ML20138Q240
| ML20138Q240 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/1978 |
| From: | Constable G, Herwig N, Sniezek J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20138Q140 | List: |
| References | |
| FOIA-85-481 PROC-780831, NUDOCS 8511180043 | |
| Download: ML20138Q240 (222) | |
Text
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RESEARCH REACTORS A Reference and Training Text Prepared by: Nancy Herwig Reviewed by: G. L. Constable Approved by: J. H. Sniezek DROI, IE AUGUST 1978 I
INTRODUCTION This publication was developed for use in an introductory training course and as a preliminary guide to the research reactors that are regulated by the NRC. Some of the data may be outdated, and therefore this manual should not be considered as a primary reference. It can, however, enable an individual to gain a basic awareness of and to become familiar with a specified research reactor. It is hoped that this manual will succeed in presenting a general, and individual, perspective of these research reactors. This information is the best available data as of August 1978. Any questions or connents concerning this manual are welcome and shou.ld be referred to the Assistant Director For Field Coordination, Division of Reactor Operations Inspection, Office of Inspection and Enforcement.
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l-1 Table of Contents r fage, I. Introduction iii II. Table of Contents v III. Research Reactors 1 A. Solid homogeneous core reactors 1
- 1. AGN-201 3
- 2. AGN-211 11 .
- 8. Critical experiment facilities 17
\ C. Liquid homogeneous core reactors 21
- 1. L-77 23 ,
- 2. L-85 31 D. Heterogeneous core reactors - Argonaut 33 E. Tank type reactors 47 l
- 1. light water moderated 47
- 2. heavy water moderated 55
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P_ age F. Pool type reactors 67 G. TRIGA reactors 105
- 1. TRIGA Conversions 109
- 2. MARK I 119
- 3. MARK II 149 4.' MARK III 163
- 5. MARK F 169
- 6. Advanced 175 III. Reactor Terms 183 IV. Reactor Addresses and Principal Contacts 191 V. Index , 207 O
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Individual Reactor Listing Pajyt A. Solid homogeneous core reactors 1 AGN-201 Univ. of Delaware Oregon State Univ. Calif. State Polytechnic College Catholic Univ. Texas A&M Univ. Univ. of Utah Georgia Institute of Technology Idaho State Univ. Tuskegee Institute Univ. of New Mexico AGN-211 Univ of Oklahoma B. Critical experiment facilities 17 Babcock & Wilcox Co. Rensselaer Polytechnic Institute
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I Page C. Liquid homogeneous core reactors 21-L-77 Rockwell International Corp.
- Univ..of California j .Brigham Young Univ.
L-85 i i j Rockwell International Corp. . .i . D. Heterogeneous core reactors - Argonaut 33 i Argonaut i Univ. of California Univ. of Florida j Univ. of Washington UTR-10 Virginia Polytechnic Institute and State Univ. ; Iowa State Univ. -,, 1 -viii-r,,.mn. --,e _ , - , - , - , , . , .,,m.-g,g.-y:,- -,w-,,,,,.-. . , - .~n.-w.-w,w,nn,
n Page E. Tank reactors 47 Light water moderated Cornell Univ. Westinghouse Electric Corp. General Electric Co. (NTR) General Electric Co. (GETR-Test Reactor) Heavy water moderated Georgia Institute of Technology Mass. Institute of Technology National Bureau of Standards (Test reactor) F. Pool reactors 67 Manhatten College Univ. of Virginia (CAVALIER) Worcester Polytechnic Institute Univ. of Missouri (MURR) Purdue Univ. Ohio State Univ. Univ, of Missouri Univ. of Kansas Univ. of Lowell
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3 ' Univ. of Wisconsin ,. ( MARK I I ,, , t V. A. Hospital Dow Chemical Co. .'
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Univ. of Utah Reed College Univ. of California - Irvine Univ. of Texas Univ. of Arizona General Atomic Co. U. S. Geological Survey _ MARK II Cornell Univ. Columbia Univ. Kansas State Univ. Michigan State Univ.
. Oregon State Univ.
MARK III Pennsylvania State Univ. (Conversion) Univ. of California - Berkeley MARK F Armed Forces Radiobiology Research Institute ( AFFRI) Northrop Corp. General Atomic Co. ADVANCED TRIGA Univ. of Illinois
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k. AGN-201 SOLID HOMOGENE0US REACTOR The AGN 201 reactor is a compact, portable, self-contained reactor designed to operate at very low power levels. The ten inch diameter core consists of U 235 embedded in a polyethylene moderator. A graphite, lead and water shield surrounds the core. The AGN 211 reactor also uses polyethylene to contain the fuel. The' core is .in-a vertical water tank surrounded by a concrete shield. O
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Solid homogeneous core research reactor Fuel: UO 2 alloy dispersed in Polyethylene enrichment 20% clad none critical mass = 656 grams core loading ~ 665 grams max. excess ak reactivity 0.5% k description 10" diameter Polyethylene discs > 2 Max Neutron 5 x 106 n/cm -sec (.1 watt) Flux: 2 2.5 x 108 n/cm -sec (5 watt) Controls Rods: 2 safety 'uel rods comp )sition UO2 in Polyethylene individual worth 1.25% ^k 2 control rods composition U02 in Polyethylene coarse control ak rod worth 1.25% k fine control ak rod worth 0.15% k Moderator: Polyethylene Coolant: None Reflector: Graphite Shield: Lead and H 2O l . j \ 1 L.
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E The following reactors are essentially identical to the Aerojet-General Nucleonics Reactor. Name: Univ. of Delaware (AGN-201) Location: Newark, Delaware Docket Number: 50-98 License Number: R-43 Date of Initial Criticality: 1958 Number of Operators: SRO-1, R0-0 Name: Oregon State Univ. (AGN-201) Location: Corvallis, Oregon Docket Number 50-106 License Number: R-51 Date of Initial Criticality: 1959 - Number of Operators: SRO-2, R0-2 Name: Calif. State Polytechnic College (AGN-201) Location: San Luis Obispo, Calif. . Docket Number: 50-394 License Number: R-121 Date of Initial Criticality: 1957 Utilization: Operated for approximately 5 hours in 1976 Note: Formerly US Naval Post Graduate school reactor transferred to CSPC in 1973 5-
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Name: Catholic University ( AGN-201 ) Location: Washington, D.C. Docket Number: 50-77 License Number: R-31 Date of Initial Criticality: 1957 Number of Operators:- SR0 - 1, R0 - 0 Name: Texas A & M (AGN-201 M) Location: College Station, Texas Docket Number: 50-59 License Number: R-23. Rated Power: 5 watts Increased rated power in 1972 Date of Initial Criticality: 1957 Number of Operators: SRO-3, R0-0 Utilization: Reactor operated approximately 100 hours between 6/77 and 6/78 Startups - 124 Name: Univ. of Utah (AGN-201M) Location: Salt Lake City, Utah Docket Number: 50-72 Rated Power: 5 watts Increased rated power in 1975 Date of Initial Criticality: 1959 Number of Operators: SRO-2, R0-3 O l o lat ! !
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Name: Georgia Institute of Technology (AGN-201) 9 Location: Atlanta, Georgia , Docket Nu'mber: 50-276 License Number: R-111 Date of Initial Criticality: 1968 Number of Operators: SRO-2, R0-4 Name: Idaho State University (AGN-201) Location: Pocatello, Idaho Docket Number: 50-284 License Number: R-110 Date of Initial Criticali,ty: 1967 Name: Tuskegee Institute (AGN-201) Location: Tuskegee, Alabama Docket Number: 50-406 License Number: R-122
- Date of Initial Criticality: 1974 Number of Operators: SRO-1, R0-0*
Name: University of New Mexico (AGN-201M) location: Albuquerque, New Mexico Docket Number: 50-252 License Number: R-102 Rated Power: 5 watts Increased rated power from .1 watt to 5 watts in 1969 Date of Initial Criticality: 1966 Number of Operators: SRO-3, R0-2 . Utilization: Operated approximately 240 hours per year
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r Name: University of Oklahoma Reactor (AGN-211) Location: Norman, Oklahoma Docket Number: 50-112 License Number: R-53 Date of Initial Criticality: 1959 Rated Power: 15 watts
Description:
Solid homogeneous core research reactor Fuel: U0 2 enrichment 20% clad plastic liner , critical mass 780 grams core loading 785 grams max. excess ak reactivity 0.52% k l description fuel rods - polyethylene and graphite Max. Neutron Flux: 3 x 10 9 "Icm2 -sec Control Rods (4): 2 safety rods
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. individual worth 1.1% ^k 1 regulating rod I composition stainless steel worth 0.36%
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i Moderator: polyethylene Coolant: Light water (H20) Reflector: Graphite Shield: Concrete, lead and H O 2 Number of Operators: SRO-2, R0-1 4 0
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l Name: Babcock and Wilcox Critical Facility Location: Lynchburg, Va. Docket Number: 50-13 ! License Number: CX-10 ! Date of Initial Criticality: 1958 l Rated Power: 1 kw l
Description:
Tank-type, light water' moderated critical l reactor l Fuel: UO pellets or UO2 - Th02 pellets 2
' enrichment 2.5% or 93%
clad Aluminum max. excess ak
. reactivity <2% k Control Rods (4): 3 safety blades composition Boron or Cadmium ,
clad stainless steel i total worth 5.1% ^k I ragulating rod same composition and clad worth 0.9% a k k Moderator: Mixed moderator in supplemental core tank of D 20 and H 2O Coolant: 302 Reflector: Graphite and 0 0-H 0 2 2 Shield: Concrete Number of Operators: SRO-4, R0-0
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Name: Rensselaer Polytechnic Institute Critical
. Experiments Facility Location: Schnectady, New York Docket Number: 50-225 License Number: CX-22 Date of Initial Criticality: 1958 (under ALC0 Products, transferred to RPI in1964)
Rated Power: 100 watts
Description:
CX-type, light water moderated, critical facility Fuel: UO 2 enrichment 93% clad stainless steel cermet core loading 6011 grams max. excess ak reactivity 3.9% k description standard 38 assemblies with 18 fuel plates per assembly Control Rods (7); 7 fuel follower control rods composition Boron, stainless steel Moderator: Light water (H 2O) Coolant: HO 2 Reflector: Stainless steel and H 2O
~' Shield: Concrete Number of Operators: SRO-5, R0-1 l
LIQUID HOMOGENEOUS CORE REACTORS P' 7-0 S' 9
LIQUID HOMOGENE0US REACTOR (L-77--L-85) The liquid homogeneous core reactor utilizes enriched U 235 which is evenly dispersed in a water solution of uranyl sulfate. This reactor is often referred to as a " water boiler" because during operation there is an evolution of hydrogen and oxygen gases, through the slow decomposition of the water, which causas a bubbling similar to that of boiling. A , gas recombiner is provided to prevent the formation of an explosive mixture of the gases. The reactor consists of a one foot diameter stainless steel sphere containing the aqueous solution. The core is surrounded by a graphite, water or lead reflector and a lead and water shield. SAFETY. CONTROL THIMBLE (2) GAS LINE x/ 4 - f FILL AND DRAIN LINE SECOND SHIELD c RECOMBINEH THIRD SHIELD. p CANOPY 3 g y$ ......... DU T/ h ' j=y= G = HOLDUP ASSEMBLY g :i:!l : v M 4 ::... ... I s a 'T N f R CENTRAL g , . -
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c t Name: L-77 Owner: Rockwell International Location: Canoga Park, California Docket Number: 50-94 License Number: R-40 Date of Initial Criticality: 1958 Rated Power: 10 watts
Description:
Liquid, homogeneous core research reactor Core: 15 3/4" diameter stainless steel spherical core gas recombiner Fuel: Uranyl Sulfate (U02504 ) enrichment 20% 90%
- critical mass 1.396 kg 1.152 kg core loading 1.405 kg 1.173 kg max. excess Ak reactivity 0.5% k Temp. coefficient
- 0.02%/*c Max. Neutron Flux: 1 x 108 n/c,2-sec ControlsRods(2): 1 safety rod I regulating rod composition stainless steel and cadmuim clad Aluminum individual ak worth 1.3% k
Moderatdr: HO 2 Reflector: - Lead and diphenyl Number of Operators: SRO-3, R0-0 Utilization: Operated 62. times, generating 103 watt-hours - of energy in 1973. 6 4 4 4 J
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a The following reactors are identical to the Rockwell International L-77 reactor: Name: University of California Santa Barbara L-77 Reactor Location: Santa Barbara, California Docket Number: 50-433 License Number : R-124 Date of Initial Criticality: 1975 transferred from Univ. if flevada Number of Operators: SRO-1, RO Utilization: Operated approximately 13 hours in 19) i flame: Brigham Young University location: Provo, Utah Docket Number: 50-262 License Number: R-109 Date of Initial Criticality: 1967 Number of Operators: SRO-2, R0-0 Utilization: Operated 19 times for approximately 15 hours in 1976 O
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Name: L-85 Owner: Rockwell International Corp. Location: Santa Susanna, California Docket Number: 50-375 License Number: R-118 Date of Initial Criticality: 1972 Rated Power: 3 kw
== Description:== Homogeneous liquid core Core: I foot diameter stainless steel core Fuel: Uranyl Sulfate (U02504 ) Dissolved in .3 .4 molar sulfuric acid en.richment 90% core loading 800 grams max. excess ak reactivity 0.8% k Max. Neutron 2 Flux: 4 x 1010 n/cm -sec Control. Rods (4): 2 safety rods composition Cadmium and Cadmium-Silver total worth 2.3% ^k 2 control rods composition Cd and Cd-Ag coarse control ak rod worth 1.3% k -
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fine control ak rod worth 0.4% k Moderator: Heavy water (D 0) 2 Coolant: D0 2 Max. Coolant Temp.: 160 F Reflector: Graphite Shield: -Concrete Utilization: Operated approximately_30 hours in 1977 l 9
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. Argonaut i-An Argonaut is a water and graphite mderate'd thermal heterogeneous j reactor. The core lattice consists of a five foot cube of graphite j containing NTR type fuel elements locaud in aluminum tanks containing water. An internal graphite reflector contains access holes for experimental purposes. The reactor is shielded by concrete and has l an integral water tank and graphite thermal column for use in a variety of experiments. 4 s G 4 1 4 I f i (
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s Name: UCLA Training Reactor Location: Los Angeles, California Docket Number: 50-142 License Number: R-71 Date of Initial Criticality: 1960 Rated Power: 100 kw Rated power increased from 10 kw to 100 kw in 1963
Description:
Argonaut type, heterogeneous core research reactor Fuel: U-Al alloy enrichment 90% clad Aluminum critical mass 3.2 kg max, excess ak reactivity 2.3% k description 24 elements, 11 MTR type plates per element Max. Neutron Flux: 1 x 10" "I cm2 -sec Control Rods (4): Composition Cadmium clad Magnesium Swinging vane type 3 safety rods Total worth 4.5% ^k 1 regulating rod A worth 0.6% k i l l j
Moderator: H2 O and graphite Coolant: HO 2 Max Coolant U Temp.: 110 F Reflector: Graphite Shield: Concrete Number of Operators: SRO-4, R0-2 Utilization: Generated approximately 13 MW-hrs of ene '2v in 1976 l s Name: ~ University of Florida Trainino Reactor Location: Gainesville, Florida Docket flumber: 50-83 ~ License Number: R-56 -Date of Initial Criticality: 1956 Rated Power: 100 kw
Description:
Argonaut type, light water moderated research reactor Fuel: U-Al enrichment 20% 93% clad Aluminum critical mass 3.5 kg 3.1 kg core loading 3.6 kg. 33 kg max. excess aK ak reactivity 0.6% k 2.3% k description 11 rectangular parallel plates per fuel bundle Max. Neutron Flux: 1.8 x 10 12 n/cm2 -sec enrichment 20%
- 93%
Control Rods (4): 3 shim safety blades total worth 4.24% 4.11% 1 regulating blade worth 0.78% 1.02% composition Cadmium clad Magnesium Moderator: Light water (H 2O) Coolant: HO 2
- Licensee does not currently possess 20% enriched fuel.
l l l 1 Reflector: Graphite Shield: Concrete Number of Operators: SRO-6, R0-2
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1 Name: University of Washington Nuclear Reactor (UWNR) Location: Seattle, Washington Docket Number: 50-139
. License' Number: R-73 02te of Initial Criticality: 1961 Rated Power: 100 kw Increased rated power from 10 kw to 100 kw in 1966.
