ML20203P244
| ML20203P244 | |
| Person / Time | |
|---|---|
| Site: | 07001374 |
| Issue date: | 03/04/1986 |
| From: | Bowen R IDAHO STATE UNIV., POCATELLO, ID |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 26870, 460976, NUDOCS 8605060430 | |
| Download: ML20203P244 (24) | |
Text
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Nuclear Regulatory Commission i
Region IV Material Radiation Protection Section N
611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
Dear Sir:
Enclosed are six copies of an application for renewal of the Idaho State University license for Special Nuclear Material, as described.
The renewal request is for five (5) years and renewal of license is for the original License No. SNM-1373, due to expire April 30, 1986.
1 The enclosed application has been prepared and is being submitted to you pursuant to Title 10, Code of Federal Regulations, Part 70.33, using the format previously submitted for our license.
If you desire any further information, please contact:
Dr. V. Charyulu, Dean School of Engineering Idaho State University Campus Box 8060 g
Pocatello, ID 63209 m
I (208) 236-2911 rk W
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- o Your attention to this matter is appreciated.
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RECCIVED SY LFMS Enclosures [*
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8605060430 860304 PDR ADOCK 07001374 C
PDR ISU is An Equal Opporturury Employer
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e IDAHO STATE UNIVERSITY SCHOOL OF ENGINEERING
SUBJECT:
.. Idaho State University desires renewal of special
'l nuclear material license SNM-1373, to receive,
. store and use the special nuclear material listed below:
(1) 1510 gm of Uranium 235 in the form of Uranium-Aluminum fuel plates.
(2) 1 gm of Uranium 235 contained in a fission counter and Uranium-Aluminum foils, e'
(3) 20 gm of Plutonium 239 in the form of sealed Pu-Be neutron sources.
ENCLOSURES:
(1) Biographical Data for Operating Staff.
(2) Water Handling System Diagram (3) Water Handling System Electrical Diagram (4) Source Dose Rate Calculation (5) Area Monitor Specifications (6) Ground Floor Building Plan (7) Basement Floor Building Plan (8) Idaho State University Map (9) Pocatello Area Map REFERENCES (1) Rutgers University Special Nuclear Material License SNM-431, Docket Number 70-461.
^
(2) Idaho State University Application for 104 Construction Permit, Class 104 Facility License and By-products Materials License, April 3, 1967, License Number SOP-934-2, Docket Number 55-638 (3) Emergency Plan for the Nuclear Facility at Idaho State University. Rev 3 02/85 I
The School of Engineering at Idaho State University uses the suberitical assembly to strengthen the existing undergraduate and graduate programs in the area of nuclear science and engineering.
The suberitical assembly was originally assembled and operated at Rutgers University, New Brunswick, New Jersey.
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Information required by sections of 10 CFR 70 will be listed after the sequence number of the section in 10 CFR 70 requesting that information.
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70.22.1 Information about the applicant, his plans and qualifications.
NAME: Idaho State University ADDRESS: Pocatello, Idaho 83209 DESCRIPTION OF BUSINESS OR OCCUPATION: Institution of Higher Learning:
Idaho State University is operated by the State of Idaho with its principal office at Pocatello, Idaho. At present the principal officers and board members are:
Charles D. McQuillen, Executive Director, Office of the State Board of Education, LBJ Building #307 650 W. State St. Boise, Id. 83720 Diane Bilyeu, President, 11076 N. Philbin Rd.
Pocatello, Id. 83202 Dennis E. Wheeler, Vice President P.O. Box I, 505 Front Ave.
Coeur d'Alene, Id. 83814 Cheryl Hymas, Secretary, 1441 Rainier Dr.
Jerome, Id. 83338 George E. Alvarez, 2850 Christine Boise Id. 83704 Roberta L. Fields, Box 13 New Meadows, Id. 83654 Charles M. Grant, 168 Harvard Rexburg, Id. 83440 Mike P. Mitchell, 316 Skyline Drive Lewiston, Id. 83501 Jerry L. Evans, State Superintendent of Public Instruction 650 W. State St. LBJ Building.f282 Boise, Id. 83720 University Officers Richard L. Bowen l
Administration Building, Idaho State University President of the University Lawrence H. Rice Administration Building, Idaho State-University Academic Vice President Philip H. Eastman, M.B.A.
