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diff --git a/.gitattributes b/.gitattributes new file mode 100644 index 0000000..d7b82bc --- /dev/null +++ b/.gitattributes @@ -0,0 +1,4 @@ +*.txt text eol=lf +*.htm text eol=lf +*.html text eol=lf +*.md text eol=lf diff --git a/LICENSE.txt b/LICENSE.txt new file mode 100644 index 0000000..6312041 --- /dev/null +++ b/LICENSE.txt @@ -0,0 +1,11 @@ +This eBook, including all associated images, markup, improvements, +metadata, and any other content or labor, has been confirmed to be +in the PUBLIC DOMAIN IN THE UNITED STATES. + +Procedures for determining public domain status are described in +the "Copyright How-To" at https://www.gutenberg.org. + +No investigation has been made concerning possible copyrights in +jurisdictions other than the United States. Anyone seeking to utilize +this eBook outside of the United States should confirm copyright +status under the laws that apply to them. diff --git a/README.md b/README.md new file mode 100644 index 0000000..6cdd3ef --- /dev/null +++ b/README.md @@ -0,0 +1,2 @@ +Project Gutenberg (https://www.gutenberg.org) public repository for +eBook #68120 (https://www.gutenberg.org/ebooks/68120) diff --git a/old/68120-0.txt b/old/68120-0.txt deleted file mode 100644 index 39abef1..0000000 --- a/old/68120-0.txt +++ /dev/null @@ -1,979 +0,0 @@ -The Project Gutenberg eBook of Army Pulse Radiation Facility, by US -Army - -This eBook is for the use of anyone anywhere in the United States and -most other parts of the world at no cost and with almost no restrictions -whatsoever. You may copy it, give it away or re-use it under the terms -of the Project Gutenberg License included with this eBook or online at -www.gutenberg.org. 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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You may copy it, give it away or re-use it under the terms -of the Project Gutenberg License included with this eBook or online -at <a href="https://www.gutenberg.org">www.gutenberg.org</a>. 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. -</div> - -<p style='display:block; margin-top:1em; margin-bottom:1em; margin-left:2em; text-indent:-2em'>Title: Army Pulse Radiation Facility</p> -<p style='display:block; margin-top:1em; margin-bottom:0; margin-left:2em; text-indent:-2em'>Author: US Army</p> -<p style='display:block; text-indent:0; margin:1em 0'>Release Date: May 18, 2022 [eBook #68120]</p> -<p style='display:block; text-indent:0; margin:1em 0'>Language: English</p> - <p style='display:block; margin-top:1em; margin-bottom:0; margin-left:2em; text-indent:-2em; text-align:left'>Produced by: Brian Coe, Lisa Corcoran, who supplied the scans, and the Online Distributed Proofreading Team at https://www.pgdp.net</p> -<div style='margin-top:2em; margin-bottom:4em'>*** START OF THE PROJECT GUTENBERG EBOOK ARMY PULSE RADIATION FACILITY ***</div> - -<hr class="chap x-ebookmaker-drop" /> -<h1>Army Pulse Radiation Facility</h1> - -<div class="figcenter"> - <img src="images/frontispiece.jpg" alt="" width="600" height="615" /> -</div> -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<h2 class="nobreak">Contents</h2> -</div> - -<table class="fontsize_120" border="0" cellspacing="0" summary="TOC" cellpadding="0" > - <tbody><tr> - <td class="tdl"> </td> - <td class="tdr"><small>Page No.