Description:
Heterogeneous, Argonaut-type research reactor. Core: Rectangular prism of graphite Fuel: U-Al enrichment .90% clad Aluminum core loading 3.7 kg max, excess Ak reactivity 2.3% k description MTR-type plates 24 denents,11 plates per element Max. Neutron 2 Flux: 1 x 10" "/cm -sec Control Rods (4): 3 safety blades composition Cadmium clad Magnesium individual worth 1.5% ^k i regulating rod similar composition and clad worth 0.6% ^k (- . Moderator: H2 O and graphite Coolant: HO2 0 Max. Coolant. Temp.: 160 F 4 Reflector: Graphite i Shield: Concrete Number of Operators: SRO-3, R0-1 Utilization: Operated 107 times for approximately 180 hours in 1977 i' 7 I I. o ; J i
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l Name: University Training Reactor (UTR-10) Owner: Va. Polytechnic Institute and State University Location: Blacksburg, Virginia Docket Number: 50-124 License Number: R-62 Principle Contractor: American Radiator and Standard Sanitary Corp. Date of Initial Criticality: 1960 Rated Power: 100 kw Increased power from 10 kw to 100 kw in 1965
Description:
Argonaut type Fuel: U-A1 4 enrichment 93% clad Aluminum critical mass 3 kg. core loading 3.4 kg. max. excess ak reactivity allowed 0.6% k presently 0.3% of Max. Neutron Flux: 1 X 10 I4 "I cm2 -sec Control Rods (4): 3 safety rods windowshade type composition Cadmium total worth 0.8% ak
.o
p 1 regulating rod , composition Cadmium worth ak 0.2% k Moderator: Light water (H 2O) Coolant: HO 2 Max. Coolant Temp.: 170* F Reflector: Graphite U . eld: Concrete Number of Operators: SRO-5, R0-4 Utilization: Generated approximately 113,387 kw-brs of energy in 1976. 235 start ups 44
Name: Iowa State University Reactor Location: Ames, Iowa Docket Number: 50-116 License Number: R-59 Date of Initial Criticality: 1959 Rated Power: 10 kw
Description:
Argonaut type, light water moderated research reactor Similar to UTR reactor at VPISU except: Max. Neutron Flux: 1.25 x 10" "/cm2-sec Control Rods (4): 3 shim safety rods composition Cadmium individual Ak worth 1.86% k 1 regulating rod composition Cadmium Ak worth 0.12% k Operators: SRO-3, R0-2
O O TANK REACTORS S Os 3 W 1 e - - - - - -
Name: Cornell Zero Power Reactor (ZPR) , Location: Ithaca, New York Docket Number: 50-97 License Number: R-89 F Inciple Contractor: Vitro Engineering Co. I Date of Initial Criticali ty: 1963 Rated Power: 100 watts
Description:
Low power, light water moderated tank type research reactor Fuel: UO2 pellets enrichment 2.1% clad Aluminum max. excess ak reactivity 2.8% k description 228 fuel roads (0.6" diameter, 48" length) Max. Neutron Flux: 1.45 x 109 "/cm2-sec Control Rods (4): 4 control rods each a cluster of three cylinders composition Boron-carbide clad Aluminum O total worth 6% k Moderator: Light water (H 2O) Coolant: HO 2 i
9 i f r i Reflector: HO 2 1 Shield: Concrete 1 Number of Operators: SRO-2, R0-0 i Note: The ZPR is located in the same pool as the J Cornell TRIGA reactor therefore neutron i coupling occurs. i r I. l L f 4 h P A t l l . i .i l
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Name: Westinghouse Nuclear Training Reactor (NTR) Location: Zion, Illinois Transferred from Waltz Mill, Penn. in 1972 Docket Number: 50-87 License Number: R-il9 Date of Initial Criticali ty: 1972 Rated Power: 10 kw Fuel: U-Al x enrichment 93% clad Aluminum core loading 7.4 kg max. excess ak . reactivity 4.1% k description 28 elements, 3 tubes per element Control Rods: 9 fuel follower control rods composition Cadmium clad stainless steel A total worth 9.4% k Moderator: HO 2 Coolant: H0 2 Reflector: HO 2 Shield: Concrete and H.02 Number of Operators: SRO-12, R0-0 Utilization: Operated approximately 2000 hours in 1977.
Name: General Electric Nuclear Test Reactor (NTR) Location: Alameda County, California Docket Number: 50-73 License Nunber R-33 Date of Initial Criticality: 1957 Rated Power: 100 kw Increased rated power from 30 kw to 100 kw in 1969
Description:
Light water moderated research reactor Fuel: U-Al alloy enrichment 93% clad Aluminum
, critical mass 3 kg.
core loading 3.7 kg. max, excess ak reactivity 0.75% k description 16 fuel assemblies, 40 disks per assembly Max, Neutron Flux: 2.5 X 1012 n/cm2 -sec Control Rods (11): 6 poison sheets composition Cadmium-Aluminum 0 individual worth 1% 4 safety rods composition Baron carbide powder clad Cadmium steel ak individual worth 0.5% k t 1 fine control rod ak worth 0.12% k Moderator: Graphite Coolant: HO 2 Max. Coolant Temp.: 126' F Reflector: Graphite Shield: Concrete Number of Operators: SRO-5, R0-1 Utilization: Operated approximately 1820 hours in 1977 with 359 reactor start-ups.
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Name: General Electric Test Reactor (GETR) Location: Alameda C.ounty, California Docket Number: 50-70 License Number: TR-1 Date of Initial Criticality: 1959 Rated Power: 50 Mw increase in power in 1966
Description:
low pressure, low temperature tank test reactor located in a pool. Fuel: U-Al alloy, enrichment 93% or U-A1x alloy, enrichment 89% clad Aluminum core loading 10.7 kg max. excess A reactivity 11.5% k description standard 21 elements,19 fuel plates per element Max. Neutron Flux: 1.6 x 10 I4 n/cm2 -sec Control Rods (6): 6 fuel follower control rods l composition Boron, steel l total worth 17.5% Ak k This system contains a liquid emergency shutdown system. Moderator: light water (H 20) Coolant: HO2 0 Max. Coolant Temp.: 135 F Shield: Concrete Number of Operators: SRO - 20 R0 - 10
1 EXTENSION ROD PERFORATED CASING I 6%" lI3 P i, t> \ 9%" CONNECTING ROD o POISON SECTION # ^
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Name: Georgia Tech Research Reactor (GTRR) Location: Atlanta, Georgia Docket Number: 50-160 License Number: R-97 Date of Initial Criticality: 1964 Rated Power: 5 Mw Increased rated power to 5 Mw in 1974
Description:
Tank-type, heavy water moderated research reactor Fuel: U-Al enrichment 93% clad Aluminum max. excess reactivity 11.9% ^k description 19 fuel assemblies, 16 plates per assembly triangle array Max. Neutron Flux: 1.5 x 10I4 "/cm2-sec Control Rods (5): 4 shim safety blades hollow blades composition Cadmium filled with Helium
. clad Aluminum individual worth 4% ^k 1 regulating rod same composition and clad worth 4% ^k 1
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Concrete-t- !: Niinber of Operators: SRO-4, R0-6 q k- Utilization: Operated approximately 420 hours between I. , 6/76 and 6/77 / L L s k s . 5 4A
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1 l l l Name: Mass. Institute of Technology Reactor (MITR) Location: Cambridge, Mass. Docket Number: 50-20 License Number: R-37 Principle Contractor: ACF Industries Date of Initial Criticality: 1958 Rated Power: 5 Mw
== Description:== Tank-type, heavy water reflected reactor Fuel: U-A1 x enrichment 93% clad Aluminum core loading 11.6 kg max. excess ak reactivity 1.8% k description Rhomboidal fuel elements, hexagonal distribution Max. Neutron Flux: 1 x 10 I4 "I cm2 -sec Control Rods: 6 flat plates composition stainless steel with 1% boron total worth 12.6% a k Moderator: HO2 Coolant: Light water (H20) Absorbers: Hafnium 61 -
Reflector: Heavy water (D2 0) and graphite Shield: Concrete
- Number of Operators: SRO-11, R0-5 Utilization: Operated approximately 4500 hours in 1977
. Note: Major change in the core in 1976. Light water relaced heavy water as the coolant
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MITR HORIZONTAL SECTION Name: -National Bureau of Standards Reactor (NBSR) Location: Gaithersburg, Maryland Docket Number: 50-184 License Number: TR-5 Principle Contractor: Burns and Roe, Inc. _Date of. Initial Criticality: 1967 Rated Power: 10 Mw
Description:
Tank-type heavy water moderated test reactor Fuel: U-Al enrichment 93% clad Aluminum core loading 6 kg max. excess ak reactivity 10% k description 24 fuel elements, 17 plates per element MTR-type curved plates, hexagonal distribution Max. Neutron Flux: 1 x 10 I4 "I cm2 -sec Control Rods (5): 4 shim safety blades semaphore type - composition Cadmium clad Aluminum total worth 32% ^k - F-1 regulating rod composition Aluminum worth 0.5% Ak k Moderation: Heavy water (D 0) 2
. Coolant: z 00 2
Reflector: D0 2
' Shield: Lead, iron and concrete Max. Coolant Temp.: 50 C Number of Operators: SRO-16, R0-1 Utilization: Operated approximately 6100 hours in 1977 1
V' y O Os e POOL REACTORS
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Name: Manhattan College Zero Power Reactor (ZPR) Location: Riverdale, New York Docket Number: 50-199 License Number: R-94 Principle Contractor: AMF Atomics Date of Initial Criticality: 1964 Rated Power: .1 watt
Description:
Low Power, pool-type reactor Fuel: U-Al alloy enrichment 90% clad Aluminum critical mass 3.25 kg. core loading 3.74 kg. ] max. excess reactivity 0.44% ^ description 16 fuel elements, 18 MTR-type plates per element Max. Neutron 9 Flux: 1.26 X 10 "/cm2-sec Control Rods (2): Two Y-shaped control rods 1 safety rod composition cadium and stainless steel
^
~
worth 3.4% l regulating rod composition stainless steel worth 0.9% ^ Moderator: lightwater(HO) 2 Coolant: HO2 Reflector: graphite Shield: concrete Number of Operators: SRO - 3. RO - 0 . 1 Name: Cooperatively Assembled Virginia Low-Intensity taucational Reactor (CAVALIERJ Location: Charlottesville, Virginia l Docket Number: 50-396 License Number: R-123 Date of Initial Criticality: 1974 Rated Power: 100 watts
Description:
Low power, pool-type training facility. Two types of reflectors are possible, graphite or light water. Fuel: U-Al alloy , enrichment 93% clad Aluminum max. excess reactivity 1.6% g k description flat plate, curved MTR elements 12 plates per element light water (H20) Graphite core loading 2.31 kg. 2.97 kg, elements in core 16 12 Max. Neutron Flux: 8.5 X 107 n/cm2 -sec 1.1 X 108 n/c ,2, sec ! Control Rods (4): 4 control blades l l bayonet type, oval cross section composition boron stainless steel individual' worth 3% N k
Moderator: Light water (H O) 2 Coolant: HO 2 Reflector: H2 O or graphite Shield: Concrete Number of Operators: SRO-1, R0-4 Utilization: Operated approximately 400 hours in 1977 9 4 I Name: Worcester Polytechnic Institute Reactor Location: Worcester, New York Docket Number: 50-134 License Number: R-61 , Principle Contractor: General Electric Date of Initial Criticality: 1959 Rated Power: 10 kw
Description:
Increased rated power from 1 kw to 10 kw in 1967 Light water moderated open pool reactor
- Fuel: U-A1 alloy enrichment 93%
clad Aluminum critical mass 3.6 kg. core loading 3.7 kg. max. excess ak reactivity 0.5% k description MTR-type plates 27 elements, 10 plates per element Max. Neutron Flux: 9 X 10 9 "I cm2 -sec Control Rods (4): 3 safety blades composi tion Boral
^
individual worth 3.5% 1 regulating rod composition stainless steel 0 worth 0.7% L
1 Moderator: Lightwater(H0) 2 Coolant: HO 2 Max. Coolant Temp.: 130' F
- Reflector: Graphite and H O 2
Shield: Concrete and H O 2 Number of Operators: SRO-3, R0-4 h e e
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Name: Missouri University Research Reactor (MURR) Location: Columbia, Missouri Docket Number: 50-186 License Number: R-103 Principle Contractor: Internuclear of St. Louis Date of Initial Criticality: 1966 Rated Power: 10 h
== Description:== Increase in rated power from Sh to 10 N in 1974 Pool-type, light water moderated research reactor Fuel: U-Al or U-A1x curved plates enrichment 93% clad. Aluminum ' critical mass 4 kg. core loading 6.2 kg. max. excess ak reactivity 9.8% k description 8 fuel assemblies with 24 plates per assembly Max. Nuetron Flux: 1.6 X 1012 n/c ,2 -sec Control Rods (4): 3 safety shim blades composition Baron steel clad Aluminum individual worth 3% ^ 2 I I regulating blade
+
composition stainless steel worth ^ ' 0.7% Moderator: Light water (H O) 2 Coolant: HO 2 Max. Coolant Temp. : 135' F Reflector: Beryllium-Graphite and H O 2 Shield: Concrete and H O 2 Number of Operators: SRO-13, R0-11 Utilization: Operated approximately 5100 hours in 1977 4
}
t
Name: Purdue University Reactor Location: West Lafayette, Indiana Docket Nun 6er: 50-182 License Number: R-87 Principle Contractor: Lockheed Nuclear Products Date of Initial Criticality: 1962 Rated Power: 10 kw ,
== Description:== Pool-type, light water moderated and cooled research reactor Fuel: U-Al enrichment , 93% clad Aluminum core loading 2.44 kg. max, excess reactivity 0.6% of description 13 MTR-type elements,10 plates per element Max. Neutron Flux: 2.1 X 1010 n/cm2-sec Control Rods (3): 2 shim safety rods composition baron stainless steel total worth 5.8% ak 1 regulating rod composition H2 O filled stainless steel tube worth 0.47! ak
\
F Moderator: Light water (H 2O) Coolant: HO 2 Reflector: Graphite waterproofed with a polyester resin Shield: - Concrete,' sand and H O 2 Number of Operators: SRO-2, R0-3 Utilization: Generated approximately 200 Mw-hrs of energy between 6/75 and 6/76 e o G h
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s s i l Name: Ohio State University Reactor Location: Columbus, Ohio Docket Number: 50-150 l License Number: R-75 L l Date of Initial 1 o Cri ticality: 1961 Rated Power: 10 kw
Description:
Light water moderated pool reactor ! Fuel: U-Al alloy enrichment 93% clad Aluminum . ! critical mass 2.84 kg. core loading 3.13 kg. max. excess reactivity Ak 1.88% k description 20 elements. 10 MTR-type plates per element Max. Neutron 2 i Flux: 2.2 X 10 11 "/cm -sec 1 ControlRods(4): 3 shim safety rods composition baron stainless steel total worth 8.6% ak k
- 1 regulating rod composition stainless steel worth 0.6% ^k 79 -
t
1 Moderator: Light water (H20) Coolant: HO 2 Max. Coolant Temp.: 145* F Reflector: Graphite and H O 2 Shield: Concrete and H O 2 Number of Operators: SRO-2, R0-2
Name: University of Missouri Nuclear Reactor Facility Location: Rolla, Missouri Docket Number: 50-123 License Number: R-79 Principle Contractor: Curtiss Wright Corporation Date of Initial Criticality: 1962 Rated Power: 200 kw
Description:
Light water moderated pool type research reactor Fuel: U03 8 - Al enrichment 90% clad Aluminum core loading 2.9 kg. max. excess Ak reactivity 3.3% k description MTR-type fuel elements Max. Neytron Flux: 2.8 X 1012 n/cm2-sec Control Rods (4): 3 shim safety rods composition stainless steel and boron total worth 8.9% 1 regulating rod hollow tube composition stainless steel worth 0.65% O Moderator: HO 2 Coolant: H0 2 Max. Coolant Temp.: 113' F Reflector: Graphite and H O 2 Shield: Concrete and H O 2 Nunber of Operators: S RO-_1 , R0-1 Utilization: Generated approximately 11',800 kw-hrs of energy between 4/77 and 4/78 4 O
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Name: University of Kansas Training Reactor Location: Lawrence, Kansas Docket Number: 50-148 License Number: R-78 Principle Contractor: Bendix Aviation Corp. Date of Initial
' Criticality: . 1961 Rated Power: 250 kw, average level 10 kw Power increased from 10 kw to 250 kw in 1971
Description:
Pool type, light water moderated reactor Fuel: U-Al alloy enrichment 93% clad Aluminum l l critical mass 2.5 kg. core loading 2.8 kg. max. excess ak raactivity 1.5% k de scription 10 MTR-type plates Max. Neutron Flux: 3 X 10Il "/cm 2-sec Control Rods (3): 3 control plates composition Boral clad Aluminum ak individual worth 2% k Moderator: Light water (H20)
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Reflector: Graphite and H2, 0 ' c
' _s-Shield: Concrete .
