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If you are not located in the United States, you -will have to check the laws of the country where you are located before -using this eBook. - -Title: Army Pulse Radiation Facility - -Author: US Army - -Release Date: May 18, 2022 [eBook #68120] - -Language: English - -Produced by: Brian Coe, Lisa Corcoran, who supplied the scans, and the - Online Distributed Proofreading Team at - https://www.pgdp.net - -*** START OF THE PROJECT GUTENBERG EBOOK ARMY PULSE RADIATION -FACILITY *** - - - - - -Transcriber’s Notes: - - Underscores “_” before and after a word or phrase indicate _italics_ - in the original text. - Equal signs “=” before and after a word or phrase indicate =bold= - in the original text. - Illustrations have been moved so they do not break up paragraphs. - Typographical and punctuation errors have been silently corrected. - - - - -Army Pulse Radiation Facility - - -[Illustration] - - - - -Contents - - - Page No. - - The Concept 3 - The Facility 5 - The Reactor 7 - Exposure Locations and Performance Levels 11 - APRF User Support Facilities 17 - Instructions to Potential Users 20 - - Table I. - APRFR Core Design Data 8 - - Table II. - Typical APRFR Performance Levels 8 - - Table III. - APRFR Fluence and Flux Data 13 - - Table IV. - Nominal APRFR Leakage and U235 Fission Spectra 13 - - Table V. - Fluence-to-Dose Conversion Factors for APRFR Leakage Neutrons 14 - - Table VI. - Kerma and Kerma Rate in Tissue for APRFR Exposure Conditions 14 - - Table VII. - Kerma and Kerma Rate in Silicon for APRFR Exposure Conditions 15 - - Table VIII. - Neutron-to-Gamma Dose Ratios 15 - - Table IX. - APRF User Support Equipment 18 - - Army Pulse Radiation Facility - _U.S. Army Ballistic Research Laboratories_ - AMXRD-BTD - _Aberdeen Proving Ground, Maryland 21005_ - -[Illustration: Army Pulse Radiation Facility Location Map] - -[Illustration] - - - - -The Concept - - -The Army Pulse Radiation Facility (APRF) is designed to meet an -Army need for a facility located near the Eastern Seaboard capable -of providing large fast neutron and gamma radiation doses within -microseconds. This fast pulse radiation capability is necessary for -the determination of transient responses of materiel in nuclear -environments. - -The APRF increases Army capability by providing improved simulation of -radiative effects of a nuclear burst for studies of Army interest, and -provides a facility for testing Army materiel. Because of its location, -the APRF economically and efficiently serves the heavy concentration of -Army agencies and contractors located along the Eastern Seaboard. - -The design of the APRF is a direct outgrowth of projected user -requirements. Thus the reactor can be used both for high dose -irradiations of small objects, as a point source for radiation detector -studies, and irradiation of bulk objects. The former requirement led -to the incorporation of a 1½-inch OD “glory hole” running through -the center of the core, and providing a fast neutron fluence of -about 9 × 10¹⁴ neutrons per square centimeter per pulse. The latter -two requirements have resulted in the design of a large volume, -low-radiation backscatter Reactor Building. Provision is made for -moving the reactor both within the Reactor Building and to an outdoor -test site at heights variable up to 44 feet above ground by means of a -mechanical device called the reactor transporter. The reactor is also -capable of intermittent steady state operation in the kilowatt range -for classes of experiments requiring this mode of operation. - -[Illustration] - -[Illustration] - -[Illustration] - - - - -The Facility - - -The APRF is located on the military reservation of Aberdeen Proving -Ground (APG), in southeastern Harford County, Maryland. The Reactor -Building is at the center of the facility. - -This building is a windowless, circular structure with aluminum siding. -Inside, the building is 