</small></td> - </tr><tr> - <td class="tdl">The Concept</td> - <td class="tdr"><a href="#Page_3"> 3</a></td> - </tr><tr> - <td class="tdl">The Facility</td> - <td class="tdr"><a href="#Page_5"> 5</a></td> - </tr><tr> - <td class="tdl">The Reactor</td> - <td class="tdr"><a href="#Page_7"> 7</a></td> - </tr><tr> - <td class="tdl">Exposure Locations and Performance Levels</td> - <td class="tdr"><a href="#Page_11">11</a></td> - </tr><tr> - <td class="tdl">APRF User Support Facilities</td> - <td class="tdr"><a href="#Page_17">17</a></td> - </tr><tr> - <td class="tdl">Instructions to Potential Users</td> - <td class="tdr"><a href="#Page_20">20</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table I.</b></big></td> - </tr><tr> - <td class="tdl">APRFR Core Design Data</td> - <td class="tdr"><a href="#TABLE_I"> 8</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table II.</b></big></td> - </tr><tr> - <td class="tdl">Typical APRFR Performance Levels</td> - <td class="tdr"><a href="#TABLE_II"> 8</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table III.</b></big></td> - </tr><tr> - <td class="tdl">APRFR Fluence and Flux Data</td> - <td class="tdr"><a href="#TABLE_III">13</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table IV.</b></big></td> - </tr><tr> - <td class="tdl">Nominal APRFR Leakage and U235 Fission Spectra</td> - <td class="tdr"><a href="#TABLE_IV">13</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table V.</b></big></td> - </tr><tr> - <td class="tdl">Fluence-to-Dose Conversion Factors for APRFR Leakage Neutrons</td> - <td class="tdr"><a href="#TABLE_V">14</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table VI.</b></big></td> - </tr><tr> - <td class="tdl">Kerma and Kerma Rate in Tissue for APRFR Exposure Conditions</td> - <td class="tdr"><a href="#TABLE_VI">14</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table VII.</b></big></td> - </tr><tr> - <td class="tdl">Kerma and Kerma Rate in Silicon for APRFR Exposure Conditions</td> - <td class="tdr"><a href="#TABLE_VII">15</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table VIII.</b></big></td> - </tr><tr> - <td class="tdl">Neutron-to-Gamma Dose Ratios</td> - <td class="tdr"><a href="#TABLE_VIII">15</a></td> - </tr><tr> - <td class="tdc_space-above1" colspan="2"><big><b>Table IX.</b></big></td> - </tr><tr> - <td class="tdl">APRF User Support Equipment</td> - <td class="tdr"><a href="#TABLE_IX">18</a></td> - </tr> - </tbody> -</table> - -<p class="f120 space-above2 space-below2">Army Pulse Radiation Facility<br /> -<i>U.S. Army Ballistic Research Laboratories</i><br /> -AMXRD-BTD<br /><i>Aberdeen Proving Ground, Maryland 21005</i></p> - -<div class="figcenter"> - <img src="images/i_02.jpg" alt="" width="400" height="557" /> - <p class="f120 space-below2">Army Pulse Radiation Facility Location Map</p> - <img src="images/i_03.jpg" alt="" width="500" height="618" /> -</div> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<p><span class="pagenum" id="Page_3">[Pg 3]</span></p> -<h2 class="nobreak">The Concept</h2> -</div> - -<p>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.</p> - -<p>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.