f Number of Operators: SRO-2, R0-2 Utilization: Generated approximately 2.46 Mw-hrs of energy s ' between 6/75 and 6/76. . y a 4 4 g f
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Name: Lowell Technological Institute Reactor Location: Lowell, Massachusetts Docket Number: 50-223 License Number: R-125 Date of Initial Criticality: 1975
- Rated Power
- 1 Mw
Description:
Light water moderated and cooled pool reactor Fuel: U-Al alloy enrichment 93% clad Aluminum critical mass 2.8 kg. core loading 3.5 kg.
. max. excess ak reactivity 4.5% k description 26 elements, 18 plates per element ' Max. Neutron Flux: 8.6 X 1012 n/c,2,3,e Control Rods (5): 4 safety rods composition Boral l total worth 15.5% h 1 regulating rod ,
composition Boral worth 0.7%^f l Moderator: Light water (H 2O) l l l .
s 7, 3, t Coolant: HO 2 l
. Max. Coolant Temp.: 124' F
', Reflet. tor: Graphite and H O 2
Shield: Concrete,and H O 2 ! Number of. Operators: SRO-5, R0-7 Utilization: Operated approximately 350 hours between 5/75 and 5/76
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I Name: Lynchburg Pool Reactor (LPR) Owner: Babcock and Wilcox Location: Lynchburg, Virginia Docket Number: 50-99 License Number: R-47 Date of Initial Criticality: 1959 Rated Power: 1 Mw increase in rated power in 1962
Description:
light water moderated pool reactor Fuel: U-Al alloy enrichment 93% clad Aluminum core loading 4.1 kg. max. excess ak reactivity 4% k description 18 elements, 10 plates per element Control Rods (4): 3 safety shim rods composition Boron, stainless steel ak individual worth 2.4% 1 regulating rod (hollow) composition stainless steel worth 0.75 k
P Moderator: light water (H 20) Coolant: HO-2 Max.-Coolant Temp.: 120 F ! Reflector: Graphite
- Shield
- Concrete and H20 -
3 Number of Operators: SR0 - 2, R0 - 2 Utilization: Reactor was operated approx. 300 hours in 1974 i 6 O i. J [ l i
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-J Name: Ford Nuclear Reactor Location: University of Michigan Ann Arbor, Michigan Docket Number: 50-2 License Number: R-28 Principle Contractor: Babcock and Wilcox Date of Initial Criticality: 1957 Rated Power: 2 Mw Increased rated power to 2 Mw in 1963
== Description:== Light water moderated, pool type reactor Fuel: U-A1 x enrichment 93% clad Aluminum core loading 4.2 kg. max. excess Ak reactivity 3.5% k description 25 elements, 10 MTR-curved plates per element Max. Neutron Flux: 1.4 X 1013 n/cm2 -sec Control Rods (4): 3 shim safety rods composition Boron, stainless steel individual worth ^ 3% l control rod composition stainless steel ak worth 0.3% k
= . _ _ .- . . ._ . - . - . - - . .. . . .. .- _ . .- . - - . .
4 Moderator: HO 2 Coolant: HO 2 Max. Coolant 0 Temp.: ll6 F Reflector: D 0 and-graphite D 0 reflector is contained in a tank on one side of the pool.
- Shield: ' Concrete and H 2O i Number of Operators: SR0 - 11, R0 - 5
- Utilization
- Generated approx.12,300 Mw-hrs of energy in 1975.
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Name: Rhode Island Open Pool Reactor Owner: Rhode Island Nuclear Science Center Location: Ft. Kearney, Rhode Island Docket Number: 50-193 License Number: R-95 Principle Contractor: General Electric Date of Initial Criticality: 1964
^
Rated Power: 2N increased the rated power from 1 Mw to 2 N in 1970
Description:
pool type research reactor. Fuel: U - Al enrichment 93% clad Aluminum core loading 3.7 kg max. excess 6 reactivity 4.5% description flat plate MTR-type elements 30 elements, 18 plates per element Max.-Neutron 2 Flux: 5.6 x 1012 n/cm -sec
~
Control Rods (5): 4 safety blades composition Boron carbide clad Aluminum Total worth 26% 1 regulating rod square shape composition Stainless steel N, l clad Aluminum ak worth 4% k Moderator: light water (H 2O) Coolant: HO 2 Max. Coolant Temp.: 125 F ~ Reflector: Graphite Shield: Concrete Number of Operators: SR0 - 2, R0 - 4 Utilization: Operated approx. 1300 hours between 6/76 and 7/77 k e t e t p -- o - .s... .- , . - - ,.,,r- , . , . , . , , , - , , - - , , - - , - . - , -
Name: University of Virginia Reactor (UVAR) Location: Charlottesville, Virginia Docket Number: 50-62 License Number: R-66 Date of Initial Criticality: 1960 ~ Rated Power: 2N power increased to 2 % in 1971
Description:
pool type research reactor capable of either graphite or water reflector Fuel: U - Al alloy enrichment 93% clad Aluminum critical mass 2.97 kg (H2 0 reflector) - 2.31 kg (graphite reflector) description 16 MTR type fuel elements, 12 plates per element Max. Neutron Flux: 2.2 x 10 13 n/cm2 -sec (H2 O reflector) 1.7 x 10 13 n/cm2 -sec (gr: shite reflector) Control Rods (4): 3 control rod fuel elements bayonet type composition baron - stainless steel A individual worth 3% k l regulating rod . composition stainless steel worth 0.5% a k
. Moderator: HO 2
Coolant: HO2 0 Max. Codlant Temp.: 110 F 9 Reflector: H2 O or graphite Number of Operators: SR0 - 5, R0 - 14
. Utilization: Operated for approximately 408 hours in 1975~ .
S I l. I - I r. I l 1 I l- J \ i 98 -
kame: Union Carbide Nuclear Company Research Reactor (UCNC) Location: Sterling Forest, New York Docket Number: 50-54 License Number: R-81 Principle Contractor: AMF Atomics Inc. Date of Initial Criticality: 1961 Rated Power: 5 Mw
Description:
Pool type research reactor Fuel: U-A1, U 03 g -Al or U-A1x enrichment 93%
, clad Aluminum cri.tical mass 3.8 kg.
core loading 5.5 kg. max. excess reactivity 10.2% description curved MTR fuel plates standard 21 fuel elements Max. Neutron 2 Flux: 3.1 X 1013 n/cm -sec Control Rods (6): 5 safety rods ___ thin plates similar to fuel elements composition Ag-In-Cd total worth 16.4%
.. I regulating rod composition Ag-In-Cd worth 0.6%
Moderator: Light water (H20)
' Coolant: HO 2
Max. Coolant Temp.: 116' F Reflector: Graphite and H O 2
. Shield: Lead, concrete and H O 2
Number of Operators: SRO-7, R0-12 Utilization: Operated approximately 6600 hours in 1977 s
- 100 -
Name: State University of New York PULSTAR Reactor Location: Buffalo, New York Docket Number: 50-57 License Number: R-77 Principle Contractor: AMF Atomics Date of Initial Criticality: 1964 Rated Power: 2 Mw steady state 3000 Mw peak pulse
Description:
Pulsing research reactor Fuel : UO 2 enrichment 6% clad
- zircaloy critical mass 26.65 kg.
core loading 30 kg. max. excess ak reactivity allowed 9.3% k presently 5.55% ak k description 25 fuel pins Max. Neutron 2 Flux: 8 X 1012 n/cm -sec Control Rods (5): 4 shim safety rods rectangular shape composition Ag-In-Cd
^
individual worth 3% , - 101 -
1 regulating rod composition Ag-In-Cd worth 0.6% k Moderator: Light water (H O) 2 Coolant: HO 2 Reflector: HO 2 Shield: Concrete Number of' Operators: SRO-4, R0-12 Utilization: Operated approximately 4200 hours in 1977 i e I 2
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Name: PULSTAR Owner: North Carolina State University location: Raleigh, North Carolina Docket Number: 50-297 License Number: R-120 Date of Initial Criticality: 1972 Rated Power: 1 Mw steady state 2200 Mw peak power
Description:
Pool type, light water moderated, pulsing research reactor Fuel: U-0 2 pellets enrichment 4% clad zircaloy core loading 12.6 kg. max. excess ak reactivity 1.035% k description 25 elements, 25 pins per element Max. Neutron Flux: 6.42 X 10I4 "/cm2-sec . Control Rods (4): 3 shim safety rods rectangular shape composition Ag-In-Cd total worth 7.14% a k k
- 103 -
1 pulse rod composition Ag-In-Cd worth ak 1.72% k Moderator: Light water (H 20) 4 Coolant: HO 2 Max. Coolant Temp.: 120 F Reflector: HO 2 Shield: Concrete Number of Operators: SRO-2, R0-2 Utilization: Operated approximately 1600 hours in 1977 104 - 1 a
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9 O TRIGA REACTORS
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A deff ling feature of the TRIGA reactors is their inherent safety, which results from the large prompt negative temperature coefficient of reactivity of its fuel moderator system. A sudden large increase of reactivity results in an instantaneous increase of the reactor power level to several thousand times the steady 4 state power level. The temperature of the fuel rises with the power level, and as a result of the negative temperature coefficient, the power level returns immediately and automatically to the normal steady state operating range. This large negative temperature effect is a unique feature of Uranium-Zirconium hydride (U-ZrH) fuel. The primary negative effect ( 90%) is due to the " cell effect" where the neutron scattering, with the bound hydrogen, is temperature dependent. The other 10% is due to doppler broadening.
. With a 2.1% reactivity addition, the resulting power pulse would reach a peak power of approximately 2000 N within 2.8 msec and result in a total energy release of approximately 24 h-sec. The peak fuel temperat.ures in this instance approach 450*C. The maximum allowable temperatures for TRIGA and TRIGA-FLIP fuel are 1000*C and 1150*C respectively.
TRIGA reactors are designed by General Atomic.
