IV. REACTORS

A. SMALL EXPERIMENTAL PILES

1. Design and operating characteristics of small experimental piles in which enriched material or heavy water is used, provided the pile generates power at a level under 100 KW. No information is to be released beyond the minimum necessary for the successful design and operation of such a small unit and in information essential for the successful design and operation of a production pile. (46-1)

2. Information can be released as to which non-classified isotopes and fission products can be produced in a pile. Caution must be exercised not to reveal production capabilities by disclosing critical data as to the amounts of such substances on hand or the rate at which they can be made. (46-1)

3. Design and operating characteristics of small experimental piles in which enriched material or heavy water is used, provided the pile generates power at a level under 100 KW. The chemistry of decontamination is not included. (47-1)

4. Information on small reactors may be released (declassified) if it is of a particular value for teaching the basic principles of small reactors. This excludes the release of information on the design of small reactors. (47-1)

5. The neutron fluxes for the following reactors only (48-1):

United States

Argonne National Laboratory

CP-1 (graphite)

CP-2 (graphite)

CP-3 (heavy water)

Clinton Laboratory

Graphite Air Cooled Pile

Los Alamos Laboratory

Low Power Water Boiler

High Power Water Boiler

United Kingdom

Harwell

GLEEP

BEPO

Canada

Chalk River

ZEEP

NRX

a. The design power of these reactors may also be declassified but in no event are actual operating power levels to be released. Neutron distributions in space should be limited to smooth trends without details which might reveal lattice cell sizes. The external dimensions of these reactors and the thickness of shielding may be revealed. (48-1)

b. The dimensions, neutron fluxes and velocity distributions of the thermal columns for all of the reactors listed above. (48-1)

6. The dimensions of lattices, rods and their assemblies, and of the hole diameters through which the rods are mounted for the following reactors: (50-1)

United States - Argonne National Lab CP-3 (Heavy Water)

7. The critical mass of the reactors listed in IV.A.5. above. (50-4)

8. ("Class I" REACTORS) All information necessary for the design, construction and operation of the following reactors as designed at January 1, 1950, but not necessarily the results of work done with the reactor. (50-3 and 50-4)

United States

Argonne National Laboratory

CP-1 (graphite, natural uranium)

CP-2 (graphite, natural uranium)

CP-3 (heavy water, natural uranium)

Los Alamos Scientific Laboratory

Low Power Water Boiler (light water, enriched uranium)

High Power Water Boiler (light water, enriched uranium) versions 1, 2, and 3

United Kingdom

Harwell - GLEEP (graphite, natural uranium)

Canada

Chalk River - ZEEP (heavy water, natural uranium)

9. ("Class II" REACTORS) The following reactors are primarily used for research purposes but incorporate features of value in the design of production, power or mobile reactors ("Class III" reactors). For Class II reactors, only certain features can be declassified while other features must remain classified. (50-3 and 50-4)

United States

Brookhaven National Laboratory

Graphite Air Cooled Reactor

Oak Ridge National Laboratory

Graphite Air Cooled Reactor

Los Alamos Scientific Laboratory

Plutonium Fast Reactor

United Kingdom: Harwell - BEPO

Canada: Chalk River, N.R.X. Pile

10. Critical mass of Class II reactors on an individual basis to facilitate the teaching of reactor technology in universities and engineering institutions. (53-6)

B. ENRICHED REACTORS:

1. The qualitative characteristics of fast, intermediate and thermal reactors, provided that such information was of the same general type as has already been released on natural uranium reactors and provided it does not reveal information about composition and design of projected reactors or about relative merits of individual materials of construction or about relative merits of possible combinations of materials. (50-1)

2. The qualitative principles of breeding, but excluding numerical information on actual gain factors likely to be achieved. Whether a particular system will not breed is not declassifiable. (50-1)

3. Examples of possible moderators, ceramics, coolants, and structural materials but not including information about composition and design of projected reactors or about relative merits of individual materials of construction or about relative merits of possible combinations of materials. (50-1)

4. The general problems of refueling but not to include any detailed information on chemical reprocessing. (50-1)

C. EXPERIMENTAL BREEDER REACTORS

1. The power density is 250 KW per liter. (52-2)

2. The reactor core is the approximate size of a regulation football field. (52-2)

3. The neutron flux is approximately 10¹⁴ neutrons/sq. cm/sec. (52-2)

4. The coolant is sodium potassium alloy. (52-2)

5. Electromagnetic pumps and flow meters are used in the liquid metal circuits. (52-2)

6. The temperature of the coolant leaving the reactor is 350 degrees C. (52-2)

7. Super-heated steam of 400 psi pressure is generated in a boiler heated by sodium-potassium alloy. (52-2)

8. The generator is of 250 KW size and excess electrical power not required by the reactor is used for building service or dissipated to the atmosphere by electrical heaters. (52-2)