Administration Building, Idaho State University Financial Vice President (All of the above board members and officers are citizens of the United States. There is no concrol or ownership exercised over the applicant by any alien, foreign corporation, or foreign government.)
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C 70.22.2.a Activitiy for.which the material is requested The material is requested for educational and training programs.
A total weight of 1511 gm of U-235 is requested in this application.
1510 gm of U-235 are contained in 150 Uranium-Aluminum fuel
- plates. - The fuel plates will be loaded in various lattice arrangements in a water filled tank to produce a p
-suberitical assembly ~ The fuel plates may be used singly for a quasi homogeneous assembly or in groups of two or more to produce a heterogeneous assembly.
The remaining 1 gm of U-235 b ing requested will be contained in a fission counter and Uranium-Aluminum foils. These foils will be used as neutron detectors in some experiments performed with the suberitical assembly. The materials will be used primarily for instructional purposes in senior and graduate level courses.
Research programs utilizing the materials in the suberitical assembly will also be encouraged. No activity will be performed without the prior approval of the Dean of the School of Engineering.
Some of the experiments to be carried out with the suberitical assembly are:
(1) Approach to critical (2) Flux distribution measurements (3) Exponential pile measurements (4) The Fermi age (5)' Optimum cell dimensions in a heterogeneous suberitical assembly (6) Effect of fuel plate thickness on multiplication factor (b) The place and the general plan for carrying out the activity:
The material will be used and stored in room 23 in the basement of the Lillibridge Engineering Laboratory at Idaho State University. Room 23 is 20' by 20' square with a 12' ceiling.
~ The floor is a 4 inch reinforced concrete slab. The concrete was poured over the undisturbed soil and reinforced with #3 bar
- spaced 12 inches apart. The floor will safely accommodate the weight of the entire suberitical assembly. Located in the same se' tion of the basement is the Health Physicist's office and the e
decontamination facility'. This section of the basement is a controlled access area.
Only the Reactor Supervisor, selected
+
faculty, members and students employed by the School of Engineering have keys to this section of the basement.
70.22.E(3)
Period of time for license:
This license is requested for a period of 5 years.
It is expected that a request for renewal will again be submitted at the end of that period.
3
70.22.a(4)
Specifications of the special nuclear material:
(a) Uranium-Aluminum fuel plates:
The fuel plates were fabricated in 1960 by M & C Nuclear, Inc.,
for Rutgers University, New Brunswick, New Jersey. The 1
i manufacturers specifications for the plates are:
Total number of plates 150 Total weight of Uranium 7614.79 gm Enrichment of U-235 isotope 19.83%
Total U-235 content 1510.27 gm U-235 leading per plate 17.27 gm Overall dimension of plate (26"+.015")x(3 0"+.015")x
(.080"+.006")
Dimensions of Uranium bearing i
portion of the plate.
(24"x 2.75"x.04")
Cladding thickness 0.020" (b) Fission counter and Uranium-Aluminum foils:
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(i) Fission counter Total Uranium weight 0.002 gm U-235 enrichment 93%
Total U-235 weight 0.002 gm (ii) Uranium-Aluminum foils Total Uranium weight 0.3 gm U-235 enrichment 93%
Total U-235 weight 0 3 gm The specifications for the above items were taken from the U ited States Atomic Energy Commission's Nuclear Material n
Transfer Report.
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Two Pu-Be neutron sources, obtained in 1962 from Monsanto Research Corp., Mound Laboratory, under and AEC loan, later to become a grant.
Container inside dimensions 0.82" ID x 0.75" H Container outside dimensions 1.02" OD x 1.45" H with 10-32 tapped hole.
Source material composition Source S. N. M-1197 18.04 gm Pu, 7.86 gm Be Source S. N. M-1198 1.80 gm Pu. 7.86 gm Be Neutron emission 6
Source S. N. M-1197 2.10 x 10 n/see 5
Source S. N. M-1198 2.80 x 10 n/see The specifications for the Pu-Be neutron sources were taken from
'the Mound Laboratory shipping data form supplied with the sources.
