap j

Late in 1961, an attempt was made to stop the leakage by drilling Q[ C.

selected holes (2-inch diameter) and pressure-grouting a lean cement mix into the holes. This was unsuccessful because very little grout was v

l accepted by the holes. A chemical grout (AM-9) which could be pumped as kq i

a liquid with a preset jelling time was then tried. This was very sue-g.

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cessful, one hole s.ctually accepting about 24 gallons of the chemical oh h{h hyd i grout. Prior to refilling the reactor pool, all vall-to-floor joints in the main pool and the joint around each beam tube was sealed with a to pressure-sensitive tape. These two actions eliminated about 75 percent L-of the leaks.

A;. y y f.$. no 6

t res Based on careful observations of the remaining leaks, additional M

holes were drilled and in February 1962 these holes were pressure grouted 2

with the chemical grout. This operation eliminated all but two minor l

leaks, one of which has since dried out and the other leaks intermittently.

j The remaining leak is mostly an irritant and does not hamper reactor Y

operations. No further corrective action is considered necessary at this

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time.

A.

B.

Corrosion of Heat Exchanger l

In July 1963 the heat exchanger of the reactor coolant system devel-

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mee oped a leak. The heads were pulled and the leaking tube was plugged.

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the Leaks developed on four other occasions and in January 1964 the tube g

bundle was removed and replaced.

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1 19-066-791/0RD-59 Figure 2. REACTOR MODEL 3

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III. CHANGES r:

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Conductivity and pH Indicators In February 1962, cells were installed directly in the pool f [f

- measure conductivity and pH.

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,' the rear of the control console.

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Relocation of Fission Proquef Monitor y,

In March 1%2, the fission product monitor was removed from the

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coolant room to a lover background area outside.

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Pool Top Monitor

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y In March 1%2, an area monitor was installed directly over the pool 4:

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,urface.

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Thermal Power Measuring System

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In May 1%2, a thermal power measuring system was installed based on the temperature difference across the heat exchanger and the flow rate of the primary coolant. It is a most useful and reliable addition to the the control system.

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Organic Removal Unit M.

In July 1%2, an organic removal unit was installed in series with the pool fill and make-up demineralized.

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Main Sump Alarm N.

In July 1%2, a float-operated alarm was installed in the main sump in place of the electrodes which were originally installed.

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G.

Removal of Certain Slow Shutdowns 4

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In July 1%2, the well water monitor, the fission product monitor, the stack alpha, gas and particulate monitors, and the recirculating air fff i

I monitors were removed from the slow shutdown circuits. Although not sta required by the Hazards Sn = ey Report, these monitors were initially she.

connected to the slow shutdown system. Operating experience soon showed lin-that too many unnecessary slow shutdowns were initiated.

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Motor Generator Set tra:

was In August 1%2, a motor generator set was installed to provide regu-l lated power to the more sensitive electronic components of the control p,

system.

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Lov Water Level Alarm i

floc ter:

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I In October 1%2, an alarm, operated by a float, was installed which indicates a drop in pool water level if it exceeds 6 inches from the g

overflow gutter.

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Water Sampling Lines

'N In October 1%2, lines were installed to pemit sampling tne primary

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vater, the secondary water into the heat exchanger, and the secondary Q Ik; water out of the heat exchanger.

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High Temperature Alarm we

• .Oi f'*fM In November 1%2, an alarm was added to indicate an increase above II@h 103 F in the primary system.

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Drain on Exhaust Line i

9b jg-In February 1%3, a manually operated drain line was installed in

&plifE flowed back into the absolute filter.

c/ the exhaust line to the stack to permit draining condensation before i't EQ9

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Low Flov Scram 6

l In March 1%3, the slow scram point for low primary coolant flow was i

h'changedfrom500gpmto950gpm. The audible alarm at a flow less than d

g 800 gpm was discontinued.

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Secondary Flow Measuring System d{d C..