</p> - -<p>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. -<span class="pagenum" id="Page_4">[Pg 4]</span></p> - -<div class="figcenter"> - <img src="images/i_04a.jpg" alt="" width="400" height="610" /> - <img src="images/i_04b.jpg" alt="" width="600" height="427" /> - <img src="images/i_05.jpg" alt="" width="500" height="610" /> -</div> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<p><span class="pagenum" id="Page_5">[Pg 5]</span></p> -<h2 class="nobreak">The Facility</h2> -</div> - -<p>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.</p> - -<p>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.</p> - -<p>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.</p> - -<p>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. -<span class="pagenum" id="Page_6">[Pg 6]</span></p> - -<div class="figcenter"> - <img src="images/i_06a.jpg" alt="" width="600" height="671" /> - <p class="f120 space-below2">APRF Reactor Core Assembly</p> - <img src="images/i_06b.jpg" alt="" width="500" height="619" /> -</div> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<p><span class="pagenum" id="Page_7">[Pg 7]</span></p> - -<h2 class="nobreak" id="The_Reactor">The Reactor</h2> -</div> - -<p>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.</p> - -<div class="figcenter"> - <img src="images/i_07.jpg" alt="" width="500" height="523" /> - <p class="f120 space-below2">High Yield Prompt Pulse Shape</p> -</div> - -<p>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.</p> - -<p>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 -<span class="pagenum" id="Page_8">[Pg 8]</span> -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.</p> - -<p>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.</p> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<h2 class="nobreak" id="TABLE_I">Table I.</h2> -</div> - -<p class="f150"><b>APRFR Core Design Data</b></p> - -<table class="fontsize_120 no-wrap" border="0" cellspacing="0" summary="Table I" cellpadding="0" > - <tbody><tr> - <td class="tdl">Core Diameter</td> - <td class="tdr">8.90 inches</td> - </tr><tr> - <td class="tdl">Core Height<a id="FNanchor_1" href="#Footnote_1" class="fnanchor">[1]</a></td> - <td class="tdr">8.0 inches</td> - </tr><tr> - <td class="tdl">Fuel Alloy</td> - <td class="tdr">90 wt % uranium -  </td> - </tr><tr> - <td class="tdl"> </td> - <td class="tdr">10 wt % molybdenum</td> - </tr><tr> - <td class="tdl">Uranium-235 Enrichment</td> - <td class="tdr">93.14%</td> - </tr><tr> - <td class="tdl">Total Fuel Mass<a id="FNanchor_2" href="#Footnote_2" class="fnanchor">[2]</a></td> - <td class="tdr">125</td> - </tr><tr> - <td class="tdl">Safety Block Mass</td> - <td class="tdr">15.7 kg</td> - </tr><tr> - <td class="tdl">Safety Block Height</td> - <td class="tdr">8.06 inches</td> - </tr><tr> - <td class="tdl">Safety Block Diameter</td> - <td class="tdr">4.00 inches</td> - </tr><tr> - <td class="tdl">Glory Hole Diameter</td> - <td class="tdr">1.50 inches</td> - </tr><tr> - <td class="tdl">Number of Control Rods</td> - <td class="tdr">Three</td> - </tr><tr> - <td class="tdl">Core Cooling</td> - <td class="tdr">Forced Air</td> - </tr><tr> - <td class="tdl">Number of Core Bolts</td> - <td class="tdr">Nine</td> - </tr><tr> - <td class="tdl">Safety Block Reactivity Worth</td> - <td class="tdr">~$20</td> - </tr><tr> - <td class="tdl">Pulse Rod Reactivity Worth</td> - <td class="tdr">~$1.15</td> - </tr><tr> - <td class="tdl">Core Environment During Pulse</td> - <td class="tdr">Dry Nitrogen</td> - </tr><tr> - <td class="tdl">Core Cooling</td> - <td class="tdr">Forced Air</td> - </tr> - </tbody> -</table> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<h2 class="nobreak" id="TABLE_II">Table II.