70.22.a.6, Technical qualifications of the applicant and staff:
Attached as enclosure (1) are the biographical data for those members of Idaho State University who will have direct responsibility for the operation of the suberitical assembly.
Varada P. T. Charyulu, Ph.D. Dean, School of Engineering i
Albert E. Wilson, Ph.D, Professor of Engineering, Reactor Supervisor.
Dewitt T. Neill, Ph.D Professor of Engineering, Radiation Safety Officer.
70.22.a.7 Equipment and facilities to protect health and minimize danger to life and property:
(a) The handling procedure of the material:
(i) Fuel plates While handling the fuel plates disposable plastic gloves or other hand coverings will be used.
(ii) Uranium-Aluminum foils While handling the foils disposable plastic gloves, or tongs as appropriate will be used.
c (iii) Pu-Be neutron sources l
The sources will be handled with tongs or source I
holders in such a manner that the sources will be a minimum of three feet away from any person.
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(b) Working area:
See 70.22.a.2.b The place and plan for carrying out the activity.
(c) Measuring and Monitoring Instruments Beta / gamma and neutron sensitive film badges, processed by R.S. Landauer Jr. & Co., are issued to all personnel working with the special nuclear material.
NaI crystal detector Ludlum Model 2200 single channel analyzer
(
Ludlum Model 14A Geiger counter with Type 146 probe and external speaker.
Ludlum Model 12 count' rate meter with the following attachments:
Type 146 GM probe Type 44-2 gamma probe Type 44-3 gamma probe Type 43-1 alpha probe Type RSN-127A fast neutron probe with thermalizing attachment Technical Associates Type SFM-5V-3 Gas Flow 2-pi counter Technical Associates Type CP-5 (cutie-Pie)
In addition to the above instruments, all portable radiation monitoring equipment listed in the "By-Products Materials i
License" (reference 2, page 27, para. 9) will be available.
(d) Waste disposal There will be very little contamination resulting from the handling and storage of materials in our poetession under this license. Contaminated material will be controlled and disposed of by Health Physics personnel in accordance with the procedure established under Radioactive Materials License IDA-33-1, issued to the university by the State of Idaho.
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(e) Storage facilities and security measures:
There is a minimum of two locked doors which will prevent intruders from entering the area where the suberitical assembly will be housed. When the suberitical assembly is not in operation the uranium-aluminum fuel plates will be secured in their shipping container. The shipping container will be stored i
in room 23 The fuel plates may be left in the assembly tank or in the shipping container. Both the assembly-tank and fuel shipping container will be locked when containing fuel. The remaining 1 gm of U-235 will stay in room 23 All entrances to the building are secured from 11:00 p.m. to 6:00 a.m. on weekdays and stay locked on weekends and holidays. Also, the building is patrolled by Idaho State University security guards four times daily at random hours between 4:00 p.m. and 8:00 a.m.
(f) Water handling system:
Distilled water will be used in the suberitical assembly. The distilled water will be stored in three polyethylene drums of 53 gallons capacity each. The drums will be connected to each other by a 1/2 inch tube in such a manner that water can flow freely from one tank to another.
At the beginning of each experiment the water will be pumped from the storage tanks to fill the assembly tank. At the end of each experiment the water will be drained out of the assembly tank through a 3/4 inch drain line at the bottom of the assembly tank.
A schematic diagram of the water handling system is provided as enclosure 2.
The drain pipe will be opened and closed by a "normally open" solenoid valve.
In the event of a power failure the pumps will shut off and the drain valve will be open.
Without water as moderator the neutron multiplication factor of j-the assembly will be extremely small.
Power feeding the solenoid drain valve and the pump will first go through a double pole open solenoid switch. This switch will be held open by the criticality alarm signal.
In the event of accidental criticality, power will be cut off to the pump and solenoid drain valve, causing water to drain out of the assembly tank.
Furthermore, the solenoid switch will be wired in such a manner that any attempt to disconnect the solenoid switch from the criticality alarm will result in loss of power to both the pump and the solenoid drain valve. The wiring diagram for this installation is provided as enclosure 3 7
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70.22.a.8 Proposed procedure to protect health and minimize danger to life and property:
(a) Radiation Hazard:
(i) Radiation hazard from suberitical assembly in operation.