In October 1%3, a flow measuring system which displays the flow dEate in the coolant room was installed in the secondary coolant lines.

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ORfOvelpressurization Protection Device

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( In November 1%3, an overpressurization protection device was in-

stalled to prevent an increase in internal pressure of the containinen't f, shl1 of more than 2 psi in the event of a leak in the compressed air 4Nnes. The device consists of a two-inch-diameter pipe forming a 'five-u t

oot., trap which is water filled. It is essentially the same as the trap famed on some exit lines as described in the Hazards Summey Report., This trap is filled with water and the level is checked each shift. The device t

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,.eshin place during the 1%4 leak test and did not increase the leak rate.

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YBeam Tube Modifications

)$. In. July 1%4, three beam tube extensions were modified to pe U

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f' looding from the pool top in order that they may be used as water shut-ters for the installed experiments.

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IV. R3SEARC R0 GRAMS T

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Present and Planned Programs k

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Reactor Fac;11ty: Six-inch horizontal beam tube

&; 4 Principal Investigator: Dr. John J. Antal, q@

l U. S. Army Materials Research Agency Experimental Apparatus: Velocity selector - crystal spectrometer 24; (VSC Spectrometer)

-y Status: Spectrometer in place, velocity selector being fabricated

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Duration:

Indefinite 1,

Experiment:

Studies of the neutron spectra from various low tem-perature moderator configurations situated in a transmission geometry povel with respect to the reactor core are being conducted. It is estimated

- g explc that these studies will take approximately one year, after which studies

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neutt of defects in materials, lattice vibrations in materials, and further q

relat neutron moderation studies vill be made using the long wavelength neutrcns w

Gmanating from the low temperature moderator configuration.

5 2.

Reactor Facility:

Six-inch horizontal beam tube fQ Principal Investigators:

Dr. H. Boutin, Dr. H. Prask, and Mr Dr. S. Trevino, Picatinny Arsenal g

d(($f; Experimental Apparatus:

Fixed scattering-angle time-of-flight spectrometer (slow neutron chopper)

Status:

In operation Duration:

Indefinite expyo ev vork Experiment:

Studies of low-energy molecular motions and lattice y

vibrations in polymers and hydrogen-containing inorganic compounds related

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• desig of te to explosive materials are being conducted.

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Reactor Facility:

Six-inch horizontal beam tube 3

',4 Principal Investigators : Dr. D. Chipman and Dr. L. Jennings, U. S. Army Materials Research Agency

.:.n Experimental Apparatus:

Polarized neutron diffractometer 4

Status: Diffractometer in operation. Polarization means being installed.

v Duration:

Indefinite 5.

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Experiment: Studies of electron distribution and the effects of

. [ temperature on their distribution are being conducted. Similar studies hare being conducted using X-ray diffraction techniques; the two results tcomplement each other and result in more complete conclusions.

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4.

Reactor Facility:

Six-inch horizontal beam tube J. -

Principal Investigators:

Dr. H. Boutin, Dr. H. Prask, and n

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Dr. S. Trevino, Picatinny Arsenal Experimental Apparatus:

Triple-axis crystal spectrometer

'b 46 Status: Two axes in operation. Third axis being installed.

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Jg Duration:

Indefinite Kil Experiment: Use as a triple-axis unit is marginal at the present

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power-level. If feasible, studies will be made of lattic dynamics of g

explosives and related materials. Otherwise, it will be used only as a

..L neutron diffractometer for crystallographic studies of explosives and Tde related material..

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Reactor Facility: Six-inch horizontal beam tube

.k"#;h Principal Investigators:

Dr. H. Boutin, Dr. H. Prask, and Dr. S. Trevino, Picatinny Arsenal d

Experimental Apparatus:

Neutron diffractometer

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Status:

In operation e

Duration:

Indefinite Experiment: Used exclusively for crystallogra hic studies of O

and HMX. The

,;%g explosives and related materials,e.g., Pb(N )s, Ba(Na a, 3

vork is currently being done at room temperature but a cryostat is being D designed to make it possible to study structural changes as a function Vy 4.h;;~r ' of temperature.