100 feet in diameter and 65 feet high. There -is a roll-up door in the south wall for the passage of the reactor -transporter to the outdoor test site and another in the west wall for -the access of vehicles to the building. A shielded stairway and maze -provides access from the underground Control Building. This concrete -structure provides radiological shielding for the personnel and -controls associated with the operation of the reactor and the conduct -of experiments. - -The area within a ~450-yard radius of the Reactor Building constitutes -the APRF high-radiation area defined by a 10-foot anti-personnel fence. -This high-radiation area is in turn surrounded by a nearly concentric -restricted area defined at its outer boundary by a barbed wire warning -fence at a radius of ~1500 yards from the Reactor Building. - -The Laboratory Building, located at the periphery of the restricted -area, houses the administrative and support personnel for the APRF. -Access to APRF is controlled at this point. - -[Illustration: APRF Reactor Core Assembly] - -[Illustration] - - - - -The Reactor - - -The reactor, (APRFR), is designed for both self-limited, -super-prompt-critical pulse operation and steady state operation. The -maximum available pulse has a yield of ~2.1 × 10¹⁷ fissions, while -steady state operation is limited to about 10 kilowatts by the reactor -core cooling system and activation of the core. - -[Illustration: High Yield Prompt Pulse Shape] - -The APRFR is an advanced version of the Health Physics Research -Reactor (HPRR) at Oak Ridge National Laboratory (ORNL), which has -been operating since 1962. ORNL has played a key role in the design -and testing of the APRFR. In pulse operation, the power level may -rise on periods as short as 10 microseconds. Electro-mechanical scram -systems are too slow to terminate such an excursion. Shutdown results -from increased neutron leakage due to fuel expansion, resulting in -a large prompt negative temperature coefficient of reactivity. This -self-limiting feature depends almost entirely on the thermal expansion -of the fuel alloy, and thus it is regarded as completely reliable and -safe. - -Following a pulse, additional reactor shutdown capability is provided -by a safety block which, when ejected from the core, reduces the -reactivity to about 20 dollars below delayed-critical. At lower yield -pulses, below about 6 × 10¹⁶ fissions, the safety block is ejected by -the electro-mechanical scram system in about 0.1 seconds after a pulse. -At higher yield pulses, the safety block is ejected in much shorter -times due to thermo-mechanical shock forces which cause the safety -block to bounce out. The large shutdown margin provided by the safety -block is also the primary design device for preventing accidental -criticalities during periods of reactor shutdown. - -The APRFR core is an unmoderated cylindrical assembly containing about -125 kilograms of an alloy of uranium 235 containing 10% molybdenum. The -actual core mass varies with the experiment. The core is cylindrical -and consists of two concentric annuli: a fixed outer shell of stacked -fuel discs bolted together with nine fuel bolts and Inconel nuts and -a movable inner safety block, also of fuel alloy. The 1½-inch OD -“glory hole” runs vertically through the center of the safety block. -Key reactor data is summarized in Tables I and II. The APRFR has been -operated during tests at ORNL at more than twice its design yield. - - - - -Table I. - -APRFR Core Design Data - - - Core Diameter 8.90 inches - Core Height[1] 8.0 inches - Fuel Alloy 90 wt % uranium - - 10 wt % molybdenum - Uranium-235 Enrichment 93.14% - Total Fuel Mass[2] 125 - Safety Block Mass 15.7 kg - Safety Block Height 8.06 inches - Safety Block Diameter 4.00 inches - Glory Hole Diameter 1.50 inches - Number of Control Rods Three - Core Cooling Forced Air - Number of Core Bolts Nine - Safety Block Reactivity Worth ~$20 - Pulse Rod