-105-
~ Name: University of Illinois Low Power Reactor Assembly (LOPRA) location: Urbana, Illinois Docket Number: 50-356 License Number: R-117 Date of Initial Criticality: 1972 Rated Power: 10 kw Fuel: U-ZrH enrichment 20%
' clad stainless steel core loading = 2.0 kg max. excess reactivity $0.06 max. ?uel temp. 550 C desciiption TRIGA type fuel; three.
types of fuel: standard U ZrH l.7 low hydride U ZrH l.0 Sandia Control Rods (3): 2 safety rods composition cadmium clad aluminum
. total worth $10.00 raison rod same composition and clad worth $1.35
- 107 -
i Moderator: Zirconium hydride and H O 2 Coolant: Light Water (H20) Reflector: Graphite and H O 2 Shield: Concrete and H20 Number of Operators: SR0-1, R0-0 Utilization: Operated approximately 25 hours between 6/76 and 6/77 Note: The LOPRA is located in the bulk shielding tank of the Illinois Advanced TRIGA reactor and there-fore neutron coupling occurs. e e b
/
-108 -
O TRIGA CONVERSION 'R.
f Name: Aerojet-General Nucignics Industrial Reactor (AGNIR) 4 Location: San Ramon, California Docket Number: 50-228 License Number: R-98 Date of Initial Criticality: 1965
- Rated Power: 250 kw steady state i
TRIGA conversion with no pulsing capability De'scription: Pool reactor with TRIGA-type fuel l Fuel : U-ZrH 1.0 enrichment 20% clad Aluminum critical mass 2265 grams core loading 2.3 kg. max. excess ak reactivity 2.25% k description TRIGA-type fuel elements Max. Neutron 2 ! Flux: 6.7 X 1012 n/cm -sec 4 Control Rods (3): composition baron carbide powder i clad Aluminum
^
worth - shim rod 2.6% ak safety rod 2.6% k ak regulating rod 0.75% k Moderator: Zirconium-Hydride and H 2O
-109 -
Coolant' HO 2 Max. Coolant Temp.: 130* F Reflector: Graphite and H U 2 Shield: Concrete and H 2O Number of Oper: tors: SRO-4, R0-0 Utilization: Operated for approximately 880 hours between 6/74 and 6/75 4 i b I i'
.Y
- 110 -
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. s Name: Maryland University TRIGA Reactor (MUTR) d Location: College Park, Maryland Docket Number: 50-166 License Number: R-70 Date of Initial .
Criticality: 1960 _, converted to TRIGA fuel-in 1973 . t Rated Power: 250 kw steady state no pulsing capability
Description:
Pool-type, TRIGA conversion research reactor Fuel: U-ZrH enrichment 20% clad stainless steel core loading 3.4 kg max. fuel temp. 1000 C max. excess A reactivity 2.5% k description 20 standard clusters, 4 fuel rods per cluster Max. Neutron Flux: 1.2 x 10 13 n/cm2 -sec Control Rods (3): 3 rod clusters 1 poison rod per cluster composition borated graphite A total worth 8.27% k Moderator: Zirconium-Hydride and H O 2 Coolant: HO 2 U Max. Coolant Temp.: 110 F
- 111 -
w
i e Reflector: Graphite and H 2O x
- Shield: Concrete and H 2O Number of Operators: SR0 - 7, R0 - 2 ,
Utilization: Operated 101 times generating 2.93 Mw-hrs of energy between 6/76 and 6/77. ,
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- 112 -
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Name: Texas A&M Nuclear Science Center Reactor (NSCR) Location: College Station, Texas 4- Docket Number: 50-128 License Number: R-83 Date of Initial Criticality: 1968 converted to TRIGA fuel in 1968 Rated Power: added TRIGA-FLIP fuel in 1973 Rated Power: 1 & steady state 2000 % peak pulse-
Description:
Pool-type TRIGA conversion Fuel: combination of TRIGA and TRIGA-FLIP fuel enrichment 20% 70% clad stainless steel critical mass 3.3 kg F f core loading 3.8 kg - max. fuel temp.5 525 0C, f, max. excess
, reactivity 4.9% [
A step insertion $2.70 (1.89% k ) Max. Neutron Flux: , 3 x 10 13 n/cm2 -sec (steady state) 6 x 10 16 n/cm2 -sec (pulse mode)
, Control Rods (5): 3 shim safety rods >
> 1 regulating rod composition , boron carbi.de,
, clad Aluminum l
\
total worth 6.9% ^k
; I , ,
j 1-
^'3' I t ansient rod j composition borated graphite l
+
a' l clad Aluminum l worth 2.9% agk
- 113 -
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. ..1 .
1 c Moderator: - Zirconium-Hydride and H O 2 Coolant: H0 2 Reflector: . Graphite Shield: CdncreteandH0 2 Number of Operators: SRO - 6. R0 - 3 Utilization: Operated approximately 2000 hours in 1973_ 4 e v 9 i I - 114 -
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s Name: Washington State University TRIGA Reactor Location: Pullman, Wash. Docket Number: 50-27 License Number: R-76 Date of Initial Criticality: 1962 Rated Power: 1 Mw steady state 2000 Mw peak pulse
Description:
TRIGA Conversion in 1967 Fuel: Combination TRIGA and TRIGA-FLIP U-ZrH 1.7 U-Z rH l.6 enrichment 20% 70% clad stainless steel core loading 3.7 kg. max. fuel temp. 861 C max. excess ak reactivity 4.9% k step insertion' l.75% ^k description modified TRIGA Mark III elements Max Neutron Flux: ' Control Rods (5): 3 control blades composition Boral clad Aluminum A total worth 6.1% k 1 regulating blade composition stainless steel worth. 0.3% ^k
- 115 - - - - - , , , , , ,- c- - -- w
a 4 1 transient rod borated graphite . worth 2.1% ^k Moderator: Zirconium-Hydride and fi 0 2 Coolant: HO 2 Max. Coolant Temp: 110 F-Reflector: Graphite and H 0 2 Shield: Concrete and H 2O Number of Operators: SRO-2, R0-4 Utilization: Generated approx.1000 Mw-hrs of energy
, between 6/76 and 6/77 6
t Ie ! - 116 - i
Name: University of Wisconsin Nuclear Reactor Location: Madison, Wisconsin Docket Number: 50-156 License Number: R-74 Date of Initial Criticality: 1967 f Rated power: 1 h steady' state 2000 N peak pulse square-wave operation
Description:
Converted in 1967 to a TRIGA Reactor with pulsing capability Fuel: Combination of TRIGA and TRIGA-FLIP enrichment 20% 70% clad stainless steel core loading 6.4 kg. max. excess ak reactivity 4.9% k description TRIGA, TRIGA-FLIP or a combination. Four element clusters. 25 clusters in core Max. Neutron 3.2 x 10h cm2 -sec steady state Flux: 6.5 x 10 cm -sec peak' pulse Control Rods (5): 3 safety blades composition Boral and stainless steel 1 regulating blade composition stainless steel Total worth 11% a k 1 Transient rod composition Borated graphite worth 2.9% a k
- 117 -
2. Moderator: Zirconium-Hydride and H 0 2 Coolant: HO 2
' Max. Coolant Temp: 130 F ,; . Reflector: Graphite and H20 Shield: Conctete and H 2O Number of Operators:
Utilization: Operated 121 times for approx. 470 hours and pulsed 59 times between 6/76 and 6/77 ( _J
- - 118 -
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Name: V. A. Hospital TRIGA Reactor Location: Omaha, Nebraska Docket Number: 50-131 R-57 License Number: Date of Initial Criticality: 1959 Rated power: 18 kw steady state no pulsing ability increase in rated power from 10 kw to 18 kw in 1963
Description:
Tank type reactor TRIGA fuel Fuel: U-ZrH l.0 enrichment 20% clad Aluminum critical mass 1.9 kg. core loading 2 kg. max. excess Ak reactivity 0.7% k Max. Neutron Flux: 4 x 10" "I cm2 -sec Control Rods (3): composition baron carbide powder
. clad Aluminum worth - safety rod 2% ^k shim rod 2% ^k regulating rod 0.4% ^k
- 119 -
Moderator: Zirconium-Hydride and H 2O Coolant: HO 2 Max. Coolant Temp.: 35 C Reflector: Graphite encased in Aluminum , Shield: Concrete and H 2O Number of Operators: SR0-2, R0-0 i r 6 . G
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-122-
Name: Dow Chemical Co. TRIGA MARK I Nuclear Reactor Location: Midland, Michigan Docket Number: 50-264 License Number: R-108 Date of Initial Criticality: 1967 Rated Power: 100 kw steady state no pulsing capability
Description:
TRIGA MARK I Research Reactor Fuel : U-ZrH 1.0 enrichment 20% clad Aluminum and/or Stainless Steel critical mass 1.9 kg core loading 2.3 kg max. excess reactivity 1.5% akk Max. Neutron Flux: 4 x 1012 n/cm2-sec Control Rods (3): 2 safety rods composition boron-carbide clad Aluminum individual worth 2.6% akk 1 regulating rod composition baron carbide clad Aluminum worth 0.8% ^k
- 123 -
4 Moderator: -Zirconium-Hydride and H O 2 !~ Coolant: HO 2 I Reflector: Graphite Shield: Concrete Number of Operators: SRO-6, R0-0 i i a e 1 i a k e i
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- 124 -
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Name: Dow Chemical Co. TRIGA MARK I Nuclear Reactor Location: Midland, Michigan Docket Number: 50-264 License Number: R-108 Date of Initial Criticality: 1967 Rated Power: 100 kw steady state no pulsing capability
== Description:== TRIGA MARK I Research Reactor Fuel: U-ZrH 1.0 enrichment 20% clad Aluminum and/or Stainless Steel critical mass 1.9 kg core loading 2.3 kg max excess reactivity 1.5% ak k Max. Neutron Flux: 4 x 1012 n/cm2-sec Control Rods (3): 2 safety rods composition boron-carbide clad Aluminum individual k worth 2.6% ^k 1 regulating rod composition boron carbide clad Aluminum worth 0.8% ^k ,
- 123 -
i
- Moderator: -Zirconium-Hydride and H 0 2
Coolant: HO 2 Reflector: Graphite Shield: Concrete Number of Operators: SRO-6, R0-0 t } I' i f-I i I
- 124 -
i
..-.,.,.~...,-.v.,,,, __ __ ,,,_____,__.._._____,__,,__,____,_____,%,_._ __._..m_ _ _ , _m,...___
, Name: University of Utah TRIGA Reactor
, Location:' Salt Lake City, Utah Docket Number: 50-407
-License Number: R-126 Date of Initial Criticality: 1975 Rated Power: 100 kw steady state No pulsing capabilities
Description:
TRIGA MARK I Below ground
-Fuel: U-ZrH or U- M j,7 l.0 enrichment '20%
clad Aluminum and/or stainless steel critical mass 2.4 kg. core loading 2.8 kg. , max. fuel temp. 530" C max. excess ak reactivity 2.25% k description TRIGA MARK I fuel elements Control Rods-(3): ? composition boron carbide clad Aluminum A worth - shim 2% safety ak 2% regulating 0.5% ak k
- 125 -
- . - . . . ~ _ _ - . . - .
-7 - . . - , - . - . -
Y
~
- Moderator
- Zirconium-Hydride and H O 2
i Coolant: HO 2 e Max. Coolant { Temp.: 110' F
- Reflector: H2 O and/or graphite elements and/or D 0
, 2 Shield: Concrete, sand, and H O 2 Number of Operators: SRO-1, R0-3 Utilization: Operated for 40 hours during first year of operation 4 4 5 1 e i r 4 Y f f i J i h 4
- 126.-
4
. _ _ - _ . . . , . , _ - . _ _ - , - _ . . . , - . _ ..._- _. ,~,,- . . , , . _ , , , , . . - _ , , . _ . , . . _ - . _ _ , _ _ . _.,_.__,~,_....,s~._-..
Name: The Reed College Reactor Facility Location: Portland, Oregon Docket Number: 50-288 License Number: R-112 Date of Initial Criticality: 1968 Rated Power: 250 kw staady state no pulsing capability
== Description:==
Fuel: U-ZrH 1.0 enrichment 20% clad Aluminum and/or stainless steel critical mass = 2.1 kg - max. excess reactivity
*2.25% ^k description TRIGA MARK I Fuel-Moderator elements Max. Neutron Flux: 1 x 10 13 n/cm2 -sec Control Rods (3): 2 safety rods composition boron carbide clad Aluminum individual worth 2.8% ^k 1 regulating rod composition baron carbide _
clad Aluminum worth 1.0% ^k
- 127 -
Moderator: Zirconium-Hydride and H O 2 Coolant: HO 2 Reflector: graphite Shield: H2 0 and Concrete Number of Operators: SR0 - 15, R0 - 10 9 6
- 128 -
p,-- - w Name: University of California, Irvine Nuclear Reactor Facility Location: Irvine, California Docket Number: 50-326 License Number: R-116 Date of Initial Criticality: 1969 Rated Pcwer: 250 kw steady _ state 250 Mw peak pulse
Description:
TRIGA MARK I Nuclear Reactor Fuel: U-ZrH1 .7 enrichment 20% clad stainless steel critical mass 2.3 kg core loading 2.7 kg max. excess reactivity 2.1% o k A step insertion 2.1% k 13 2 Max. Neutron Flux: 1 x 10 n/cm -sec (steady state) 1 X 10 16 n/cm2 -sec (peak pulse) Control Rods (4): 2 fuel follower rods composition borated graphite clad stainless steel individual worth $3.40 2 transient rods composition barated graphite clad Aluminum worth - adjustable rod - $2.30 fast rod - $0.50
- 179 -
. . . . . - . .- - - -..- . . - - . - - . . .- ..-.- - -.....---..~.---
2
- Moderator
- Zirconium-Hydride and H O 2
Coolant: HO 2 Reflector: Graphite
~
Shield: Concrete and H 2O Number of Operators: SR0 - 5, RO - 2 Utilization: Operated approximately 663 hours between j- 6/76 and 6/77. i I r i {' E f i 1 e 1 l b i J
- 130 -
e
Name: University of Texas TRIGA Reactor Location: Austin, Texas Docket Number: 50-192 License Number: R-92 Date of Initial Criticality: 1963 Rated Power: 250 kw steady state 250 Mw peak pulse increase in rated power from 10 kw to 250 kw (steady state) in 1%8.
== Description:== TRIGA MARK I type Fuel: U-ZrH enrichment 20% clad Aluminum core loading 2.3 kg max. fuel temp. 450 C max. excess reactivity 2.25% o k 13 2 Max. Neutron Flux: 1.3 x 10 n/cm -sec , Control Rods (3): 2 safety rods composition boron carbide powder clad Aluminum A total worth 3.5% k 1 transient rod composition borated graphite clad Aluminum worth 1.5% ^k
- 131 -
d 3 i Moderator: Zirconium-Hydride and H O 2
- Coolant
- HO.
2 Max. Coolant Temp. : 120 F , Reflector: Graphite and H O 2
; Shield: Concrete and H20 g
Number of Operators: SR0 - 2, R0 - 2 Utilization: Operated approximately 140 hours in 1977. t $~ j 4 i 4 b i !~ l r i- _. i l~ i l.