6.

Reactor Facility:

Six-inch horizontal beam tube

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.6 Principal Investigators:

Dr. H. Boutin, Dr. H. Prask, and Dr. S. Trevino, Picatinny Arsenal;

'jf Dr. M. Kronman, Army Natick Laboratories

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Experimental Apparatus: Variable scattering angle time-of-flight

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.i spectrometer (slow chopper) id Status: Designed a-*

Duration:

Indefinite if installed

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d' Experiment:

Studies of surface adsorption and hydrogen bonding area

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in solutions.

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Reactor Facility: Six-inch horizontal beam tube tube did :

Principal Investigator:

Dr. D. Walker, 1,5 U. S. Army Materials Research Agency tiga-Experimental Apparatus:

Triple-axis crystal spectrometer in t' 3 p f e' Status: The first two axes of this apparatus vill be fabricated sqff the and installed. The entire spectrometer vill be installed

${ftubei at the higher power level.

cygtprod hge;refl Duration:

Indefinite

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YM able Experiment: Diffuse scattering studies of short-range order in tain alloys, and simple inelastic scattering studies of the dispersion rela-i tions o'f lattice vibrations in crystals.

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Reactor Facility:

Six-inch horizontal beam tube h

Sp Principal Investigator: Dr. John Antal, mfe U. S. Army Materials Research Agency W b neot Experimental Apparatus: Velocity selector - crystal spectrometer M}oper e,tg., were i Status: Designed

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@jg[{obtt Duration:

Indefinite if installed gy; Use at One Megawatt: The low-temperature moderator configurations

' fi vill provide long wavelength neutrons suitable for studies of defects in

($d materials and lattice vibrations in materials.

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Completed Programs J. "i ei 1.

Reactor Facility: Six-inch horizontal tube, tangential to core Principal Investigator:

Mr. C. R. Porter h

l Experimental Apparatus:

Single crystal spectrometer and twenty-foot-long bent tube y

Status:

Completed. Ref. AMRA Technical Report AMRA TR 63-25, N

A Subthermal Neutron Beam Collimate'd by l

Total Reflection.

.g, Duration: September 1962 - May 1963 p@

Experiment:

A method for providing an experimental beam of long l

vavelength neutrons was investigated. The method involved allowing l

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neutrons to travel from the vicinity of a reactor core to the experimental i y1

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ky means of a curved hollow tube.

The method makes use of the i

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'inenon of cotal internal reflecuion of long wavelength neutrons to

• tively transport subthermal neutrons the length of the tube. The i

fyss slightly curved so that a line-of-sight path through the tube j

Jot exist. The tube was 20 feet long, had an internal diameter of r

%ches, and was made of copper. A nickel-plated tube was also inves-

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s ted. Wavelength spectra taken of the beam of emergirg neutrons peaked g[Be vicinity of 3 75 A.

u The general shape and position of the spectrum i

'* de'rging neutrons was investigated as a function of the tube curvature, a

e l nternal finish of the tube, and the reflective natorial inside the patId i

atalled g,c The range over which these parameters could be varied did not

' uce significant variations in the spectrum. Using nickel as the r'*flective material instead of copper did, however, increase the total e

I 5. fMensity by a factor of nearly four. Gnmmnn and fast neutrons were not i

iM'd to negotiate the curvature of the tube and as a result the beam ob-in

}la-tained was virtually free from contamination.

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Reactor Facility: Six-inch horizontal tube h):

Principal Investigators: Dr. W. Z. Leavitt and Mr. A. W. Schultz g

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,j:, 7 Experimental Apparatus:

A collinated neutron beam with homoge-e 7

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neous intensity over a 10-inch-diameter area passing through a crane-peter

• ' " rated sliding sample chamber. Samples to be radiographer by neutrons ve$e inserted in the beam, which in turn activated a foil behind the l

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4 ample. The foil was then placed on X-ray film and an image of the sample bbtained.