9. The power load required to operate the reactor is approximately 85 KW. (52-2)

D. EFFECTS OF RADIATION IN REACTOR DESIGN (See also I.C.10.)

1. All theory on the effects of radiation on materials except for theoretical recipes specifically intended to fit substances of special significance to the Project. (Care should be taken that classified experimental information is not revealed either by inclusion or by implication.) (50-4)

2. All effects of radiation on all substances except as limited by topics 10-112 through 10-116 [Note 4]; for example: (50-4)

a. Electrical thermal conductivities, except for materials of special interest for reactors, such as possible refractories.

b. Hall effect.

c. All effects in semi-conductors.

d. Mechanical properties. See topic 10-116 [Note 4].

e. Transition effects and metastable phases in general.

f. Irreversible (metastable) effect on the crystal lattice, i.e., lattice disordering and studies of stored energy associated therewith.

g. Effects of radiation on chemical processes, except as excluded by topics 10-113 [Note 4], 10-114 [Note 4] and 10-240 [Note 5]. (See also topic 1-240.[Note 6])

3. All shielding studies except: (50-4)

a. Shielding studies carried out with neutrons from a reactor.

b. Complete reactor shields.

c. Details of reactor shields, including such items as heat generation and removal within shields, apertures, labyrinths, ducts, plugs, etc., whensuch design details reveal the design criteria or the overall design of specific reactor shields.

d. Detailed discussion of distribution of various shield elements for reactor shielding purposes.

NOTE: The above exceptions do not refer to the reactors listed in paragraph IV.A.5. Rather, it is the intent of these exceptions to classify advances in the solution of the problem of developing a shield of limited weight and/or size for submarine and aircraft reactors.

E. LIQUID METAL COOLANTS

1. Laboratory-scale corrosion data in the absence of reactor or simulated reactor radiation. This includes static, dynamic and other types of corrosion data in monometallic or small multimetallic systems except corrosion data involving uranium and plutonium. (50-4)

2. Basic theoretical and experimental heat transfer and pressure-drop data of simple round-tube, flat-plate, or annuli configurations, including constructional details of laboratory equipment used, provided that the actual construction details of a reactor or full-scale heat exchanger are not revealed. (50-4)

3. Any component part of a large-scale liquid metal heat transfer system except for drawings, design data, and performance and operating data of individual components of the large-scale liquid metal heat transfer system insofar as they reveal details of the reactor, their relationship to a reactor coolant system or the over-all design. (50-4)

4. Applications of liquid metal coolants in connection with uses other than as primary or secondary reactor coolants. (50-4)

5. The revelation of interest in a given element or alloy as a heat transfer fluid provided that no reference is made to the special reactor or the reactor system for which this element or alloy is intended. (50-4)

6. The remaining classified technology developed in the Lithium Cooled Reactor Experiment (LCRE) and the SNAP-50 program. (73-3) (See also IV.J.11.d.)

F. ARMY NUCLEAR POWER PACKAGE PROGRAM

1. Fact that application of nuclear energy to production of electric and other power to meet military needs is under investigation. (53-4)

2. Fact that program is joint effort of Army and AEC. (53-4)

3. Contractor involved. (53-4)

4. Reactor concepts being considered for use. (53-4)

5. All equipment within the reactor container (Reactor container is vessel inclosing nuclear reactor and its controls together with primary coolant contained therein) and designed data pertaining to this equipment is classified except:

a. Fact that a particular material is to be studied as coolant. (53-4)

b. Fact that a particular type of fuel is being considered for use. (53-4)

c. Control activating mechanisms except as they reveal dimensions and size of core, location and nature of control elements and nature of control problem. (53-4)

d. Reactor container except as it reveals design of core, reflector and control. (53-4)

6. Declassification of all information concerning the Army Nuclear Power Package except the following: (55-3)

a. Information revealing strategic defense plans (i.e., the fact that such a reactor is to be located at a specific defense outpost, etc.).

b. Information revealing the non-declassifiable nuclear properties of fuel materials (i.e., on the cross-section of U-235 for neutrons having an energy above .1 Mev).

c. Information revealing the exact degree of U-235 enrichment if the assay is greater than 90%.

d. Information on the methods to be used to inhibit, control, or alleviate the effects of radiation on materials to be used in the construction of the reactor.

e. The methods developed to fabricate the fuel elements.

f. The method to be used to inhibit or control corrosion, erosion, crud formation, or activity in the coolant stream.

g. Information developed as a result of shielding studies which materially helps solve the problem of developing a shield of limited size and/or weight.