- i. - 132 -
i
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Name: University of Arizona TRIGA Reactor Location: Tucson, Arizona Docket Number: 50-113 License Number: R-52 Date of Initial Criticality: 1958 Rated Power: 250 kw steady state 300 Mw peak pulse
== Description:== TRIGA MARK I Reactor Fuel: U-ZrH 1.0 enrichment 20% clad stainless steel critical mass 1.9 kg. max. fuel temp. 700* C
^
step insertion 1.5% Max. Neutron Flux: i X 10I 3 n/cm 2-sec (steady state) 16 n/cm2 -sec (peak pulse) 1 X 10 Control Rods (3): composition boron carbide worth: safety rod 3% ^k shim rod 2% ^k transient 2. 5% ^ k Moderator: Zirconium Hydride and H20
- 133 -
M Coolant: H0 2 Max. Coolant Temp : 70* F Reflector: Graphite Shield: H2 0, graphite, concrete and soil Number of Operators: 'SRO-5, R0-5 Utilization: Operated approximately 294 hours and generated 1 17,000 kw-hrs of energy between 6/76 and 6/77 0 9 4 r 1
- 134 -
hame: Torrey Pines TRIGA MARK I Reactor Location: San Diego, California Docket Numoer: 50-89 License Number: R-38 Date of Initial Criticality: 1958 Rated Power: 250 kw steady state 800 Mw peak pulse
== Description:== Below ground. TRIGA MARX I Reactor Fuel: U-ZrH x enrichment 20% clad Hastaloy-X or Incaloy-80 core loading = 2.3 kg max. fuel temp. 530 C max. excess A reat t' fity 2.25% k k step insertion 1.6% ^k description 64 fuel elements , Max. Neutron Flux: 1.2 x 10 13 n/cm2 -sec (steady state) 1.2 x 10 16 n/cm2 -sec (peak pulse) Control Rods (4): 3 control rods 1 transient rod composition borated graphite total worth $10.73 Moderator: Zirconium-Hydride and H O 2 Coolant: HO 2 Max. Coolant Temp. : 65 C .
- 135 -
p e s i Reflector: ",' _ Graphite clad in Aluminum-s .
. . _~
' ='
Shield: Concrete and H 2O Number of Operators: SRO - 2.'R0 - 2 Utilization: Generated approximately 28 Mw-hrs. of energy ,in 1977. s t N % K V YQ% s - s ',. v.
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- 136 -
s
s Name: U. S. Geological Survey TRIGA Reactor Location: Jefferson County, Colorado Docket Number: 50-274 License Number: R-113 Date of Initial Criticality: 1969 Rated Power: I h steady state 1200 Mw peak pulse square-wave operation
Description:
TRIGA MARK I Nuclear Research Reactor Fuel: U-ZrHj ,7 enrichment 20% clad stainless steel critical mass 2.86 kg rrax. excess reactivity 4.9% ^k reactivity insertion 2.1% akk description TRIGA MARK III fuel-moderator elements Max. Neutron Flux: 3 x 10 13 n/cm2 -sec (steady state) 6 x 10 I6 n/cm2 -sec (peak pulse) Control Rods (7): 3 fuel follower rods - composition borated graphite clad - stainless steel 2 safety rods k individual worth 1.8% ^k l regulating rod worth 2.7% ^k
- 137 -
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,- A -
Control Rod,s (continded): .,
,1 transient, rod composi, tion- borated graphite v
clad , Alumfnum worth 2.1% ^k { , Moderator: Zirconium-Hydride and H 2O [ Coolant: HO 2 j ~ 0 '* Max. Coolant, Temp: , 60 C A ' Reflector.: .H2 0 and graphite r 4 Shield: 'H2O and. concrete Number of-Operators: SR0 - 3, R0 .0 t .
/ ,
Utilization: Operated for approximately '1300 hours in 1976.
?
4 4 r" e e
/-
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-139- - _ _ . . ~ . _ - _ - . - . _ _ . - . _ _ _ _ _ _ .. - _ __ ._ . . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ ___-_ _
1 I CONTROL-ROD g i-. II ; REMO ALTUBE 1
, TRAN FE TUBE
.j lON CHAMBER s N .
'l
, ROTARY
- - SPECIMEN RACK l
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, REFLECTOR f
I
~- - FUEL ELEMENT
.,~
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TRIGAMARKI Core and Reflector Assembly
-140-
j UB OR VE SHAFT l 6 II i hDS I E US 10N CHAMBER A FUEL ELEM NT 1 11 i i) J REFLECTOR ELEMENT w*..
.a l
C EN ON "h$ g AfYSUSAN)
- '-, R l FUEL ELEMENT GRIO PLATE 3 ( Mi-670 )
Cutaway view of reflector and rotary specimen rack surrounding TRICA Mark I or Mark II core
-141-
l Pneumatic Transfer System In-Core Terminus Y
,, y 7
~
~
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i=i Central Thimble 7 8_____ j
- Reactor Shroud
; l q, ! " g Ih l M- LLi l ~ 1
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^
V Fuel Element W
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<- 7 g , . . Positions l g ,
l f'.'.~
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Reactor core and shroud showing in-core terminus N ..
- i:
Wall-mounted laboratory terminus and MIS-48 convenient control assembly l l Pneumatic Transfer System l
-142-
l l ALUMINUM TOP END-FIXTURE GRAPHITE h SPACER
= -
c,;D l t ZIRCONIUM HYDRIDE-3 8-1/2 WT-% URANIUM
; N
'I 28.37 IN. -
14 IN. 1.41 IN. I !
~
~1.47 IN. t i 7' .
GRAPHITE 3.94 IN.
/tr ALUMINUM BOTTOM END FIXTURE MIII-30 U-ZrHl.0 '"*
-143-
STAINLESS STEEL TOP END FITTING
. GRAPHITE 3.45 IN.
1
- m o STAINLESS STEEL TUBE CLADDING THICKNESS 0.02 IN.
URANIUM ZlRCONIUM HYDRIDE-WITH AXIAL - ZlRCONIUM ROD 28.8 JN. 15 IN. TOTAL l .43 IN.- -
~
~ l.47 IN.
o v d GRAPHITE 3.45 IN. o STAINLESS STEEL v BOTTOM END FITTING U-ZrHl .6 fuel element. Can be used up to 2000 kW steady state and pulsing up to 2,000,000 kW (natural convection cooling); higher pulsing is optional. With forced convection cooling-steady state operation can be increased to 3000 kW with pulsing
-144-
ALUMINUM TOP END-FIXTURE l 1.476 IN. lllI l1 l 1 1.12 IN. ll llL
,S y/ ' 1.470 IN.
<\ / .a L ..I .
V ,, j' L---- L ij I 0.50 IN. I TOP END-VIEW OF FUEL ELEMENT
----l '
m GRAPHITE N l 4.00 IN. SAMARIUM -@;jgl l i ZlRCONIUM HYDRIDE- l 8 WT- % URANIUM h:~ t I i- 1 l 14.00 IN. 0.030 IN. WALL ': i 7W I I 23.00 IN.
' l 1
i 44 9 I I SAMARIUM k ! ., L - 28.44 IN. GRAPHITE *; . I 4.00 IN. t?___ j p
!c_,. _.__,_,'i 0.50 IN.
ALUMINUM BOTTOM-END FIXTURE o l 2.62 IN. I i 1.476 IN. I l' O a 1.470 iN. ! 57
~
BOTTOM END-VIEW OF FUEL ELEMENT TRIGA Mark i Fuel Moderator Element
-145-
- r m- m -
w
d SOFT SOLDER STAINLESS STEEL (1/ A.) 3 IN. 7: ! TRIANGULAR SPACER _ , _ _ END PLUG GRAPHITE END REFLECTOR
\
BURNABLE POISON m ZlRCONIUM ROD t FUEL-MODERATOR MATERIAL [%
.. W THERMOCOUPLES (3)
)
s h 1 {N. BURNABLE POISON h )h . ) W 94 + E
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STAINLESS STEEL glNg CLADDING ' z 2~' " 5 GRAPHITE END REFLECTOR
/ l?!
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l: l f1.471N.9 Instrumented TRIGA Fuel Element
-146-
i I l 1 1 10,000 , , , , , , , , , 1,000 O k 10 0 y - - o - - W 2 - -
.J w
j - - 4: w 3 I o 10 1,000 8
- MAXIMUM 6 - FUEL-ELEMENT TEMPERATURE - .
4 -
~~~~~~~~~~~--______
f W I W 2 I - g l POWER s 4 I a: I 100 W 5 % a.
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I I ' ' ' ' ' ' ' ' ' 10 O.1 O I 2 3 4 5 6 7 8 9 10 11 12 TIME (SEC) ,3 3) Transient power and fuel temperature as functions of time after 2.25% 6k/k ($3.00) reactivity insertion
-147-
Name: Cornell TRIGA Reactor Location: Ithaca, New York
$cketNumber: 50-157 License Number: R-80 Date of Initial Criticality: 1962 Rated Power: 100 kw steady state 250 Mw peak pulse
Description:
TRIGA f1 ARK II Reactor, above. ground Fuel: U-ZrH l.0 U-Zm l.7 enrichment 20% 20% clad Aluminum stainless steel critical mass 1.9 kg. core loading 2.9 kg. 0 max. fuel temp. 550 C 1000 C max. excess ak reactivity 2.6% k A step insertion 'l.5% k Max Neutron 5 x 10 steady state Flux: 1 x 10 peak pulse , Control Rods (4): 3 safety rods composition boron carbide clad aluminum worth - shim rod 1.7% ^k safety 1.7% Ak k regulating 0.9% ^k
- 149-
1 transient rod same composition and clad A worth 1.7% k Moderator: Zirconium-Hydride and H O 2 Coolant: HO 2 0 Max. Coolant Temp.: 130 F Reflector: Graphite Shield: , Concrete and H 2O Number of Operators: SRO-3, R0-0 t 0 0 4 4 J 4
..A 4
-150-
Name: Columbia University Research Reactor Location: New York, New York Docket Number: 50-208 License Number: R-128 Date of Initial License issued in 1977. Reactor operation Criticality: is currently suspended pending the outcome of court cases. Rated power: 250 kw steady state 250 Mw peak pulse
Description:
TRIGA MARK II research reactor Fuel: U-ZrH l.7 enrichment 20% clad , stainless steel core loading 2.3 kg. max. fuel temp. 500 C max. excess ak reactivity 2.45% k step insertion 1.5% ^k description TRIGA f1 ARK III ele.nents , Max Neutron 4.0 x 1012 n/cm2 -sec steady state . Flux: Control Rods (3): 2 safety rods composition . borated graphite clad stainless steel k total worth 3.5% ^k 1 pulse rod similar composition and clad worth 1.8% ^k
-151-
Moderator: Zirconium-Hydride and H O 2 Coolant: H0 2 Max. Coolant Temp.: 41 C Reflector: Graphite and H O 2 Shield: Concrete'and H 2O Number of Operators: SRO-2, R0-0 S O 4 f f i i ) ./ i.