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Completed. Ref. (1) AMRA Technical Report, WAL TR 142/67,

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j The Feasibility of Using Neutron Radiography

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as a Nondestructive Testing Technique; (2) AMRA Technical Report, AMRA TR 64-31,

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The Neutron Radiography of Uranium and Iud.

f Duration:

October 1961 - December 1963 j

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jW Experiment:

A study of the feasibility of neutron radiography as a nondestructive technique and the application of such a technique to

'thic.k sections of uranium and lead in the Army Shielding and Weapons f

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y-3 Reactor Facility: Six-inch slant tubes (2)

Principal Investigator:

Mr. R. D. Micheleni, AVC0 Corporation,

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conducted under Project Sleigh Ride, r

.i Air Force Contract AF 04 (694) 297

gf Experimental Apparatus

Described belov

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Completed. Equipment available for other uses.

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Duration: July 1963 - May 1964

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tol' Experiment: These facilities were originally designed and used

![ the for the production and eventual study of radiation damage effects within

"' T lea solid state and other type electronics components. Each of these irradi-Mr out ation facilities has ample volume to accommodate entire circuit boards (ellipsoid, 5" x 7") including the various components, connectors, and

%g mea j: riu wiring mounted thereon. In addition, quick disconnect cables providing

, M' ass fifty electrical leads to external instruments is already an integral part

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of these existing facilities. Thus, measurement of current, voltage, and Y

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other electri, cal parameters is easily accomplished upon' electronic devices y

being tested while simultaneously undergoing irradiation.

.g The loading and emptyfag, plus insertion and withdrawal of successive

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canister loadings is quite rapid and safe. Specific amounts of a rad.t-i' tion dose can be accurately controlled because of the complete ease of 9

canister positioning. All the above operations can be performed while san the nucflear reactor is operating at full power. No undue delay has been 4

ope encountered because of the necessity of having to shut down and restart the reactor following each and every loading and withdrawal.

4.

Reactor Facility: Six-inch slant tube g

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. Principal Investigators:

Dr. G. K. Gaule, Institute for Explora-j p,.

tory Research, U. S. Army Electronics Research and Development Laboratory; M

Dr. J. L. Bloom,. Division of Isotopes W

Development, U. S. Atomic Energy Division 4

Experimental Appuratus: Watertight canister with sixteen-foot g

tube to permit bringout wires (similar to previous experiment in "3")

2 Status:

Coupleted k

f*e Duration: October 1963 kh Experiment: The Institute for Exploratory Research, U. S. Army Electronics Research and Development Laboratory, and the Nuclear Division

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of Martin-Marietta Conoration had conducted a joint program extending i

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over a two-year period which had as its objective the davelopnent of boron h$

y thermistors as devices for measurement of thermal neutron flux and temper-

,y re ature within nuclear resctors. The program had proceeded to the point Mt where proof-of-principle thermistors had been fabricated and calibrated over an adequate temperature range. They had proven to be accurate and i y @p?r,Et me reproductive sensors of temperatures up to 500 C.

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In order to study the effect of an actual radiation enviro /iment on the i fn characteristics of the thermistors, an aluminum irradiation capsule was M

fabricated in a size suitable for insertion in a slant tube of the AMRA d

12 Reactor.

The capsule was capable of testing three thermistors simultane-ously. Themal neutron fluxes in tLe range of 10 to 10 8 n/c:F/secwere l.h 1

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')A Noired. In-pile t(mperatures of greater than about 150 C could not be

' lerated by the capsule because of the use of elastomeric materials for 1_

Abe sealing of closures. It was possible to subject the capsule to at I

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east five distinctly different neutron fluxes in the range stated with-11-g

.cutevithdrawing the capsule from the reactor, and to make electrical f' measurements of the thermistors at each flux value after thermal equilib-N rium had been attained. Temperature control was not required, other than

' assurance that the temperature limit above was not exceeded.