7. All information concerning the design and associated technology developed to date for the Military Compact Reactor concept. (67-7)

G. CONTROLLED THERMONUCLEAR PROGRAM - PROJECT SHERWOOD

1. The AEC interest in Project Sherwood and the identification of the sites at which the work is underway. (55-5)

2. The fact that Sherwood work is concerned with thermonuclear reactions between "the isotopes of hydrogen." (55-5)

3. Code names e.g., Sherwood etc. and their association with thermonuclear reactions between isotopes of hydrogen. (57-2)

a. Possibility of direct conversion of above phenomena to heat. (57-2)

b. Possibility of direct conversion of above phenomena to electrical energy. (57-2)

4. General Scientific Information

a. Design of present or future models revealing components or portions which do not disclose the connection of such items in the CTR program. (55-5)

b. Detectors and diagnostic equipment by themselves (and not revealing their connection to the Sherwood program). (55-5)

c. Energy balance considerations based on Maxwellian distributions. (57-2)

d. All theoretical analyses of the equilibrium of a quiescent pinch. (57-2)

e. Theory of hydrodynamic and hydromagnetic shock waves. (57-2)

f. Widely known techniques for achieving high temperatures such as shock tubes and simple discharges. (57-2)

g. Fundamental experiments, but excluding any method developed for the achieving of high plasma temperatures which represent a significant step on the road to the production of a C.T.R. (57-2)

h. Designs of components of portions of present or future models which do not disclose the connection of such items in the C.T.R. program. (57-2)

i. General Theory of diffusion of ions in a magnetic field. (57-2)

j. Scientific investigations of a general nature on plasma instability. (57-2)

k. Existence and theory of simple pinch effect. (57-2)

l. Existence and theory of skin effect in an ionized gas. (57-2)

m. Fact of production of thermonuclear neutrons. (57-2)

n. Technology of energy storage and release, using capacitors, homopolar generators, Kapitza-type batteries, or electric guns when not specifically associated with classified C.T.R. devices. (57-2)

o. Methods of measurement not revealing significant information concerning classified C.T.R. devices. (57-6)

p. The design, construction, performance, or operating characteristics of other C.T.R. devices. For example: (57-6)

(1) Nuclear reaction rates

(2)Theoretical studies

(3) Models

(4) Plasma densities

(5) Magnetic field configurations

5. Programs Involving Pinch Effect

a. Experimental work in the pinch effect prior to May 1, 1956 (such as Columbus, Perhapsatron, Cousins and Ware). (57-2)

b. Theoretical work on controlling instabilities by applied uniform axial magnetic fields produced by direct current. (57-2)

6. Stellarator Program

a. Conventional radio frequency excitation of plasma (electrodeless discharge). This does not mean magnetic pumping. (57-2)

b. Frequency of, and power for, magnetic pumping components when unrelated to C.T.R. apparatus. (57-2)

7. Magnetic Mirror

a. Switching methods. (57-2)

b. Shock wave experiments (if unrelated to the rest of the program). (57-2)

8. Declassification of the controlled thermonuclear reactor project (Project Sherwood). Any device employing thermonuclear reactions which has a weapons application will remain classified. (58-7)

9. All information on controlled fusion. (59-3)

H. OTHER CIVILIAN NUCLEAR POWER

1. Certain data concerning natural and slightly enriched uranium reactors necessary in studying the feasibility of power reactors. (53-6)

2. Fabrications of fuel elements--limited to U-Al elements, and uranyl sulphate solutions for a homogeneous reactor. (55-1)

3. Certain data concerning reactors necessary in studying the feasibility of power reactors. (55-2)

4. Additional information concerning research reactors including necessary fuel element fabrication techniques. (55-2)

5. Production technology not important to classified programs. (55-2)

6. All information necessary to the design, construction, and operation of civilian power reactors with the exception of that information primarily applicable to military propulsion, production reactors, or Army Package Power Reactors. (56-6)

7. Information relating to the chemical processing of reactor fuels and blanket materials irradiated in civilian power reactors. (56-6) (See also I.C.20)

8. All nuclear data (concerning reactor technology) except that which has or may have significance to the weapons program. (56-6)

9. All chemistry and chemical processing except that revealing the quantities and specifications of the materials that are produced primarily for military purposes. (59-3) (See also I.C.21)

10. All work and information originated in the civilian reactor field for civilian purposes, provided no classified information from other sources is incorporated in the work or information. (61-1)