Reference 1, page 11 provides the information below:
Direct Calculations BSF Data Fast neutrons
.157 mr/hr
< 4.6 mr/hr Thermal neutrons
.21 mr/hr Gamma photons 5 0 mr/hr 2.6 mr/hr These intensities are not expected to constitute a hazard to personnel for the following reasons:
- 1) the above values are given at the surface of the assembly tank, personnel are not routinely that close to the assembly,
- 2) personnel will only spend a few hours a week in the vicinity of the unit while it is operating,
- 3) Personnel are required to actively pursue the ALARA policy.
Operation of the suberitical assembly has not revealed any radiation hazard to personnel. However, a criticality alarm is installed, as required by section 70.24, in room 23 Furthermore, all personnel involved in the operation of the suberitical assembly will wear a cumulative gamma photon and neutron sensitive film badge.
In addition to the criticality alarm, there will be a gamma detector in operation at all times in room 23 while fuel is in the assembly tank.
(ii) Radiation hazard from neutron sources:
The Pu-Be neutron sources will be located in the lattice of the l
suberitical assembly or in the graphite pedestal, when the l
suberitical assembly is in operation.
Otherwise the sources l
will be stored in a neutron howitzer in a vault in the physical l
science building basement. The sources will be moved to room 23 in a paraffin block approximately 18" on a side.
The sources j
will be handled with tongs or source holders under the direct supervision of the reactor supervisor or the radiation safety l
officer. The handling devices will be 3 feet long. The dose l
rate at 3 feet from the strongest source is 2.2 mr/hr.
Calculations of this dose rate are provided as enclosure 4.
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(b) Fire hazard:
No materials or chemicals will be stored in room 23 which could present a fire hazard. The normal fire rules will be observed.
There is an "ABC" cJass fire extinguisher next to the door of room 23 and two more in the same section of the basement. A heat rise sensor is located in the ceiling above the assembly tank.
Activation of the sensor by a fire will sound the building fire alarm and energize an indicator light on a fire location display panel, located at the east main entrance. A leak test will be performed on all fuel plates and source material in the event of a fire which may have caused damage to same.
(c) Accidental criticality:
The assembly has been designed to be suberitical under all conditions.
Operation has verified the design calculations.
Criticality may occur by introduction of a superior moderator or a reflector material to the assembly. The procedure below is in effect to prevent accidental criticality:
"The following materials are not to be taken into the suberitical assembly area without the permission of Professor A.E. Wilson.
Permission may be granted for only one material at a time and cannot exceed the limitation stated: graphite 8 lbs., Beryllium 2 lbs., Beryllium oxide 4 lbs., heavy water 21bs., fissionable isotopes (U-235. U-233, Pu-239) 3 gm of any one or combination except for the Pu-Be source necessary for facility operation. This limitation applies to other chemical forms or mixtures containing the above material. Detailed plans of the experiments to be conducted must be submitted before approval will be granted.
A criticality alarm system is installed in room 23 The alarm is manufactured by Ludlum Instrument Company, and fulfills the requirement stated in 70.24 (d) Personnel monitoring:
Personnel present in room 23 during operation of the suberitical assembly will wear personnel dosimetry. Staff and students will be issued gamma, beta, and neutron sensitive film badges processed by R.S. Landauer Jr. & Co.
Visitors will be issued gamma sensitive pocket dosimeters. All personnel monitoring on campus is in accordance with 10 CFR 20 and the ALARA program is actively practiced.
9
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l (e) Leakage testing and surveys:
Ten percent of the fuel plates will be leak tested using the standard smear test for alpha contamination prior to each experiment and at normal inventories. The Uranium foils will be tested in conjunction with the fuel plates. A general area contamination survey of room 23 will be performed in conjunction with-the fuel plate and foil surveys. In addition a monthly contamination survey and general area radiation survey are performed in room 23 Standard procedures required by radioactive materials license IDA-33-1 issued by the State of Idaho are followed in the event of detected contamination.
70.22.b, (i) Inventory procedures:
Inventory of the material will be performed at least twice every year.