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/C. Irradiation Programs

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Reactor Facility:

Pneumatic tube b t.a

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Principal Investigator:

General use g-g Experimental Apparatus:

Two-inch-diameter tube through which

g. L samples say be pneumatically inserted and removed from the reactor during

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soperation.

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Status:

In operation Experiment: Simila.* use as for the slant tube discussed above.

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. Particularly used for irradiations of short duration. Has been used in i

f programs for U. S. Army Materials Research Agency, Picatinny Arsenal,

Detroit Arsenal, U. S. Army Natick Laboratories, y

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Reactor Facility:

Six-inch slant beam tube

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Principal Investigator: General use h 4fN".tvo-inch-diameter sample tubes in which samples may be inserted and Experimental Apparatus: Water-filled six-inch beam tube with 4 Dp

..s< removed during reactor operation.

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Status:

In operation p.

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Indefinite b

Experiment: Used for activation analysis of samples, including

[()phigh purity samples containing trace impurities and for inducing slight Pradiation effects in materials.' Has been used in programs for U. S. Army U,

l-Materials Research Agency, Picatinny Arsenal, Detroit Arsenal, U. S. Army l

ANatick Laboratories and the U. S. Army Electronics Research and Develop-l

4 ment Laboratory, Fort Monmouth.

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3 Typical Uses of Neutron Activation Analysis (NAA) n a.

Analy2.ed ultrapure germanium and gern:a.nium dioxide for all L

yimpuritiesthatcouldbefoundusingactivationanalysis, p

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Determined manganese content in spores submitted by Quarter-

] master Corps in Natick (nondestructively).

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' j Analyzed beryllium and beryllium oxide for all im c.

I that could be found by activation analysis (nondestructively) purities

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Analyzed oil sample submitted by Detroit Arsenal.

r-samples were part of a vear studies program.

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~1 Over 200 samples have been analyzed, Manganese and copper vere fopnd.

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j hk2 are to be put into the reactor are performed using NAA. Rapid deter e.

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have been analyzed and founf to contain appreciable quantitie f

t s,y manganese.

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Ultrapure water has been irradiated and found to contain the g.

'&gj unexpected impurities:

copper, manganese, sodium, and chlorine.

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Niobium has been determined nondestructively in iron, s

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y Tantalum has been determined in micro samples of silver.

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nondestructively in the ppb range. Tungsten diffusion impurities were found in qu M]%

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Lanthanum vsa found in ultrahigh purity carbon black.

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an explosion involving a high-vacuum system containing s h@;

tion for oxygen using the AMRA Reactor is 10 mg.It was found expe g* j -

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Hydrofluoric acid hns been e.nalyzed for impurities and found n.

to contain arsenic.

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found to contain copper. Hydrogen peroxide has been analyzed for trace impurities and ff

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copper, manganese, argon,has been analyzed and found to contain t' races cf W

p.

Polyethylene and sodium.

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-g determino iodine, bromine, and chlorine. Sea water htus beer. analyzed using q.

j )Jl unecessfully to rain vs.ter and riser vater,The technique was also applied

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Etman hair $mple's have been analyzed for copper, manganese r.

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gold, and arsenic.

They were analyzed nondestructively.These samples w and weighirs 50 g.

Teflon samples have teen analyzed for sodium nondestructively s.

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Niobium samples have been analyzed for silicon using NAA and biochemistry.

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It has been found that the major constituents of practically

!ny sample can be determined qualitatively very rapidly using short

{eactor irradiations and gamma-ray spectroscopy.

v. ' It has been observed thr:.t many materials that are reputedly Lure and void of any impurities can be analyzed by NAA nondestructively

nd found to contain several unexpected elements. This can be done

apidly and inexpensively, a

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