-152-1 1- . ,.. . . .- . _ . . _ . _ ... . ...._.. , - ,.-.. .-- - . _ , , -- , , , .. . . ...-a , ,
Name: Kansas State University TRIGA MARK II Reactor (K5UIM II) Location: Manhattan, Kansas Docket Number: 50-188 License Number: R-88 Date of Initial Criticali ty: 1962 Rated Power: 250 kw steady state 250 Mw peak pulse Increase in rated power from 10 kw to 250 kw (steadystate)in1968
Description:
TRIGA MARK II Reactor with pulsing abilities Fuel: U-ZrH enrichment 20% clad stainless steel core loading 2.1 kg. max. fuel temp. 450 C max. excess Ak reactivity $1.92 (1.3% k ) Max. Neutron 2 Flux: 4 X 1012 n/cm -sec Control Rods (3): 2 safety rods composition boron carbide clad Aluminum total worth $6.00
-153-
1 regulating rod - composition Cadmium clad Aluminum worth $1.60 Moderator: - Zirconium-Hydride and H O 2 Coolant: HO 2 Max. Coolant Temp.: 60' C Reflector: Graphite Shield: Concrete Number of Operators: SRO-3, R0-4 i ll 3 l /
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-155-
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-156-
Name: Michigan State University TRIGA Reactor Location: East Lansing, Michigan Docket Number: 50-294 License Number: R-114 Rated Power: 250 kw steady state 250 Mw peak pulse
Description:
TRIGA MARK II Reactor. Transferred from University of Illinois in 1969 Fuel: U-ZrH l.0 enrichment 20% clad stainless steel core loading 2.3 kg. max. fuel temp. 500 C max. excess ^ reactivity 1.9% ak step insertion 1.5% Max. Neutron 2 Flux: 8 X 1012 n/cm -sec Control Rods (3): 2 safety rods composition boron carbide clad Aluminum
^
total worth 3.8% 1 transient rod composition solid boron carbide clad Aluminum worth 1.5% of
-157-
1 o Moderator: Zirconium-Hydride and H 2O
-Coolant: HO 2
Max. Coolant Temp.: 100*.F Reflector: Graphite and H O 2 Shield:, Concrete and H 2O Number of Operators: SRO-3, R0-3 6 h l
-158-
Name: Oregon State TRIGA Reactor (OSTR) Location: Corvallis, Oregon Docket Number: 50-243 License Number: R-106 Date of Initial Criticality: 1967 Rated Power: 1 N steady state r 00 W peak pulse square wave mode
Description:
TRIGA MARK II Research Reactor, above ground Fuel: combination of TRIGA and TRIGA-FLIP fuel U-ZrH j,7 U-ZrH l.6 enrichment 20% 70% clad stainless steel max.. excess reactivity 4.9% f step insertion 2.1% description TRIGA-FLIP fuel was added in 1976. Core may be completely TRIGA or TRIGA-FLIP or a combi, nation. Control Rods (4): 3 FLIP fuel follower rods composition graphite and boron carbide clad stainless steel total worth Ok 7.0% k 1 safety-transient rod similar composition and clad worth 2.45% ^pk a
-159-
Moderator: Zirconium-Hydride and H O 2 Coolant: HO2 Reflector: Graphite
. Shield: Concrete and H O 2
Number of Operators: SR0 - 8. R0 - 4 l 4 l .) i i- -160-
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-161-
w m_w2 s i. i 4 a s R b ? 9 ? ! MARK III i \ e } i i
Name: Penn State Reactor (PSR) Location: University Park, Pennsylvania Docket Number: 50-5 License Number: R-2 Date of Initial Criticality: 1955, converted to TRIGA MARK III in 1965 Rated Power: 1 N steady state 2 N peak pulse
Description:
TRIGA MARK III conversion, below ground Fuel: U-ZrH l.7 enrichment 20% clad stainless steel core loading 3.2 kg max. excess reactivity 4.9% ^k step insertion 2.38% ^k description TRIGA MARK III fuel elements Max. Neutron' Flux: 3.26 x 10 13 n/cm2 -sec (steady state) 16 6.52 x 10 n/cm2 -sec (peak pulse) Control Rods (4): 3 fuel fe). lower rods composition Silver - Indium - Cadmium total worth 6.3% ^k 1 transient rod composition Ag - In - Cd worth 2.1 % ^ k Moderator: Zirconium-Hydride and H 2O Coolant: HO 2
-163-
U Max. Coolant Temp. : 110 F Reflector: HO 2 Shield: Concrete and H20 Number of Operators: SR0 - 8. R0 - 3
> /
-164-
Name: Berkeley Research Reactor Location: University of California Berkeley, California Docket Number: 50-224 License Number: R-101 Date of Initial Criticality: 1966 Rated Power: I h steady state 2000 N peak pulse
Description:
movable-core TRIGA MARK III Reactor, above ground Fuel: U-Z r+1 1,7 enrichment 20% clad stainless steel critical mass 2.86 kg max. excess Ak - reactivity 4.9%
, , k Ak step insertion 2.1%
k 13 2 Max. Neutron Flux: 3.3 x 10 n/cm -sec(steady state) 6.5 x 10 16 n/cm2 -sec(peak pulse) Control Rods (4): 3 fuel follower control rods composition borated graphite clad stainless steel k total worth 4.5% ^k 1 transient rod composition borated graphite worth 2.1% Moderator: Zirconium-Hydride and H 2O \
-165-
Coolant: HO 2 Reflector: H0 2 Shield: Concrete and H 2O Number of Operators: SR0 - 8, R0 - 3 O e 4 S e O 4 e 4
-166-
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- 4. Horizontal Thermal Column 16. Isotope-Prodaction Facility (Lazy Susan)
- 5. Vertical Thermal Column 17 Reactor Core
- 6. Vertical Thermal Column Shield Plug 18. Exposure Room 4 7 Vertical Access Port 19. Exposure Room Shield Door
- 8. Radial Beam Ports 20. Experimental Access Conduits 4 9. Thermal Column Access Port 21. Borated Concrete Exposure Room Liner
- 10. Intersecting Through Ports 22 Removable Plate for Access to Vertical
- 11. Concrete Shielding Thermal Column 12 Movable Bridge 23 Enclosed Door Drive 1
1 -168-i
. - - - - - - . _ . - - - . , - , _ _ , . _ _ , _ - - . _ - . _ _ , . . , . , , , ~ , - - , _ - _ _ _ - _ . . - , - - - - -
I l 1 4 l l
/ MARK F
( 4 e
Name: Defense Nuclear Agency - TRIGA MARK F Owner: Armed Forces Radiobiology Research Institute (AFRRI) Docket Number: 50-170 License Number: R-84 Date of Initial Criticality: - 1962 Rated Power 1 h steady state 2000 Mw peak pulse increased rated power from iOO kw to 1 N in 1968
Description:
TRIGA MARK F, tank in a pool reactor -Fuel: U-ZrHj ,7 enrichment 20% clad stainless steel core loading = 3.5 kg 0 max. fuel temp. 600 C max. excess reactivity 3.5% ^k A step insertion 2.3% k description TRIGA MARK F fuel elements Max. Neutron Flux: 1.1 x 10 12 n/cm2 -sec (at 100 kw) Control Rods (4): 3 control rods composition boron carbide clad stainless steel total worth 5.9% ^k
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1 transient rod
, _ composition borated graphite r
clad stainless steel A worth' 2.1% k Moderator: Zirconium-Hydride and H O 2 Coolant: HO 2
- Max. Coolant Temp.: 60 C Reflector: lead and/or water
- Shield
- concrete and H 2O Number of Operators: SR0 - 4, R0 - 3 Utilization: generated approximately 9,800 kw-hrs of energy between 10/75 and 10/76 1
( t
. )
-170-e ud
Name: Northrop Reactor (NOR) Location: Hawthorne, California Docket Number: 50-187 License Number: R-90 Date of Initial Criticality: 1963 Rated Power: 1 N steady state 2000 % peak pulse
Description:
below ground, moveable core TRIGA MARK F Reactor Fuel: U-ZrH j,7 enrichment 20% clad stainless steel core loading 3.6 kg max. fuel temp. 600 C max. excess reactivity 3.8% Ok k description 87 fuel-elements 1.1 x 10 12 n/cm2 -sec Max. Neutron Flux: Control Rods (4): 3 safety rods composition borated graphite individual worth 1.4% ^k 1 pulse rod composition borated graphite 6 worth 3.4% k Moderator: Zirconium-Hydride and H O 2 Coolant: HO 2
-1 71 -
0 Max. Coolant Temp.: 90 C Reflector: Graphite and H 2O Shield: Concrete and H 2O Number of Operators: SR0 - 4, R0 - 1 I
~
/
-172-
Name: General Atomics TRIGA MARK F Reactor Location: San Diego, California Docket Number: 50-163 License Number: R-67 Date of Initial Criticality: 1960 Rated Power: 1.5 % steady state 8400 h peak pulse
== Description:== TRIGA MARK F Fuel: U-ZrH l .0 or U M 1.7 and special test fuel elements enrichment 20% clad Hastalloy X or Incalloy 800 critical mass = 2.5 kg core loading = 2.9 kg U max. fuel temp. - 570 C max. excess A reactivity 3.5% k A step insertion 2.8% k description TRIGA fuel elements Max. Neutron Flux: Control Rods (4): 3 fuel follower con' trol tubes composition 4 tmron carbide clad Aluminum A individual worth..l.8% k 1 transient rod same composition and clad werth 2.6% agk
-173-
n Moderator: Zirconium-Hydride and H 2O Coolant: HO 2 l 0 , Max. Coolant Temp.: 90 C Reflector: Hp 0, lead or graphite Reflector can be modified for any of these - material s. Shield: Concrete and H 2O Number of Operatars: SR0 - 2, R0 - 2 Utilization: Generated approximately 530 Mw-brs of energy in 1977. Note: The TRIGA MARK F reactor was originally designated as the FLAIR Reactor.(FLashingAdvancedIrradiationReactor). O
-174-
gy u - . - ~~- - - . -- . -- -- _.. , - = I' 5 e s t l i j l ADVANCED i i h f 4 4 8 l I a S b n 1 ,
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Name: Illinois Advanced TRIGA Reactor Location: Urbana, Illinois Docket Number: 50-151 License Number: R-115 Date of Initial 1969 Criticality: Originally a TRIGA MARK II but changed in 1969 to an advanced TRIGA Rated Power: 1.5 Mw steady state 6500 Mw peak pulse Square wave operation , Description : Advanced TRIGA . Fuel: U-ZrH;,p or U-ZrH 1.7 enrichment 20% clad stainless steel critical mass 2.6 kg. core loading 3.8 kg. max. fuel temp. 850 C max. excess reactivity $8.08 step insertion $4.60 description fuel elements in hexagonal array Control Rods (5): composition boratad graphite 3 fuel follower rods m individual worth
$3:00 1 udjustable transient cod worth $2.30 1 fast transient rod worth $2.30
-175-
- 3 1 Moderator: Zirconium-Hydride and H O 2 Coolant: HO 2 Max. Coolant Temp.: 50' C Reflector: Lead and graphite Shield: Concrete and H O 2 Number of Operators: , SRO-2, R0-2 Utilization: Reactor was operated approximately 1000 hours and pulsed 436 times between 6/76 and'6/77 t o we f
-176-
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-178-
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-179-
TRIGA* Reactors INSTALLATIONS AND CONVERSIONS ATAMl(M GE N t o Jan 197 7 MAmWUW RaffMG INif s AL M 3 SitADY Statt g caseiratify ar done 1 Uamertry of Anaena TR O taena 250 ta 300 000 me i2 7 Se fetsaa Cm%a.a 2 Genere Aeame TR Q Wee 8 .'So tw 800 000 an S ISR San Dego 3 Gease Aeam.c ?R o wet 7 i suo tw e a00 000 mm 7260 San Diego 4 Geaeef 4tonist IR'GA Wet in Decoamens.* *s 1 !7 66 San Diego 8' meraw 0==inaoa et lear *eap Ceturahan TRIGA Mart 8 L 000 me 4 500 000 aw n5el powenarae e ua.wwry of Cah8 ara.a feo wet su i 000 am 2 000 000 n* R 10 66 Rermenes 7 umverg ev of Caitara a TR Q Weti 250 ew 250 000 aw I& 29 69 inwone 8 Aerotest Opereiens '94 Ceiversea 2$0 tw F 9 6S Saa samaa
* *as. 4 u 5 Ge.* ogee Sun w, TR'GA Wen # 1000 ew 1.200 000 h* 22669 Deaver n.aw, 10 va e wg s #i e ao $ fRG Men te ; S00 aw 6.S00 000 aw e 16 60 Ureaae n aases Ii maases $#ee uasw py ?RG uma is 250 k* 250 000 ** to 16 62 Mancanaa uncane t2 marry 0 amond Laesareas fu $ Aanyi TR@ MenF 2% ta 2 000 000 m* 9 t&68 f orew 4ea 1i seveies Aerar, tatseet FRIGA test F 1.000 tw 2.000 000 ** ( 28 62 Setnews i4 umme+ry at Weyievi f RG Converusa 250 aw 6- t 3 74 Co.eee Pee W<a saa I$ the 00= Chomste Pomoony TAG weei 600 kW F 6 67 Means 16 Metaagan State umwr*.ty TN G usel 250tw 250 000 hw 3-21-69 Eant Lantag W4ea h 17 uneverste of is.taour. TRIGA Camerson 200kw unser Rossa Consdructica Noorasna in veteaas Admia. ore.on nonReas fRG Meti 10 kw 626 $9 Omens me= Meews 19 Sene a Carporahea tuSAEC) TR G ACPR 600 tw 12 000.000 ew 4267 Asewswergue feen *wt 20 Cowmpia umgert ty IRQ Mah II 250kw 250.000 kw Lceasse l mee vara 21 Caraon unaersty TRQ Met H 100 tw 250 000 me i 12 62 tram a Ortson 22 Oregon State univers.tv TRIGA Met il l 000 to 3 200.000 tw 3867 Corwaehs 23 Rees Ceese fR G usti 250 tw 1264 Partiane Peaawwama 24 Peanywaana State unswervfy TRrGA Met til Convertson 1000 tw 2.000 000 tw 12316%
unroervey Port 1 Puerto Ree 2S Puerto Rce Nucies Center f AsGA Converton Cm _Z 11912 we,asoes < fe.a. ,6 fe 6. e.,, ,8 . Ca e,wa i OOO .w 2 000 000.W . i 6. l Cease Sma ur 27 unvervey of fames TR O Weti 250 kw 2$0 000 nw 8263 Ausha ute 2e , f#o Wei s 250== in2> FS
,a or e,4utan wean 29 ur e, e.. a f so Cor , a i 000.w 2 000 000.w n i . .,
Mae10a wa a.aerea 30 wain.r stoa lme Va e,.., TRo Co.,orswa 1 000 .* 2 000 000.w F i A67 Pwiraan 31 w ouiagamase maatare teG Wet # 250 em Ua a ca.ane C.cs.cer, or n M P.O BOX 81608, SAN DIEGO, CAUFORNIA 92138 (714) 455 3574 TWX 910-335-1260 m
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- s TRIGA* REACTORS a,s,A,cn tr..n.ne. .no inoio,. proouti.On WANsWUtd 8 AfiNG INa ti At t IL A fluf8 $ft Afre $fAIf IBUt $1V, C9efif. At 6f 7 A., i, . e e W.e We, e4 s o era,ose rRiGA U.= H 230 6. 2s0 000 .. 3io e+r.nd
- ** *eeg8.hste ee8 haa8ea IAnnel<nfb Saylede9 TReGA Uma se t.@0 he 12*;0 000 e* unirles
",eem Congfriar td)n R'el 8 94 t'*6 8"% 89 sif Wandt fee 844 fElGA Wat6 2$0 km I a 6 60 itet et ssAprete o e geen) 4* " 6e 40 fasGA Wat8 250 aw 8 I4 71 in ' a"ghan'h a aneuseras t ige %4ede i ,ce se t vale anglet .te
- e et ren. e egeac e fR$A Was se 2*iG ha 2'el 000 na 32'6/
..% .% an, area any * ;eseesse (engee besese
- _ eNee fRCA Ware i 250 ha 4 2% 66
**r* Se+ter g
* * **ws Me toerg uekse%+8, FRfGA Wah 80 l@ ha .'90 000 tw e 3 6's W pe a as4e etwWI hp #de'dtsan hesem
- TR$A Was les 1000 km 2 000 000 am 9 / I 12
*/ es %Fe e Wa la a t'.deege e8 **eA ves TR4Awase 250 km i 18 #1 ear ne
- news te ed f re648tedT IR4A L Assegean l .@0 6 e Uticee 9 *.esset .et Cuerfe es;*nsp s,.nes a 4. of Ateenatwe f meGA W,
+ t ,t .. g 000 se !O is (4 694n.>d g a 4- % . ,, R ose , n (enen rR4A< .m f.e.,n g 00(s go o.00 g,,,u,, , ,nae,,,,,
fa o 4i Redfaca yensenettee tar Mentem
- nergy I#sGA Was el [M ha 6. gQ.t>O Ep . = ,
4 e= ==egd, # Per e 1844 W,. g.iG ha 250 000 11 18, b',
ud tekee- # a.4 ass Ahme== f 'sergy Segea * -ist tute f#eeGA A*Ptr 3@ ha 22 000 000 6- 10 f*i tee W sta 4 W. # . .niege .* tes a* a d, TRsGA Wat et 100 tw ? 2'a 61 i,
ase use,, oereers 'e TBCA Was ** 100 aw .286I s carw.ta e e.a 4e %,s e es Arcen. tareg enW # ,e. fR4A Was ** 2'io be 1 ; e 62 see .. 4e %es nia Atan. I nerg, east.tus. *RIGA Was He 2 000 kw 2 "l00 000 an a 10 72 Se == Waayve 'i f n evnes Asum=: RewaaP i ee TR4A Wan H 1000aw . 290 000 to unoer ei.*4 mpur ( onstrin tion Wese o t2 Nata,nes Cornmenson 's hi, see i neep TRIGA Wea ut t.000 aw 2 000 000 he ,1 S k8 U sv.- (Ay h meanna 4) ent 1.de for Nim sea tersiem4.g TRIGAXPW S00 te I$ 000 000 em unnee le a P pegt construction 4 .a I t see for pouries f ecnew 4,4 7RIGA I4.000 e 9 unaee a n neest .oasteur tw,n f riddand $4 Uffice af Atomet (nergy ra f De me TRIGA Was in Con =ersion 2 000 km 2.000 000 m* Unose 8 sng 48 Lonstrurtson luthey % letDnetal Unsuces.fr ref Islamefs TRIGA Une H 2$0 em 250 W kW under OttenOut f.dNtstruc tion Viet 80ddl %I laststuft of Nuclear Reisare TRIGA Wat H Deconentessioriset 22663 Deat v.,gnua.e *,,,9 ans,e cletan 8suc'ea Institute fRCA Wat H 250mm 41166 Lit +Usene lave 19 feutaea $oente Cornenmason TR4A Wah 't t 000 tw I 000 000 m* % 21 59 scar'got s asaeu late 181-
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+
b^ REACTOR TERMS G H (3
*1 B
w e- e e L_
Reactor Terms fission The splitting of an atom. The opposite process is fusion, which is combining two smaller atoms to make a larger one. Both processes release neutrons, gamma rays and heat. fissile Fissionable nuclear fuel such as Uranium-235,' Uranium-material 233 or Plutentum-239. Uranium-235 is the most common fuel. Plutonium-239 and Uranium-233 generally are not used in research reactors. Due to low power levels very little U-238 is converted to PU-239. (50 mega watt days produce about 6 grams of PU-239). fertile Material that may be made fissile by $bsorbing a neutron material and decaying, such as Uranium-238, which can be made into Plutonium-239 and Thorium-232 which can be converted to Uranium-233. critical That combination of fuel and poison where the chain reaction is constant. That is the number of neutrons available for fission is constant and the power level is not changing. A term called K-effective is 1 in
, this condition. Keff is also called the neutron Lelance equation.