Reactivity Worth ~$1.15 - Core Environment During Pulse Dry Nitrogen - Core Cooling Forced Air - -[1] This value varies with experimental environment of core. - -[2] This value varies with experimental environment of core. - - - - -Table II. - -Typical APRFR Performance Levels - - - PULSE MODE - Routine Yield 1.5 × 10¹⁷ fissions/pulse - Reactivity Insertion $1.10 - Pulse Half-Width 48 μsec - Initial Prompt Period 18 μsec - Maximum Fuel Temperature Rise 400°C - Temperature Coefficient -0.3 cents/°C - Maximum Available Yield ~2.1 × 10¹⁷ fissions/pulse - STEADY STATE MODE - Continuous Operation ~1 kw - Intermittent Operation ~10 kw - -Steady state power levels are limited by effectiveness of core cooling -system and core activation. - -[Illustration] - -[Illustration: APRF Floor Plan] - - - - -Exposure Locations and Performance Levels - - -The highest fluence and dose rates are available in the 1½-inch glory -hole. Since the reactor is supported from above by the transporter, the -areas around and below the core are also available for experiments. - -The core can be positioned by remote control anywhere within the range -of travel of the transporter. Vertical travel is limited to about 44 -feet above the Reactor Building floor level. Horizontal travel is -limited by the range of the rails on which the transporter travels. Six -pairs of rails extend radially from a turntable in the center of the -Reactor Building. These rails terminate within the Reactor Building, -except for one pair which extends 90 feet outside the building to an -outdoor test site. Each pair of rails defines one experimental location -where semi-permanent equipment and shielding can be set up without -tying up the entire reactor operation. - -Fluence and flux data for three typical exposure locations are given in -Table III. In the absence of reflecting material beyond 1 meter from -core center (position P3), these values fall off essentially as - - 1 - —— - R² - -where R is the distance to core center. Other performance data are -summarized in Tables IV through VIII. - -[Illustration] - -[Illustration] - -[Illustration] - -[Illustration] - - - - -Table III. - -APRFR Fluence and Flux Data - - - ------------------------------------------------------------------- - Routine Pulse Yield Maximum Pulse Yield - 1.5 × 10¹⁷ Fissions 2.1 × 10¹⁷ Fissions - ------------------------------------------------------------------- - Fluence, n/cm² - P1[3] 6.7 × 10¹⁴ 9.3 × 10¹⁴ - P2 2.0 × 10¹⁴ 2.8 × 10¹⁴ - P3 1.7 × 10¹² 2.4 × 10¹² - Flux Density, n/cm²/sec - P1 1.4 × 10¹⁹ 2.0 × 10¹⁹ - P2 4.3 × 10¹⁸ 6.0 × 10¹⁸ - P3 3.7 × 10¹⁶ 5.2 × 10¹⁶ - -[3] P1: Center of Glory Hole; P2: Core Surface (11.3 cm from Core -Center); P3: 1 meter from Core Center. - - - - -Table IV. - -Nominal APRFR Leakage and U235 Fission Spectra[4] - - - -------------------------------------------------------- - Energy Average APRFR U235 Fission - Group Energy Energy Spectrum Spectrum - Number Range Eₙ Fraction Fraction - n (Mev) (Mev) XₙΔEₙ XₙΔEₙ - -------------------------------------------------------- - 1 3.0-∞ 4.41 0.133 0.204 - 2 1.4-3.0 2.10 0.251 0.344 - 3 0.9-1.4 1.14 0.164 0.168 - 4 0.4-0.9 0.65 0.262 0.180 - 5 0.1-0.4 0.26 0.168 0.090 - 6 0-0.1 0.059 0.022 0.014 - ------------------- - SUM 1.000 1.000 - ------------------- - Mean Energy (Mev) ~1.55 ~1.8 - -[4] These values are approximate and meant for qualitative comparison -only. - - - - -Table V. - -Fluence-to-Dose Conversion Factors for APRFR Leakage Neutrons - - - -------------------------------------------------------------------- - Material Quantity Conversion Factor - -------------------------------------------------------------------- - Tissue Kerma 2.4 × 10⁻⁷ erg/gram - ----------- - neutron/cm² - - Tissue Maximum Absorbed Dose For 3.5 × 10⁻⁹ rad - ----------- - neutron/cm² - - Normally Incident Neutrons - Silicon Elastic Recoil Kerma 2.7 × 10⁻⁹ erg/gram - (~Permanent Effect) ----------- - neutron/cm² - - Silicon