It is anticipated that all fuel plates will be used in any experiment. This fact, and assembly procedures, will reveal any missing material. An approved emergency plan establishes procedures to be followed in the event of a loss or theft of special nuclear material.
(Ref 3, page 16)
(ii) Administrative control:
The Dean of the School of Engineering will be fully responsible for the safe storage and the use of the material. The Reactor Safety Committee (RSC) has reviewed and approved all plans and procedures for the usage of the materials in the suberitical assembly. The RSC was formed at the request of the NRC in 1968 to review and approve experimental procedures performed with our AGN-201 reactor.
There must be a minimum of two persons in room 23 when operations involving the special nuclear material in the assembly are in progress. Access to room 23 and the fuel containers will be controlled by the distribution of keys. This distribution will be as follows:
The Dean, School of Engineering, and the Reactor Supervisor will each hold one key to room 23 The Dean and the Radiation Safety Officer will each hold one key to the fuel storage container and the assembly tank access cover.
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a 70.24 Additional requirements:
(a) (1) Criticality Alarm:
The criticality alarm is a Ludlum model 300 remote area monitor.
.It is installed six feet from the assembly tank and has a type 18503 detector hard mounted to the monitor case. The unit specifications are provided as enclosure 5 (a) (2) Emergency evacuation procedure:
The procedure below will be carried out under the direction of the person responsible for the assembly at the time the emergency occurs.
All power to the pump and solenoid drain valve will be cut off by placing the drain valve and pump power switch in the OFF position.
(This step backs up the function performed when the criticality alarm is activated)
The portable gamma survey meter will be taken from room 23 by the evacuating personnel.
Once all personnel are out of room 23 the door will be closed, the alarm on the emergency exit door for room 24 will be tripped, and a radiation survey will be performed in all areas adjacent to room 23 If radiation levels above normal are detected outside of room.23 the building fire alarm will be activated to evacuate the entire building.
Building ventilation will be secured by pushing the " Penthouse Power Emergency Trip" switch located on the wall facing the health physics office.
The health physicist, Radiation Safety Officer, and the Dean, School of Engineering will be notified of the emergency.
Building reentry will be directed by the Radiation Safety Officer. Exits and access routes to and from the basement are shown on the buildir.g floor plans provided as enclosures 6 and 7 Emergancy equipment and communication and alarm systems will be tested every Captember at the beginning of the scholastic year.
Emergency proceduc*s will be distributed to permanent staff and personnel who will werk with the suberitical assembly.
Periodic reviewoftheseprocedereswillyhecomplishedbydrills.
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Biographical Records WILSON, Albert E.,
Professor of Engineering Professional Experience 1966-present: Idaho State University, Pocatello, Idaho.
Professor, School of Engineering. Established the nuclear program at ISU leading to the Master of Science in Nuclear Science and Engineering. Developed the nuclear option in the General Engineering Program. Courses taught at ISU include:
Graduate Nuclear Instrumentation Nuclear Instruments and Control Laboratory Nuclear Engineering Experiments Senior / Graduate Nuclear Reactor Design Introduction to Nuclear Engineering Nuclear Reactor Analysis Pulse and Digital Circuits Junior / Senior Electrical Properties of Materials Fundamentals of Electrical Devices and Systems Summer employment has included:
4 1966 Idaho Nuclear Corporation, National Reactor Testing Station Idaho Falls, Idaho 1967 Argonne National Laboratory, National Reactor Testing Station, Idaho Falls, Idaho 1968 Lawrence Radiation Laboratory, Livermore, California 1964/66 University of Oklahoma, Norman, Oklahoma. Assistant Professor of Nuclear Engineering i.
1959/64 University of Oklahoma, Norman, Oklahoma. Special Instructor in Nuclear Engineering and Director of the l
Nuclear Reactor Laboratory (part time) while working l
on Ph.D.
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WILSON, Albert E. (cont) 1955/59 Los Alamos Scientific Laboratory. Staff member in K-Division (reactor development). Principal activities involved development and installation of instrumentation and control systems for the experimental reactors built and operated during this period. These instrumentation systems involved measurement and control of temperature, pressure, fluid flow, etc., as well as the more usual radiation and reactor control problems. The reactors included LAPRE I, LAPRE II, and LAMPRE. The LAPRE reactors were homogeneous, aqueous solution types while LAMPRE was a molten plutonium, sodium cooled, fast reactor. These two types provided a very wide range of instrumentation problems. Also included during this period was work on instrumentation for experimental liquid sodium heat transfer loops and for material corrosion studies.