11. Information developed in the Medium Power Reactor Experiment (MPRE) program. (67-12)

I. PRODUCTION REACTORS

1. The power level (thermal MW) of the NPR. (59-2)

2. The following information concerning the New Production Reactor (N-Reactor). (65-2)

a. Operating power level

b. Pu production that can be calculated from the operating power level and previously declassified information

c. Steam flow rate

d. Steam and condensate temperatures and pressure

e. Steam availability

f. Total water flow

g. Inlet and outlet water temperatures and pressures

h. Average neutron flux

i. Time operating efficiency

3. The uranium content of irradiated NPR fuel elements which have been determined by the Director, Division of Production, to be non-representative of routine NPR dual purpose production. (65-6)

4. Nominal power levels during reactor operation and corresponding flux levels. (68-2)

a. All Savannah River Reactors - each 2000 MW

b. Small Hanford Reactors - each 1500 MW

c. Hanford K-Reactors - each 4000 MW

5. Reactor production capabilities for certain isotopes (excluding Pu-239 and tritium) based on nominal power levels so that one could reveal the extent to which these isotopes, having specific peaceful applications, could be produced on a large scale. (68-2)

6. Unit costs for production of certain isotopes (excluding Pu-239 and tritium) having peaceful applications, when not revealing production rates (or costs of weapon materials) more accurately than estimates derivable from the nominal reactor power levels. (68-2)

7. Integrated and/or peak flux for specific tubes in a reactor, provided it does not reveal actual reactor power level or actual production rates of material for military use. (68-2)

8. Value of average flux in specific tubes, or time cycles, when influencing a particular experiment but not revealing time operated efficiency of the reactor. (68-2)

9. Location of specific tests within a reactor when this does not reveal flux pattern or flux distribution for the reactor. (68-2)

10. Coolant flow rates and temperature rises corresponding to declassified nominal power levels -- Hanford only (those for Savannah River will remain classified): (68-2)

Small Hanford Reactors
	Nominal coolant flow	84,000 gpm
	Nominal Temperature	68� C
Hanford K-Reactors
	Nominal coolant flow	210,000 gpm
	Nominal temperature rise	72� C

11. Items of less sensitive reactor technology, not related to power levels or production rates, would also become unclassified such as: (68-2)

a. Zoning of grades and stacking patterns for graphite

b. Dimensions of thermal or biological shield

c. Design features of shield, such as apertures, labyrinths, ducts, plugs, cooling tubes, and taper bore process tube entry

d. Percentage composition of reactor atmosphere and relations of atmosphere to graphite temperature, growth and annealing

12. The following information concerning N-Reactor: (71-5)

a. Power levels of the N-Reactor before December 1, 1965.

b. All N-Reactor production and production rate information.

c. All direct and residual costs of operating N-Reactor such as:

(1) The cost of fuel element manufacture at Fernald and Ashtabula.

(2) The cost of operating the extrusion line.

(3) The cost of running the reactor.

(4) The cost of reprocessing.

13. Total quantities of Krypton and Xenon per site as released to the atmosphere as a result of the operation of production reactors and associated operations at Hanford, Idaho Falls and Savannah River beginning March 1, 1971. (71-6)

14. The fact that we do not now trap Krypton and/or Xenon produced in production reactors and associated operations. (71-6)

a. Krypton and Xenon releases from F and H canyons [at the Savannah River Site] and whether any rare gases were or were not trapped prior to March 1, 1971. (94-9)

15. Items of N-reactor technology (including fuel fabrication) not previously declassified. (72-1)

Note: This action does not apply to production reactors other than N-reactor.

16. The Hot Die Size (HDS) process for cladding fuel and target elements, including the end bonding operation. (85-2)

17. Historical plutonium production information and associated rare gas releases for the decommissioned production reactors at the Hanford site for the period 1944 through 1960. (89-4) (See also II.M.27.)

18. Information concerning Hanford reactors:

a. Plutonium production and associated reprocessed quantities of products and rare gas releases, from 1961 to the shutdown of the decommissioned Richland reactors, and Hanford-produced tritium quantities. This action will declassify all Hanford weapons materials production quantities from the decommissioned reactors and amounts recovered. Comparisons with Savannah River production and any associations with intelligence activities will remain classified. (92-1)

b. All process times, temperatures, pressures, and classified compositional parameters for the early Hanford-developed cladding and canning technology including the hot press bonding, triple dip, lead dip (including the similar parameters for the Savannah River triple dip and lead dip processes), and the unbonded "B" and "C" processes. (92-1)

19. Information concerning Savannah River reactors:

a. The total quantity of weapons grade plutonium including supergrade plutonium produced at the Savannah River Plant. (93-5) (See also II.M.32.)

b. The historical quantity of plutonium produced for any time period in the Savannah River reactors and information that only reveals Pu production. (94-9) (See also II.M.40.)

c. The quantity of plutonium separated, or otherwise modified, to other forms (such as oxide or metal) at the Savannah River Plant during any time period. (94-9) (See also II.M.41.)