</h2> -</div> - -<p class="f150"><b>Typical APRFR Performance Levels</b></p> - -<table class="fontsize_120 no-wrap" border="0" cellspacing="0" summary="Table II" cellpadding="0" > - <tbody><tr> - <td class="tdl"><b>PULSE MODE</b></td> - <td class="tdr"> </td> - </tr><tr> - <td class="tdl">Routine Yield</td> - <td class="tdr">1.5 × 10¹⁷ fissions/pulse</td> - </tr><tr> - <td class="tdl_ws1">Reactivity Insertion</td> - <td class="tdr">$1.10</td> - </tr><tr> - <td class="tdl_ws1">Pulse Half-Width</td> - <td class="tdr">48 μsec</td> - </tr><tr> - <td class="tdl_ws1">Initial Prompt Period</td> - <td class="tdr">18 μsec</td> - </tr><tr> - <td class="tdl_ws1">Maximum Fuel Temperature Rise</td> - <td class="tdr">400°C</td> - </tr><tr> - <td class="tdl_ws1">Temperature Coefficient</td> - <td class="tdr">-0.3 cents/°C</td> - </tr><tr> - <td class="tdl bb">Maximum Available Yield</td> - <td class="tdr bb">~2.1 × 10¹⁷ fissions/pulse</td> - </tr><tr> - <td class="tdl"><b>STEADY STATE MODE</b></td> - <td class="tdr"> </td> - </tr><tr> - <td class="tdl">Continuous Operation</td> - <td class="tdr">~1 kw</td> - </tr><tr> - <td class="tdl">Intermittent Operation</td> - <td class="tdr">~10 kw</td> - </tr><tr> - <td class="tdl"></td> - <td class="tdr"></td> - </tr><tr> - <td class="tdl"></td> - <td class="tdr"></td> - </tr> - </tbody> -</table> - -<p class="blockquot space-above1 space-below2">Steady state power levels are -limited by effectiveness of core cooling system and core activation. -<span class="pagenum" id="Page_9">[Pg 9]</span></p> - -<div class="figcenter"> - <img src="images/i_08.jpg" alt="" width="600" height="446" /> -</div> - -<p><span class="pagenum" id="Page_10">[Pg 10]</span></p> - -<div class="figcenter"> - <img src="images/i_10.jpg" alt="" width="600" height="328" /> - <p class="f120 space-below2">APRF Floor Plan</p> -</div> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<p><span class="pagenum" id="Page_11">[Pg 11]</span></p> -<h2 class="nobreak">Exposure Locations and Performance Levels</h2> -</div> - -<p>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.</p> - -<p>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.</p> - -<p>Fluence and flux data for three typical exposure locations are given -in <a href="#TABLE_III">Table III</a>. In the absence of reflecting -material beyond 1 meter from core center (position P3), these values -fall off essentially as</p> - -<ul class="index"> -<li class="isub3">1</li> -<li class="isub2">——</li> -<li class="isub3">R²</li> -</ul> - -<p class="no-indent space-below2">where R is the distance to core center. -Other performance data are summarized in Tables IV through VIII. -<span class="pagenum" id="Page_12">[Pg 12]</span></p> - -<div class="figcenter"> - <img src="images/i_12a.jpg" alt="" width="600" height="312" /> - <img src="images/i_12b.jpg" alt="" width="400" height="615" /> - <img src="images/i_12c.jpg" alt="" width="500" height="422" /> - <img src="images/i_13.jpg" alt="" width="400" height="658" /> -</div> - -<hr class="chap x-ebookmaker-drop" /> -<div class="chapter"> -<p><span class="pagenum" id="Page_13">[Pg 13]</span></p> -<h2 class="nobreak" id="TABLE_III">Table III.