1951/55 National Bureau of Standards: 1951-53, Physicist, Microwave Standards Group; 1953-55, Instrumentation Engineer, Cryogenic Engineering Laboratory. Principle activities were in the solution of instrumentation problems encountered in the development of new systems. This experience provided a background in electronics which has been invaluable in working with other instrumentation problems.
. (cont.)
CHARYULU, Varada P.T., Dean, School of Engineering Citizenship United States citizen by naturalization Educational Qualifications B.E. (Elec), Osmania University, India, 1956 M.E.
(Power),
University of Roorkee, India, 1958 M.S.
Nuclear Engineering, Purdue University, 1960 Ph.D. Nuclear Engineering, Iowa State University, 1964 Completed 11 credit hours of laboratory work towards my degree while at Purdue University and at Iowa State University, including six hours of reactor work with UIR-10.
Practical Experience Assistant Professor in Engineering Physics at the University of Tulsa, Oklahoma, 1964-1968, where among other duties my responsibilities included organizing and conducting nuclear radiation laboratory classes.
Assistant Professor in Nuclear Science and Engineering at Idaho State University, 1968/72; Student trainee in Electrical Engineering division of Government of Andhra Pradesh, India, 1956 (March to December).
Involved with the operational aspects of thermal and hydro-power systems.
Instructor, Special Summer Institutes at Iowa State University (sponsored jointly by ASEE-AEC) in 1961 and 1962.
Assistant in the nuclear radiation laboratories.
Research Assistant, Iowa State University, Engineering Experiment Station.
Research Physicist, Cities Service Research and Development Co., Tulsa Oklahoma in summer 1965 and 1968, where I worked on " Computer Simulated Activation Analysis System" and
" Prediction of Radioactivity Levels in Gas from Project Gasbuggy."
Research Scientist at Argonne National Laboratories, Reactor 4
Physics Division at Idaho, summer 1969 Worked on Monte Carlo program to predict neutron flux in Fast Reactors.
. (cont.)
NEILL, Dewitt T.,
Professor of Engineering EDUCATIONAL QUALIFICATIONS B.S.
Chemical Engineering, University of Oklahoma,1956
. Chemical Engineering, U iversity of Oklahoma,1957 M.S.
n Ph.D. Chemical Engineering, University of Oklahoma,1968 Formal course work in Fundamentals of Nuclear Engineering at University of Oklahoma and National Reactor Testing Station.
Professional Experience Experimental Project Engineer, National Reactor Testing Station, radioisotope handling, monitoring, contamination and cleanup problems associated with large ( >10 Ci.)
sources.
Teaches courses on radiation transport, shielding and effects at both graduate and undergraduate levels at Idaho
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State University.
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a; P. i ENCLOSURE ig S;URCE DOSE RATE CAI.CUIATION lff 4
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The,Pu-Be source mentioned in this application ensnits 1.7 x 10.
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neutrons /second with an average neutron energy of 4.5 MeV.
The r,f Federal Register, Title 10, Part 20, page 64 states that a flux f
r2 Fa value of 2.66 x 10 neutrons /cm.2 7
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-7 D. R. - 6.11 x 10 Rem /sec. >
D. R. - 2,20 iurun/lious G 3 feet.
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I Enclosura 5 udlum MODEL 3001 AREA MONITOR The Model 300/ Area Monitor utilizes an automatically reset binary train to store the count rate infor-mation, providing the capability of high alarm speed with good statistical stability. A choice of one of three different GM detectors can give a range of up to 200 R/Hr. Foolproof operation is insured by the use of stand-by rechargeable D size batteries, allowing continuous operation even during power failure. A green light monitor, driven by normal back-ground gamma or a small source, proves the unit to be in counting operation. The green light will go off only if the unit has failed, radiation below set point, or if the Red alarm is on. The unit is also provided with a continuous operating, three de-cade log meter.