. nuclear A combination of fuel and control systems capable of reactor attaining a self-sustaining chain reaction.
critical A type of nuclear reactor that generally operates at facility very low power levels such as 0.1 watts, which is l below the point where heat is generated. Compare, for example, to the heat generated by a 100 watt bulb. i
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fast A reactor capable of sustaining a chain reaction using reactor high energy neutrons. There are ve.ry few of this type; none regulated by NRC. They require about 10X ~ more fuel than a so-called thermal reactor. These reactors do not use a moderator. thermal The chain reaction is niaintained by thermalized (low reactor energy) neutrons. These reactors require much less fuel than fast reactors because the fuel more readily absorbs thermal neutrons. core The fuel area of the reactor. refl.ector Material placed around a core to reflect some of the escaping neutrons back into the core. moderator Material in a reactor used to slow down (thermalize) neutrons. Usually water or graphite or polyethylene. poison Anything that absorbs neutrons such as boron, hafnium, cadmium, xenon, etc. barn Unit of measure originated in manhattan project that describes how readily a neutron is absorbed In a material. control Usually a poison used to control the chain reaction. rods In the case of the AGN reactors, fuel rods are used for control in a manner similar to but inverse to the manner poison rods are used. excess Nuclear term that is related to the amount of fuel reactivi ty in the core in excess of that needed to achieve a critical mass. Excess reactivity is increased by ; adding fuel and is nomally expressed as akk
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shutdown A measure of the ability of the control rods to margins compensate for excess reactivity. Usually the term is a measure of how much a reactor is below being critical assuming one rod is stuck in the out position. scram Term used to describe the automatic rapid insertion of control rods in the core to shutdown the reactor. PWRs generally use the word trip, which means the same thing. prompt A condition created by rapidly adding positive , critical reactivity to the core (sudden movement of a control rod) such that power rises in a rapid and uncontrolled manner. Enough positive reactivity must be added to over come the time delay effect on power rise of the delayed neutrons. This is usually about .7% akk
- An example of prompt criticality is a pulse where power rises from 1 watt to 4000 megawatts in a fraction of a second. Prompt criticality can occur any time and 'in any location where sufficient fuel is consentrated in a small area under optimum conditions of moderation.
delayed 99.3% of the neutrons that result from fission occur neutroas immediately (within 10-I4 sec). The other 0.7% of the neutrons (delayed nuetrons) appear over the next minute or two. These neutrons are very important to the safety of a nuclear reactor because they slow down the chain reaction. Nonnal changes to power level are controlled to a maximum of one power of 10 (e.g., going from 1 watt to 10 watts to 100 watts) per minute. If the delayed neutrons were not present to slow down the chain reaction, the power level would change several thousand powers of ten per minute. This is a prompt critical condition.
-185-
reactivity (ak/k) Terin used to describe the ability of the reactor to respond. Changes in reactivity are nomally made by changing the position of control rods; however, changing to position of an experime.1' or the amount of fuel will also cause changes in reactivity. Reactivity is frequently expressed in $ and ( of reactivity where a $1 addition of reactivity to a critical reactor would cause the reactor to go prompt critical. K-effective (Keff)
. This terin represents the neutron balance equation.
When the reactor is critical Keff = 1 which means that as many neutrons are being born as are being lost. When the reactor is shutdown Keff equals about 0.8. - Note: If a reactor's reactivity is said to be Keff = 1.02, this means that if the rods were removed the reactor is capable of attaining a Keff of 1.02. Another way of stating this is that the reactor' has either .02 ^ , 2% A or $2.85 of excess reactivity.
-186-
Radiation and Shielding Alpha particles (a ) short range, very high energy particles. Relatively rare except around heavy elements. Frequently found
'in small amounts in concrete or rocks that contain natural uranidm. Alpha emitting particles are considered dangerous if inha16d or injested; however, externally skin or a piece of paper are sufficient to stop them. Alpha particles travel about an inch in air.
Beta particles - (S) Very common form of radiation. Beta particles (or rays) are actually high energy electrons. They can cause the skin to turn red similar to sunburn. Beta particles are fairly easy to stop and will travel about 4-5 inches in air. Gamma Rays - (y) The most common form of radiation found around a shutdown reactor. Usual sources are activated experimental apparatus. Gamma rays are a highly penetrating form of radiation. For all practical purposes they are not stopped by air. Usually when one speaks of a radiation field or a radiation dose rate they are referring to gamma radiation. To reduce gamma radiation by a , factor of 10 requires approximately 2 inches of lead or 4 inches of steel or 24 inches of ordinary concrete or water. If the source of gamma rays can be approximated as a point source then the radiation level decreases with the square of the distance. This means that if you double your distance from the source the radiation field is reduced to 1/4 of the original value. Example: If a self protecting fuel rod reads 100 Rem /hr at 3 feet it should read approximately 25 Rem /hr at 6 feet. Conversely at 1-1/2 feet from the fuel rod the dose rate would be about 400 Rem /hr. A NL
-187-
l l Neutron Radiation - Neutrons are produced in the reactor core by the fission process. When the reactor is shutdown this radiation is insignificant. During operation neutron leakage out of the reactor if all shielding is in place will equal approximately 25% of the radiation level due to gamma rays from the same source. In the-core or with a beam port plug removed the neutron radiation would be about 300 times the radiation level of the gamma rays. Fast (high energy) neutrons are about 3 times more dameging than thermal (low + energy) neutrons. Neutrons are slowed down by water, polyethelene and to some extent iron. When thermalized they are readily absorbed by boron cadmium and many other materials. Cerenkov Radiation - The blue glow around water moderated reactor ' fuel is caused by the rapid deceleration of electrons. These electrons are produced by fission product gamma rays. 9 L i
/
i
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L , s Radiation Levels (Approximate) (milli = 1/1000) 200 milli Rem / year Normal Background Radiation 2 milli Rem /hr Maximum radiation level allowable in an unrestricted area 10 milli Rem /hr A normal area radiation monitor set point 100 milli Rem /hr Upper limit of Radiation Area - Lower limit of High Radiation Area 125 milli Rem / quarter Exposure limit for non radiation workers 1.2'S Rem / quarter (5 Rem /yr) Exposure limit for radiation workers 25 Rem /2 hr period Part 100 design limit in event of accident 25 - 100 Rem Emergency life saving dose (slight blood changes) 100 R at 3 feet Self protecting defination 200 Rem (whole body) Moderate blood changes 300 Rem (whole body) Vomiting within 2 hoursloss of hair aRar2 weeks 400 Rem (whole body) 50% fatalities - hemorrhage, infection 800 Rem (whole body) 80-100% fatalities within 2 months 2500 Rem (localized) Given to cancer patients 1 million Rem /hr Radiation level in core of 100kw Research Reactor
~
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-189-o L.______. _ _ __ _ _ _ . . _
PRINCIPLE NAMES AND ADDRESSES f 6 9 E a
Name: AGNIR Docket No.: 50-228 Address: Aerotest Operations, Inc. 3455 Fostoria Way San Ramon, CA 94583 Supervisor: R. L. Newacheck Telephone No.: 837-4248 Correct as of 9/76 Name: AFRRI Docket No.: 50-170 Address: Defense Nuclear Agency - Armed Forces Radiobiology Institute Bethesda, MD 20014 Supervisor: Capt. J. Casady Telephone No.: 301-295-0411 Correct as of 9/76 Name: Lynchburg Pool Reactor / Babcock & Wilcox Critical Facility Docket No.: 50-99, 50-13 Address: Babcock & Wilcox Company ATTH: Dr. T. C. Engelder Director, Lynchburg Research Center P. O. Box 1260 Lynchburg, VA 24505 Supervisor: Dr. T. C. Engelder Telephone No.: 804-384-5111 Correct as of 9/76 Name: Brigham Young University, L-77 Reactor Docket No. : 50-262 Address: BYU Reactor Facility c/o D. R. Dixon 166 Eyring Science Center Brigham Young University Provo, UT Supervisor: D. R. Dixon Telephone No.: 374-1211 Correct as of 9/77 X4216
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1 Name: California Polytectnic AGN-201 Docket No.: 50-394 Address: Bldg. 40, Room 103, Mechanical Engineering Department California Polytechnic State University San Luis Obispo, CA 93407 Supervisor: R. W. Adamson Telephone No.: 805-546-2405
- Correct as of 9/77 Name
- Catholic University Reactor Docket No.: 50-77 Address: 620 Michigan Avenue, N.E.
Washington, D. C. 20064 i i e Supervisor: Dr. Paul Thiess Telephone No.: 202-635-5184
. Correct as of 9/77 i
Name: Cornell TRIGA Reactor / Cornell ZPR Reactor Docket No.: 50-97, 50-157 - Address: Cornell University Ithaca, NY 14850 , 1 Supervisor: Dr. H. Aderhold Telephone No.: 607-256-3480 Correct as of 9/77
- Name: Dow Chemical Co, TRIGA I Reactor i Docket No.: 50-264 Address: Dow Chemical Company
, 1602 Building
- Midland, MI Supervisor: 0. Anders Telephone No.: 636-0304 i Correct as of 9/76
,)
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l l Name: Toney Pines TRIGA MARK I / General Atomic TRIGA MARK F Docket No.: 50-89, 50-163 Address: General Atomic Company P. O. Box 81608 San Diego, CA 92138 i k i Supervisor: W. L. Wittemore Telephone No.: 714-455-3277 Correct as of 9/77 Name: General _ Electric / GETR, NTR Docket No.: 50-70,-50-73 Address: General Electric Company Vallecitos Nuclear Center P. O. Drawer B Pleasanton, CA 94566 I Supervisor: R. W. Darmitzel Telephone No.: 415-862-2211 1 X4344 Correct as of 9/76 Name: GTRR ! Docket No.: 50-160
- Address: Georgia Institute of Technology l ATTN: Dr. M. V. Davis, Director i N0 clear Research Center Atlanta, GA 30332 l
Supervisor: Dr. Lynn Weaver Telephone No.: 404-894-3724 ; l j Correct as of 9/77 i Name: Georgia Tech AGN-201 , Docket No.: 50-276 Address: Georgia Institute of Technology 4 School of Nuclear Engineering Atlanta, GA 30332 i. Supervisor: Dr. Lynn Weaver Telephone No.: 404-894- 3724 i Correct as of 9/77 QB ! -193-l l i- _ - . _ _ _ ._ . , _ ~ . . . _ , _ , , - - , _ _ , , . . . . _ _ , _ - . . _ , , _ _ _ . , _ _ _ . _ . . , , _ . , - . _ _ _ . . _ , _ _ _ _ , _ _ _ .
4 4 J Name: Idaho State AGN-201 Docket No.: 50-284 Address: School of Engineering Idaho State University Box 8060 Pocatello, ID 83201
- Supervisor
- A. E. Wilson Telephone No.: 208-236-0211
!- Correct as of 9/77 X2281 Name: Iowa State University Docket No. : 50-116
, Address: Huclear Engineering Laboratory i Iowa State University
- Ames, 10 50011 i
) Supervisor: Dr. Adolf F. Voligt Telephone No.: 515-294-2500 Correct as of 9/77 Name: Kansas State University TRIGA MARK II Reactor Docket No.: 50-188 ~ Address: Ward Hall
- Kansas State University l Manhatten, KS 66506 i
1 1 . Supervisor: Michael McEwar Telephone No.: 913-532-5624 l j Correct as of 9/77 Name: Manhatten College ZPR Docket No.: 50-199 j Address: Manhatten College Bronx, NY 10471 i j 1 ! Supervisor: Bro. G. Kane Telephone No.: 212-548-1400 l Correct as of 9/77 X295 l I
- -194-
Name: MITR Docket No.: 50-20 Address: Mass. Institute of Technology 138 Albany St. Cambrige, MA 02139 - i Supervisor: OttoK. Harling Telephone No.: 617-253-4211 - Correct as of 9/77 i Name: Michigan State University TRIGA Reactor i Docket No. : 50-294-i Address: Division of Engineering Research Michigan State University
- East Lansing, MI 48824 l
4 3 Supervisor: Jim Carrick . Telephone No.: 517-353-9097 l Correct as of 9/77
- Name
- NSBS Docket No.: 50-184 -
) Address: U.S. Department of Commerce National Bureau of Standards t Washington, D. C. 20234 Supervisor: T. P'by Telephone No.: 301-948-0083 i Correct as of 9/ 76 i I Name: Rockwell International / L-77, L-85 i Docket No.: 50-94, 50-375
- Address: 8900 DeSoto Avenue Canoga Park, CA 91304 i
i j Supervisor: M. E. Remley Telephone No.: 213-341-1000 X2238
- Correct as of 9/76 C
! -195-l-
)' i t i
! Name: PULSTAR - N.C. State
_ Docket No.: 50-297 Address: N.C. State University Department of Nuclear Engineering Raleigh, NC 27607 4 Supervisor: J. R. Bohannon Telephone No.: 919-737-2322 Correct as of 9/76 Name: Northrop Reactor
- Docket No.: 50-187
) Address: Northrop Research & Technology Center l 3401 W. Broadway Hawthorne, CA 90250 Supervisor: D. H. Rusling Telephone No.: 213-970-2297 l , Correct as of 9/76 i l Name: Ohio State University Reactor i Docket No.: 50-150 i Address: 1298 Kinnear Road Columbus, OH 43212 ! . Supervisor: 8. K. Hajek Telephone No.: 422-6755 Correct as of 9/77 Name: Oregon State TRIGA Reactor / Oregon State AGN Reactor j Docket No.: 50-243, 50-106 Address: Radiation Center OSU j Corvallis, OR 97331 l Supervisor: C. H. Wang Telephone No.: 503-754-2344 ] Correct as of-9/77 i I
-196-1
i-a I Name: Penn State Reactor r Docket No.: 50-5 Address: Pennsylvania State University ( University Park, PA 16802 i l t Supervisor: Robert Totenbier Telephone No.: 814-865-6351 j Correct as of 9/77 4 Name: Purdue University Reactor Docket No.: 50-152
! Address: Purdue University I -
Nuclear Engineering Department West Lafayette, IN 17907 4 I l j Supervisor: Eldon R. Stansberry Telephone No.: 317-749-2920 Correct as of 9/77 l 1 l Name: Reed College Reactor Facility i Docket No.: 50-288 Reed Reactor Facility Address: Reed College , j Portland, OR 97207 : i j ! Supervisor: K. Higley Telephone No.: 503-771-1112 l Correct as of 9/76 l Name: RPI Critical Experiments Facility Docket No.: 50-255 Address: Rensselaer Polytechnic Institute Troy, NY 12181 I Supervisor: Telephone No.: 518-393-4281 l Correct as of 9/76 1 x .