Ionization Kerma 2.9 × 10⁻⁹ erg/gram - (~Transient Effects) ----------- - neutron/cm² - - Silicon (Total) Kerma 5.6 × 10⁻⁹ erg/gram - ----------- - neutron/cm² - -------------------------------------------------------------------- - - - - -Table VI. - -Kerma and Kerma Rate in Tissue for APRFR Exposure Conditions - - - -------------------------------------------------------------------- - Routine Pulse Yield Maximum Pulse Yield - 1.5 × 10¹⁷ Fissions 2.1 × 10¹⁷ Fissions - -------------------------------------------------------------------- - Kerma in Tissue - (ergs/gm) - P1[5] 1.6 × 10⁸ 2.2 × 10⁸ - P2 4.9 × 10⁷ 6.8 × 10⁷ - P3 4.1 × 10⁵ 5.7 × 10⁵ - - Kerma Rate in Tissue - (ergs/gm/sec) - P1 3.5 × 10¹² 4.7 × 10¹² - P2 1.1 × 10¹² 1.5 × 10¹² - P3 8.8 × 10⁹ 1.2 × 10¹⁰ - -[5] P1: Center of Glory Hole; P2: Core Surface; P3: 1 Meter from Core -Center. - -[Illustration] - -[Illustration] - -[Illustration] - -[Illustration] - - - - -Table VII. - -Kerma and Kerma Rate in Silicon for APRFR Exposure Conditions - - - -------------------------------------------------------------------- - Routine Pulse Yield Maximum Pulse Yield - 1.5 × 10¹⁷ Fissions 2.1 × 10¹⁷ Fissions - -------------------------------------------------------------------- - Total Kerma in Silicon, - ergs/gm[6] - P1[7] 2.7 × 10⁶ 5.2 × 10⁶ - P2 1.1 × 10⁶ 1.6 × 10⁶ - P3 9.5 × 10³ 13.3 × 10³ - Total Kerma Rate in - Silicon, (ergs/gm/sec) - P1 5.8 × 10¹⁰ 11.0 × 10¹⁰ - P2 2.4 × 10¹⁰ 3.5 × 10¹⁰ - P3 2.0 × 10⁸ 2.9 × 10⁸ - -[6] Ionization and elastic recoil processes contribute roughly equal -amounts to the total kerma. - -[7] P1: Center of Glory Hole; P2: Core Surface; P3: 1 Meter from Core -Center. - - - - -Table VIII. - -Neutron-to-Gamma Dose Ratios[8] - - - ----------------------------------------------------------------- - neutron rads tissue n/cm²/sec - ------------------- ----------------- - gamma rads tissue gamma rads tissue - ----------------------------------------------------------------- - Core Center (P1) 10 2.7 × 10⁹ - Core Surface (P2) 10 2.7 × 10⁹ - 1 Meter from Core Center (P3) 9 3.3 × 10⁹ - 10 Meters from Core Center 7 2.5 × 10⁷ - -[8] Representative data. Actual values influenced by core operating -history. - -[Illustration: Cross Section of Reactor Building] - - - - -APRF User Support Facilities - - -APRF is designed and staffed to assist its users in all key areas -relating to reactor utilization. - -=Physical Space= Several areas in the underground Control Building -are available to experimenters. These include the trailer tunnel with -room for two full-sized trailers, the data acquisition room, and the -instrument shop. All of these areas are provided with conduits so that -cables can be run directly to them from the Reactor Building. In the -trailer tunnel the minimum cable length required to run to the core -surface is about 30 feet. - -The exposure areas in the Reactor Building and the outdoor test site -are equipped with conduits for communication and instrumentation cables. - -Available areas in the Laboratory Building include a high-bay set -up area, a machine shop, laboratory space, fume hood with remote -manipulator, photography laboratory, and offices. - -=Data Acquisition and Processing= The basic element here is the -APRF Data Acquisition System described in Table IX. Various other -instrumentation is available as summarized in Table IX. Data processing -is available at the ARDC computer center and with on-line equipment at -APRF. - -=Dosimetry= Routine dosimetry is performed by APRF personnel. -Methods available include fluence and spectrum measurements using -foil techniques, glass rod microdosimetry, thermoluminescence, and -diverse active dosimeters. Foils are analyzed using the APRF Automatic -Dosimetry System and data are available within a short time following -exposure. - -Measurements are supplemented by analytical methods including one -and two dimensional transport theory, Monte Carlo, and special foil -analysis codes. - -=Staff= The APRF staff is available to guide, plan and set up -experiments at the reactor, perform dosimetry, and assist in data -acquisition. APRF participation is determined on a case-by-case basis. - -=Health Physics= Health physics survey, monitoring, decontamination -and related services are available in conjunction with the BRL Health -Physics Division. - - - - -Table IX. - -APRF User Support Equipment - - - -------------------------------------------------------------------- - =Transient Data Recording System= - -------------------------------------------------------------------- - TAPE RECORDERS: _Three each—14 track Honeywell Model 7600_ - - FREQUENCY: _DC to 80 kHz FM, 400 Hz to 700 kHz Direct_ - - SIGNAL _Universal Strain gauge and thermocouple with_ - CONDITIONING: _100 KC DC amplifiers_ - - TIME CODE: _IRIG A, 1 millisecond resolution_ - - PATCH PANELS: _Coaxial and triaxial connectors for all inputs_ - _and outputs, insulated shields._ - - AUTO CALIBRATION: _50 channel, 3 step_ - - CHANNEL ID: _Automatic ID in binary code_ - - PLAYBACK: _12” oscillograph_ - -------------------------------------------------------------------- - =Dosimetry= - -------------------------------------------------------------------- - Basic Foil Calibration System - - 5000 Curie Co-60 source - - Automated Sulfur, Fission Foil and Gamma Well Counting System, - 100 Samples each per cycle - - Eight channel active dosimeter system with digital read out and - computer analysis of neutron fluence and energy - - Toshiba Glass Rod and Harshaw TLD Gamma System - -------------------------------------------------------------------- - =Computer= - -------------------------------------------------------------------- - 16 bit/16K memory with foreground/background operation. Automatic - acquisition and reduction of foil counting data on-line. On-line - monitoring of reactor power pulse with analysis of peak, half-width - and yield. On-line monitoring of active dosimeters with data - reduction. Real time/Fortran IV. - -------------------------------------------------------------------- - =General Equipment= - -------------------------------------------------------------------- - 3300 Nuclear Data Multiparameter Analyzer, 4096 channel with - magnetic tape; RIDL 400 Channel Pulse Height Analyzer. - - Oscilloscopes, cameras, electronic calibration equipment. - - Hood areas with manipulators, photographic laboratory, radiation - monitoring equipment and services, machine shop. - -------------------------------------------------------------------- - -[Illustration] - -[Illustration] - -[Illustration] - -[Illustration] - -[Illustration] - - - - -Instructions To Potential Users - - -It is imperative to realize that there are stringent safety -requirements connected with the use of the APRFR. All experiments will -follow a written test plan approved at APRF. In order to perform an -experiment with maximum usefulness and efficiency, it is essential -that APRF be contacted during the early planning stages of a potential -experiment. Failure to do this may result in erroneous experiment -planning as regards safety and use of exposure space resulting in -schedule delays, and possibly cancellation or drastic revision of the -experiment. - -_For further information contact_: - - Commanding Officer - U.S. Army Ballistic Research Laboratories - ATTN: AMXRD-BTD, Facility Coordinator - Aberdeen Proving Ground, Maryland 21005 - -*** END OF THE PROJECT GUTENBERG EBOOK ARMY PULSE RADIATION -FACILITY *** - -Updated editions will replace the previous one--the old editions will -be renamed. - -Creating the works from print editions not protected by U.S. copyright -law means that no one owns a United States copyright in these works, -so the Foundation (and you!) can copy and distribute it in the -United States without permission and without paying copyright -royalties. 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