</h2> -</div> - -<p class="f150"><b>APRFR Fluence and Flux Data</b></p> - -<table class="fontsize_120 no-wrap" border="0" cellspacing="0" summary="Table III" cellpadding="0" > - <thead><tr> - <th class="tdc bb" colspan="3"> </th> - </tr><tr> - <th class="tdc bb"> </th> - <th class="tdc bb"> Routine Pulse Yield  <br />1.5 × 10¹⁷ Fissions </th> - <th class="tdc bb"> Maximum Pulse Yield <br />2.1 × 10¹⁷ Fissions</th> - </tr> - </thead> - <tbody><tr> - <td class="tdl" colspan="3"><b>Fluence, n/cm²</b></td> - </tr><tr> - <td class="tdc_ws2"> P1<a id="FNanchor_3" href="#Footnote_3" class="fnanchor">[3]</a></td> - <td class="tdc_ws2">6.7 × 10¹⁴</td> - <td class="tdc_ws2">9.3 × 10¹⁴</td> - </tr><tr> - <td class="tdc">P2</td> - <td class="tdc">2.0 × 10¹⁴</td> - <td class="tdc">2.8 × 10¹⁴</td> - </tr><tr> - <td class="tdc">P3</td> - <td class="tdc">1.7 × 10¹²</td> - <td class="tdc">2.4 × 10¹²</td> - </tr><tr> - <td class="tdl" colspan="3"><b>Flux Density, n/cm²/sec</b></td> - </tr><tr> - <td class="tdc">P1</td> - <td class="tdc">1.4 × 10¹⁹</td> - <td class="tdc">2.0 × 10¹⁹</td> - </tr><tr> - <td class="tdc">P2</td> - <td class="tdc">4.3 × 10¹⁸</td> - <td class="tdc">6.0 × 10¹⁸</td> - </tr><tr> - <td class="tdc">P3</td> - <td class="tdc">3.7 × 10¹⁶</td> - <td class="tdc">5.2 × 10¹⁶</td> - </tr><tr> - <td class="tdc bt" colspan="3"> </td> - </tr> - </tbody> -</table> - -<div class="chapter"> -<h2 class="nobreak" id="TABLE_IV">Table IV.</h2> -</div> - -<p class="f150"><b>Nominal APRFR Leakage and U235 Fission Spectra</b> -<a id="FNanchor_4" href="#Footnote_4" class="fnanchor"><small>[4]</small></a></p> - -<table class="fontsize_120 no-wrap" border="0" cellspacing="0" summary="Table IV" cellpadding="0" > - <thead><tr> - <th class="tdc bb" colspan="5"> </th> - </tr><tr> - <th class="tdc bb">Energy<br />Group<br /> Number <br /><big>n</big></th> - <th class="tdc bb"> <br /> Energy <br />Range<br />(Mev)</th> - <th class="tdc bb"> Average <br />Energy<br />Eₙ<br />(Mev)</th> - <th class="tdc bb">APRFR<br /> Spectrum <br />Fraction<br />XₙΔEₙ</th> - <th class="tdc bb"> U235 Fission<br />Spectrum<br />Fraction<br />XₙΔEₙ</th> - </tr> - </thead> - <tbody><tr> - <td class="tdc">1</td> - <td class="tdr">3.0-∞</td> - <td class="tdl_ws1">4.41</td> - <td class="tdc">0.133</td> - <td class="tdc">0.204</td> - </tr><tr> - <td class="tdc">2</td> - <td class="tdr">1.4-3.0</td> - <td class="tdl_ws1">2.10</td> - <td class="tdc">0.251</td> - <td class="tdc">0.344</td> - </tr><tr> - <td class="tdc">3</td> - <td class="tdr">0.9-1.4</td> - <td class="tdl_ws1">1.14</td> - <td class="tdc">0.164</td> - <td class="tdc">0.168</td> - </tr><tr> - <td class="tdc">4</td> - <td class="tdr">0.4-0.9</td> - <td class="tdl_ws1">0.65</td> - <td class="tdc">0.262</td> - <td class="tdc">0.180</td> - </tr><tr> - <td class="tdc">5</td> - <td class="tdr">0.1-0.4</td> - <td class="tdl_ws1">0.26</td> - <td class="tdc">0.168</td> - <td class="tdc">0.090</td> - </tr><tr> - <td class="tdc">6</td> - <td class="tdr">0-0.1</td> - <td