SPECIFICATIONS CONTROLS Alarm Range Standard unit supplied with on LND 712 CONTROLS THAT ARE ACCESSIBLE FROM FRONT OF
/
with alarm range from 0.03 to 300 MR/Hr.
INSTRUMENT BY REMOVING COVER PLATE For on alarm range of 0.8 to 2000 MR/Hr, spect.
Time Bose A four position top switch and trimmer fy and LND 714 GM Tube.
pctentiometer to select reset time base.
For on clarm range of 2 MR/Hr to 200 R/Hr, specify and LND 716 GM Tube.
Pulse: Eight position top switch to select number of Resolution: 100 microseconds with the 712, 20 micro, pulses to alarm.
seconds with the 714 and 716.
Power: Three position switch to select "off" "on" and " charge". Charge position is to be used for Pulse Rote: GM 712 - 23 pulses /second/MR/Hr.
fast charging of botteries. Trickle charge is pro-GM' 714 - 2 pulses /second/MR/Hr.
vided in "on" position.
GM 716 - 0.3 pulses /second/MR/Hr.
hnitor: A potentiometer to set trigger point for the Roset Time Base: Adiustable from 0.6 milliseconds to green light monitor.
6 seconds.
Calibration: A potentiometer to calibrate log meter.
Number Of Pulses to Alarm Set at 5,10, 20, 50,100, 200, 500, or 900.
CONTROLS NOT UNDER COVER PLATE Detector Voltage: Adiustable from 200 to 1200 volts.
Reset: Push button to reset alarm and meter.
Normal operation at 500 volts.
Discrimination: 40 Millivolts.
CONTROLS ACCES$lBLE BY REMOVING CHA5515 Local Alarm Indicator: A Sonalert audio and a flash.
PROM CABINET Ing red light.
H. V.:
Potentiometer to odiust High Voltage from 200 Power: 115 v - 60 CPS line power. Pilot light Indicates to 1200 volts.
line power operation.
Stand By: Four each internal rechargeable NiCd "D" EXTERNAL CONNECTIONS cells for more thanJ00 hours operation without line power - in a non-olarm state.
Eternal connections are provided for remote alcrm and i
remote aform deactivation.
Detector Connector: Series "C" quick disconnect.
Meter: A 4 inch log meter covering three decades with PRICE Model 300/ Area Mom.for 0.02 to 20 MR/Hr presentation standard.
Size:
10 wide by 8" tall by 8" deep.
Complete with stand-by batteries, one detector, and Weight: 12 pounds with batteries.
power cord.
Mounting: Bench top or shelf.
$575.00 FOB Sweetwater, Texas Finish: Brown epoxy point on steel cabinet, clear on-Spore detector assemblies $75.00 each. Specify detector edized panel. Silk screened nomenclature.
number with order.
LUDLUM MODEL 300S/ NEUTRON SCINTILLATION AREA MONITOR Specifications are essentially the same as the standard Model 300/ Area Monitor with the exception that the Meter Dial will read out per customer's specification.
PRICE: Model 3005/ Neutron Scintillation Area Monitor base price $500.00. Select Detector Model 421 Thermal Scintillation Neutron Doctor -_____________eo. $250.00 l
Model 42 2 Fast Neutron Scintillation Detector __________ ______eo. $250.00 Model 42 4 Neutron Detector with 10" sphere of polyethylene ____ eo. $525.00 g
Specifications for the Neutron Scintillators will be found in the Ludlum general catalogue.
LUDLUM MODEL 300P/ PROPORTIONAL NEUTRON AREA MONITOR Specifications are essentially the same as the standard Model 300/ Area Monitor with the following exceptions:
High Voltage Adjustable from 400 to 2400 volts.
Discrimination: Adjustable from 2 to 60 millivolts.
Meter Presentationi To read out in customer preference.
PRICE: Model 300P/ Proportional Neutron Area Monitor base unit price - $650.00.
Detector: A one Inch thick paraffin moderated BF.3 Detector as described with the Model 15 in the general catalogue - ea. $300.00.
Other types of proportional neutron detectors evollable upon request.
LUDLUM MEASUREMENTS, INC.
g SWEETWATER, TEXAS 79556 501 Oak Street - P. O. Dor 248 (915) 235-5494
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