-197-
i l Name: Rhode Island Open Pool Reactor Docket No.: 50-193 i Address: Rhode Island AEC ! South Ferry Road ' j Narragansett, RI 02882 . ? ! Supervisor: A. F. DiMeglio Telephone No.: 407-789-9391 Correct as of 9/76 ' Name: PULSTAR - State University of New York , Docket No.: 50-57 Address: Nuclear Science & Technology Center State University of New York at Buffalo 1 Rotary Road } Buffalo, NY 14214 ; i I 1 i Supervisor: P. Orlosky Telephone No.: 716-831-2826 Correct as of 9/77 i 1 Name: Texas A&M AGN-201 i i Docket No.: 50-59 1 Address: Department of Nuclear Engineering i Texas A&M University
- College Station, TX 77843 1
j Supervisor: J. B. Zgliczynski Telephone No.: 713-845-4161 l 1 l Correct as of 9/77 1 i Name: Texas A&M Nuclear Science Center Reactor i i Docket No.: 50-128 Aadress: Nuclear Science Center Texas A&M University
- F. E. Box 89
- l College Station, TX 77843 <
1 ! j Supervisor: J. D. Randall Telephone No.: 713-845-7551 Correct as of 9/76 1 ! -198- , l
4 Name: Tuskegee AGN-201 Docket No.: 50-406 , j Address: Tuskegee Institute ' i School of Engineering Tuskegee, AL i 4 Supervisor: Z. W. Dybczak Telephone No.: 205-727-8354 Correct as of 9/76 l ! Name: Union Carbide Nuclear Company Research Reactor i j Docket No.: 50-54 i Address: Union Carbide Corp. j P. O. Box 324 4 Tuxedo, NY 10987 ' 1 i Supervisor: W. Fecych Telephone No.: 914-351-2131 I Correct as of 9/76 ' Name: U.S.G.S. TRIGA Reactor j Docket No.: 50-274 ' Address: U;S. Geological Survey , Mail Stop 424 ! Box 25046, Federal Center ! Denver, CO 80225 J j Supervisor: Pat Kraker Telephone No.: 303-234-2608 Correct as of 9/76 : ) -Name: University of Arizona TRIGA Reactor i ( Docket No.: 50-113 l Address: Room 122, Engineering Building i The University of Arizona , Tucson, AR 85721 l I
- Supervisor
- Dr. George Nelson Telephone No.:
602-884-2565 i Correct as of 9/77 I
- -199-l
1 l I Name: UCLA Training Reactor Docket No.: 50-142 Address: UCLA School of Engineering 2567 Boelter Hall - N.E.L. Los Angeles, CA 90024 Supervisor: Mr. Anthony Zane Telephone No.: 213-825-2040 Correct as of 9/76 Name: Berkeley Research Reactor Docket No.: 50-224 Address: Department of Nuclear Engineering University of California Berkel ey, CA 94720 Supervisor: Ted H. Lim Telephone No.: 415.642-5213 Correct as of 9/77 Name: Irvineliuclear Reactor Facility Docket No.: 50-326 Address: Department of Chemistry University of California, Irvine l'rvine, CA 92717 Supervisor: G. E. Miller Telephone No.: 714-833-6083 Correct as of 9/77 Name: Santa Barbara L-77 Reactor Docket No.: 50-443 Address: Regents of the University of California c/o University of California, Santa Barbara Santa Barbara, CA 93106 Supervisor: A. E. Profio Telephone flo. : 850-961 -3788 Correct as of 9/77
-200-
I 2 1 4 , Name: University of Florida Training Reactor Docket No.: 50-83 Address: University of' Florida ' l 202 Nuclear Science Building Gainesville, FL 32601 Supervisor: Dr. N. Ofaz Telephone No.: 904-392-1429 Correct as of 9/77 Name: Illinois Advanced TRIGA and L0pRA Reactors Docket No.: 50-151, 50-356 Address: Nuclear Reactor Lab., University of Illinois
! Urbana, IL 61801 i
Supervisor: Gerald P. Beck Telephone No.: 217-333-0866 f L
. Correct as of 9/76 --
Name: Lowell Technology Institute Reactor i Docket No.: 50-223 , Address: University of-Lowell One University Avenue ! Lowell, MA 01854 Supervisor: Tom Wallace . Telephone No.: 617-458-9081 I l Correct as of 9/77 l ! Name: University of Kansas Training Reactor Docket No.: 50-148
- Address
- Nuclear Reactor Center
, University of Kansas Lawrence, KS 66045
~
i l j Supervisor: Russel Mesler Telephone No.: 913-864-3938 l Correct as of 9/76 i A.
-201-l . - . , . - , _ . . . . . , . _ . ,,..___.m__ _ - , _ , . . . - . . _ . _ . - , _ _ . . . _ . . . . _ _ , , . , . _ . , _ . . - _ . _ , . = . _ . . _ _ . - . . , , , , _ - . _ . _ _ . - . _ _ _ , . - _ _ _ _ _ --,-,,c , , . _ . . _ - , _ . .
s l l l Name: Maryland University TRIGA Reactor Docket No.: 50-166 Address: University of Maryland - College Park, MD 20742 Supervisor: Dr. Jim Sheaks Telephone No.: 301-454-2436 - Correct as of 9/77 i l Name: Ford Nuclear Reactor l Docket No.: 50-2 Address: 2301 Bonistell Blvd. ! North Campus i University of Michigan Ann Arbor, MI 48109 l Supervisor: R. Burn Telephone No.: 313-764-6223 . Correct as of 9/77 ! T Name: MURR Occket No.: .50-186 . Address: University of Missouri 7 Columbia, M0 ; i Supervisor: Charles McKibben Telephone No.: 314-882-4012 Correct as of 9/77 i Name: University of Missouri Nuclear Reactor Facility Docket No.: 50-123 Address: University of Missouri, Rolla Rolla, MO 65401 i Supervisor: Alva Elliott Telephone No.: 314-341-4236 Correct as of 9/77 l r
-202-
Name: University of New Mexico AGN-201 Docket No.: Nuclear Engineering Laboratory Address: Department of Chemical & Nuclear Engineering University of New Mexico Albuquerque, NM Supervisor: Dr. Robert Long Telephone No.: 505-277-5431 Correct as of 9/77 Name: University of Oklahoma Reactor Docket No.: 50-112 Nuclear Reactor Laboratory Address: NEL Building University of Oklahoma Norman, OK 73019 i l Supervisor: Johnny James Telephone No.: 405-325-5084 Correct as of 9/77 Name: University of Texas TRIGA Reactor Docket No.: 50-192 Address: Nuclear Reactor Laboratory University of Texas at Austin Austin, TX 78772 Supervisor: Dr. Lynn Draper Telephone No.: 512-47'1-5136 Correct as of 9/77 Name: University of Utah AGN-201 / TRIGA Nuclear Reactor Docket No.: 50-72, 50-407 Address: Univers 'y of Utah Nuclear keactor Laboratory Salt Lake City, UT 84112 Supervisor: G. M. Sandquist Telephone No.: 801-581-7109 Correct as of 9/77
\
-203-l l
Name: University of Virginia / UVAR, CAVALIER Docket No.: 50-62, 50-396 Address: University of Virginia Department of Nuclear Engineering Charlottesville, VA Supervisor: Dr. Meem Telephone No.: 804-924-7136 Correct as of 9/77 Name: University of Washington Nuclear Reactor Docket No.: R-73 Address: Nuclear Reactor FD-10 University of Washington Seattle, WA 98105 i Supe rviso'r: Dr. A. L. Babb Telephone No.: 206-543-2754 Correct as of 9/77 Name: University of Wisconsin Nuclear Reactor Docket No.: 50-156 Address: Reactor Laboratory i Mechanical Engineering Building University of Wisconsin Madison, WI i Supervisor: R. J. Cashwell Telephone No.: 608-262-3392 j Correct as of 9/77 i Name: V. A. Hospital TRIGA Teactor ' Docket No.: 50-131 l Address: 4101 Woolworth Avenue Omaha, NB 68105
; Supervisor: A. J. Blotcky Telephone No.: 346 8800 l X 32 Correct as of 9/76 1
1 -204-I
I i ! Name: VPISU University Training Reactor i Docket No.: 50-124 Address: Virginia Polytechnic Institute and State University j
- Nuclear Engineering Group
- Blacksburg, VA 24061 ,
) Supervisor: Robert Stone Telephone No.: 703-951-6510 i Correct as of 9/77 ! I Name: Washington State University TRIGA Reactor j Docket No.: 50-27 , i Address: Nuclear Radiation Center ! .l Washington State University [ j i i I l 509-335-8641 l Supervisor: Dr. W. E. Wilson Telephone No.: l Correct as of 9/77 ! i Name: Westinghouse NTR i Docket No.: 50-87 l 1 Address: Westinghouse Training Center , j 505 Shiloh Blvd. 1 Zion, IL 60099 , t I ! [ ! Supervisor: John M. Roth Telephone No.: 312 872-4585 . i l Correct as of 9/76 ( ! 'Name: WP! Reactor i Docket No.: 50-134 .
- Address
- Worcester Polytechnic Institute
- Worcester, MA 01609 ,
i . 1 i [ i Supervisor: L. C. Wilbur Telephone flo. : 617-753-1411 , Correct as of 9/77 l i i l 205-1 : i
t i i i i i t i 1 i, INDEX i a O / . I 4 r i t l f .i e i 1 j i 4 W I O ,i gue s
- h M
4 4 l i
Licensee Docket # Page # I. Research Reactors Aerotest Operations Inc. (TRIGA)--------------------- 50-228 109 Armed Forces Radiobiology ResearchInstitute(TRIGA). 50-170 169 Ba bcock & Wi l cox Co. (LPR)--------------------------- 50-99 87 Brigham Young Univ. (L-77) 50-262 27 Calif. State Polytechnic College (AGN-201) 50-394 5 Ca thol i c Uni v. ( AGN-201 )---------------------------- 77 7 Columbia Univ. (TRIGA II) 50-208 151 Cornell Univ. (ZPR) 50-97 47 Cornell Univ. (TRIGA) ------------------------------ 50-157 149 DowChemicalCo.(TRIGAI) . 50-264 123 General Electric Co. (NTR) 50-73 51 Georgia Institute of Tech. (AGN-201)----------------- 50-276 9 Georgia Institute of Tech. 50-160 55 GeneralAtomicCo.(TRIGAI) 50-89 135 General Atomic Co. (TRIGA F)---------- *-------------- 50-163 173 Idaho State Univ. (AGN-201) 50-284 9 Iowa State Univ. (UTR-10) 50-116 45 Kansas State Univ. (TRIGA II)------------------------ 50-188 153 Manhatten College 50-199 67 Mass. Institute of Tech. 50-20 61 Michigan Sta te Univ. (TRIGA I)----------------------- 50-294 157 Rockwell Int'1. Corp. (L-77) 50-94 23 < Rockwell Int'1. Corp. (L-85) 50-375 31 North Carolina State Univ. (PULSTAR)----------------- 50-297 103 Northrop Corporate Lab. (TRIGA) 50-187 171 Ohio State Univ. 50-150 79 OregonStateUniv.(AGN-201)-------------------------50-106 5 Oregon State Univ. (TRIGA II) 50-243 159 Penn. State Univ. (TRIGA III) . 50-5 163 Purdue Univ.----------------------------------------- 50-182 77 Reed Institute (TRIGA !) 50-288 127 Rhode Island AEC 50-193 95 State Univ of New York (PULSTAR)-------------------- 50-57 101 Texas A&M Univ. (TRIGA) 50-128 113 Texas A&M Univ. (AGN-201) 50-59 7 Tus kegee Ins ti tute ( AGN-201 ) ------------------------ 50-406 9 Union Carbide Corp. 50-54 99 U.S.G.S. (TRIGA !) 50-274 137 University (of: !)---------------------------------- Arizona TRIGA 50-113 133 California Argonaut) 50-142 35 California TRIGA !!!) 50-224 165 California TRIGA !)------------------------------- 50-326 129 California L-77) 50-433 27 Delaware (AGN-201) 50-98 5 Florida (Argonaut)---------------------------------50-83 37 1 1
- 207 -
{ l
1 l 1 1 4 i i ! Licensee Docket # Page # l ! Research Reactors (continued) i ! University of: Il linoi s (Advanced TRI GA )-------------------------- 50-151 1 175 ! Illinois (LOPRA) 50-356 107 i Lowell 50-223 85
- Kansas -------------------------------------------- 50-148 83 j Maryland (TRIGA) 50-166 111 Michigan 50-2 91 Missouri ------------------------------- ---------- 50-123 81 i Missouri 50-186 75 i New Mexico (AGN-201) 50-252 9 1 Oklahoma (AGN-211)--------------------------------- 50-112 11 i Texas (TRIGA) 50-192 131 i Utah (AGN-201) 50-72 7
! U ta h ( TR I GA I ) ------------------------------------- 5 0- 4 0 7 125 i Virginia (UVAR) 50-62 97 Virginia (CAVALIER) 50-396 69 l' Was hi ngton ( Argona u t )------------------------------ 50-139 41 i Wisconsin (TRIGA) 50-156 117 j V.A. Hospital (TRIGA) 50-131 119 j Va. Folytschnic Institute---------------------------- 50-124 43 Wash. State Univ. 50-27 115 Westinghouse . 50-87 49 ! Worcester Polytechnic Insti tute---------------------- 50-134 71 1 ! !!. Test Reactors
- i
! General Electric Co. (GETR) 50-70 53 l Na tional Bureau o f S tandards------------------------- 50-184 65 i !!!. Critical Experiment Facilities 4 Babcock & Wilcox Co. 50-13 17 j Rensselaer Polytechnic Inst.--------------------------50-225 19 l
- 208 -
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