J. MISCELLANEOUS REACTOR TOPICS

1. Materials Test Reactor (MTR) and Low Intensity Test Reactor (LITR)

a. The thermal neutron and gamma flux distribution in all experimental holes outside the reactor core. (53-3)

b. The fast neutron flux available for irradiation experiments. (53-3)

c. The design power; the design inlet and outlet water temperature and water flow rate. (53-3)

d. The reactor cooling system (primary cooling system) external to the reactor tank, except for specific points of sabotage vulnerability, andexcepting data on procedures used to insure quality control of water and data on the effects of radiation on decomposition of water as well as on the corrosive action of water. (53-3)

e. Auxiliary reactor systems such as the raw water and air system (except sabotage vulnerability points). (53-3)

f. Description of the reactor container per se except insofar as it reveals details of the core reflector, the core cooling system, and controls. (53-3)

g. Identification of materials used as moderator or reflector, or for structural support (no elaboration beyond mere identification). (53-3)

h. All side faces of the reactor; the reactor top with the top plug in place. (53-3)

i. The general type of control rods (except sabotage vulnerability points). (53-3)

j. The control actuating mechanisms (insofar as they do not reveal core details and specific nature and location of control elements, and excepting sabotage vulnerability points). (53-3)

k. The shield composition, geometry, and method of cooling, not including radiation attenuation data. (53-3)

l. Descriptions of beam holes and associated equipment (pneumatic tubes, "rabbits", etc.). (53-3)

m. Description of thermal column. (53-3)

n. Existence of holes in beryllium reflector, located in the region of maximum thermal nuclear flux and provided with cooling water at reactor coolant temperature. (53-3)

2. Operating and performance data for the lattice and fuel elements. (54-1)

3. Data on procedures used to insure quality control of water. (54-1)

4. Data on the effects of radiation on reactor components and on the decomposition of water as well as on the corrosive action of water. (54-1)

5. The technology of fabrication and testing of fuel elements including specifications of fissionable material contained therein. (54-1)

6. The isotopic content of the plutonium fuel used in the Plutonium Recycle Test Reactor and in the Plutonium Recycle Test Reactor Critical Facility. (61-3) (See also II.M.17.)

7. In the area of basic reactor materials research, i.e., the investigation of the property of materials, the work should be conducted on an unclassified basis. (62-3)

8. Information concerning the electric power reactor and isotopic heat source. (67-5)

SNAP 2, 4, 8, 10 and 10A

a. Detailed descriptions of key problems or their solutions;

b. Identification of specific technical difficulties causing schedule slippage;

c. Detailed reactor performance, including coolant outlet temperatures above 1350�F;

d. Fuel element fabrication processing and performance information, including the composition of improved fuel materials and additives;

e. Hydrogen retention barrier composition and techniques of application;

f. Details of hydriding process and welding techniques specifically developed for SNAP claddings;

g. Certain reactor subsystem design information; e.g., new control mechanisms, use of "honeycomb" in SNAP shields;

h. Changes in shield design or material which result in the development of a shield of reduced size and/or weight;

i. Processing and fabrication techniques specially developed for SNAP shield materials;

j. Significant new concepts and technology; and

k. Military mission data.

Isotopic Heat Source

Detailed specifications of the manufacturing processes for radioisotopic heat sources which reveal the effects of isotopic heat and radiation on the process.

9. The concept of a self-energized thermoelectric converter where a semi-conductor and Plutonium-238 (as an isotopic heat source material) are combined in an integral body of semi-conducting material and research and development work on such a device; provided significant advances, breakthroughs or information that reveals the fact or manner of use of these systems where necessary to protect information classified by the user agency are not revealed. (68-6)

10. Information concerning the compatibility of fuels and fuel containers above 1200� F for all radioisotope fuels. (69-4)

11. Space Electric Power Reactor Program:

a. Uranium-zirconium hydride reactor technology (SNAP). (72-3) (See also II.G.27.)

b. Thermionic converter reactor technology. (72-3)

c. Advance liquid metal cooled reactor technology. (72-3)

d. The remaining classified technology developed in the Lithium Cooled Reactor Experiment (LCRE) and the SNAP-50 program. (73-3) (See also IV.E.6.)

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