class="tdl_ws1">0.059</td> - <td class="tdc bb">0.022</td> - <td class="tdc bb">0.014</td> - </tr><tr> - <td class="tdl"><b>SUM</b></td> - <td class="tdc"> </td> - <td class="tdc"> </td> - <td class="tdc bb">1.000</td> - <td class="tdc bb">1.000</td> - </tr><tr> - <td class="tdl" colspan="5">Mean</td> - </tr><tr> - <td class="tdl" colspan="5">Energy</td> - </tr><tr> - <td class="tdl">(Mev)</td> - <td class="tdc"> </td> - <td class="tdc"> </td> - <td class="tdc">~1.55</td> - <td class="tdc">~1.8</td> - </tr><tr> - <td class="tdl bt" colspan="5"> </td> - </tr> - </tbody> -</table> - -<div class="chapter"> -<p><span class="pagenum" id="Page_14">[Pg 14]</span></p> -<h2 class="nobreak" id="TABLE_V">Table V.</h2> -</div> - -<p class="f150"><b>Fluence-to-Dose Conversion Factors<br /> for APRFR Leakage Neutrons</b></p> - -<table class="fontsize_120 no-wrap" border="0" cellspacing="0" summary="Table V" cellpadding="0" > - <thead><tr> - <th class="tdc bb" colspan="4"> </th> - </tr><tr> - <th class="tdc bb">Material</th> - <th class="tdc bb">Quantity</th> - <th class="tdc bb" colspan="2">Conversion Factor</th> - </tr> - </thead> - <tbody><tr> - <td class="tdl">Tissue</td> - <td class="tdr">Kerma </td> - <td class="tdr_ws1">  2.4 × 10⁻⁷</td> - <td class="tdc bb"> erg/gram </td> - </tr><tr> - <td class="tdr" colspan="4">neutron/cm²</td> - </tr><tr> - <td class="tdc" colspan="4"> </td> - </tr><tr> - <td class="tdl">Tissue</td> - <td class="tdr">Maximum Absorbed Dose For</td> - <td class="tdr_ws1">3.5 × 10⁻⁹</td> - <td class="tdc bb">rad</td> - </tr><tr> - <td class="tdr" colspan="2">Normally Incident Neutrons</td> - <td class="tdr" colspan="2">neutron/cm²</td> - </tr><tr> - <td class="tdc" colspan="4"> </td> - </tr><tr> - <td class="tdl">Silicon</td> - <td class="tdr">Elastic Recoil Kerma</td> - <td class="tdr_ws1">2.7 × 10⁻⁹</td> - <td class="tdc bb">erg/gram</td> - </tr><tr> - <td class="tdr" colspan="2">(~Permanent Effect)</td> - <td class="tdr" colspan="2">neutron/cm²</td> - </tr><tr> - <td class="tdc" colspan="4"> </td> - </tr><tr> - <td class="tdl">Silicon</td> - <td class="tdr">Ionization Kerma</td> - <td class="tdr_ws1">2.9 × 10⁻⁹</td> - <td class="tdc bb">erg/gram</td> - </tr><tr> - <td class="tdr" colspan="2">(~Transient Effects)</td> - <td class="tdr" colspan="2">neutron/cm²</td> - </tr><tr> - <td class="tdc" colspan="4"> </td> - </tr><tr> - <td class="tdl">Silicon</td> - <td class="tdr">(Total) Kerma</td> - <td class="tdr_ws1">5.6 × 10⁻⁹</td> - <td class="tdc bb">erg/gram</td> - </tr><tr> - <td class="tdr" colspan="2"> </td> - <td class="tdr" colspan="2">neutron/cm²</td> - </tr><tr> - <td class="tdc bt" colspan="4"> </td> - </tr> - </tbody> -</table> - -<div class="chapter"> -<h2 class="nobreak" id="TABLE_VI">Table VI.</h2> -</div> - -<p class="f150"><b>Kerma and Kerma Rate in Tissue<br /> for APRFR Exposure Conditions</b></p> -<table class="fontsize_120 no-wrap" border="0" cellspacing="0" summary="Table VI" cellpadding="0" > - <thead><tr> - <th class="tdc bb" colspan="3"> </th> - </tr><tr> - <th class="tdc bb"> </th> - <th class="tdc bb"> Routine Pulse Yield  <br />1.5 × 10¹⁷ Fissions </th> - <th class="tdc bb"> Maximum Pulse Yield <br />2.1 × 10¹⁷ Fissions</th> - </tr> - </thead> - <tbody><tr> - <td class="tdl" colspan="3"><b>Kerma in Tissue (ergs/gm)</b></td> - </tr><tr> - <td class="tdc_ws2"> P1<a id="FNanchor_5" href="#Footnote_5" class="fnanchor">[5]</a></td> - <td class="tdc_ws2">1.6 × 10⁸</td> - <td class="tdc_ws2">2.2 × 10⁸</td> - </tr><tr> - <td class="tdc">P2</td> - <td class="tdc">4.9 × 10⁷</td> - <td class="tdc">6.8 × 10⁷</td> - </tr><tr> - <td class="tdc">P3</td> - <td class="tdc">4.1 × 10⁵</td> - <td class="tdc">5.7 × 10⁵</td> - </tr><tr> - <td class="tdc" colspan="3"> </td> - </tr><tr> - <td class="tdl" colspan="3"><b>Kerma Rate in Tissue (ergs/gm/sec)</b></td> - </tr><tr> - <td class="tdc">P1</td> - <td class="tdc">3.5 × 10¹²</td> - <td class="tdc">4.7 × 10¹²</td> - </tr><tr> - <td class="tdc">P2</td> - <td class="tdc">1.1 × 10¹²</td> - <td class="tdc">1.5 × 10¹²</td> - </tr><tr> - <td class="tdc">P3</td> - <td class="tdc">8.8 × 10⁹</td> - <td class="tdc">1.2 × 10¹⁰</td> - </tr><tr> - <td class="tdc bt" colspan="3"> </td> - </tr> - </tbody> -</table> - -<div class="figcenter"> - <img src="images/i_14a.jpg" alt="" width="300" height="534" /> - <img src="images/i_14b.jpg" alt="" width="600" height="353" /> - <img src="images/i_15a.jpg" alt="" width="600" height="488" /> - <img src="images/i_15b.jpg" alt="" width="600" height="448" /> -</div> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<p><span class="pagenum" id="Page_15">[Pg 15]</span></p> - -<h2 class="nobreak" id="TABLE_VII">Table VII.</h2> -</div> - -<p class="f150"><b>Kerma and Kerma Rate in Silicon<br /> for APRFR Exposure Conditions</b></p> -<table class="fontsize_120 no-wrap" border="0" cellspacing="0" summary="Table VII" cellpadding="0" > - <thead><tr> - <th class="tdc bb" colspan="3"> </th> - </tr><tr> - <th class="tdc bb"> </th> - <th class="tdc bb"> Routine Pulse Yield  <br />1.5 × 10¹⁷ Fissions </th> - <th class="tdc bb"> Maximum Pulse Yield <br />2.1 × 10¹⁷ Fissions</th> - </tr> - </thead> - <tbody><tr> - <td class="tdl" colspan="3"><b>Total Kerma in Silicon, ergs/gm</b><a id="FNanchor_6" href="#Footnote_6" class="fnanchor">[6]</a></td> - </tr><tr> - <td class="tdc_ws2"> P1<a id="FNanchor_7" href="#Footnote_7" class="fnanchor">[7]</a></td> - <td class="tdc_ws2">2.7 × 10⁶</td> - <td class="tdc_ws2"> 5.2 × 10⁶</td> - </tr><tr> - <td class="tdc">P2</td> - <td class="tdc">1.1 × 10⁶</td> - <td class="tdc"> 1.6 × 10⁶</td> - </tr><tr> - <td class="tdc">P3</td> - <td class="tdc">9.5 × 10³</td> - <td class="tdc">13.3 × 10³</td> - </tr><tr> - <td class="tdc" colspan="3"> </td> - </tr><tr> - <td class="tdl" colspan="3"><b>Total Kerma Rate in Silicon, (ergs/gm/sec)</b></td> - </tr><tr> - <td class="tdc">P1</td> - <td class="tdc">5.8 × 10¹⁰</td> - <td class="tdc">11.0 × 10¹⁰</td> - </tr><tr> - <td class="tdc">P2</td> - <td class="tdc">2.4 × 10¹⁰</td> - <td class="tdc"> 3.5 × 10¹⁰</td> - </tr><tr> - <td class="tdc">P3</td> - <td class="tdc">2.0 × 10⁸ </td> - <td class="tdc"> 2.9 × 10⁸</td> - </tr><tr> - <td class="tdc bt" colspan="3"> </td> - </tr> - </tbody> -</table> - -<div class="chapter"> -<h2 class="nobreak" id="TABLE_VIII">Table VIII.</h2> -</div> - -<p class="f150"><b>Neutron-to-Gamma Dose Ratios</b> - <a id="FNanchor_8" href="#Footnote_8" class="fnanchor"><small>[8]</small></a></p> -<table class="fontsize_120 no-wrap" border="0" cellspacing="0" summary="Table VIII" cellpadding="0" > - <thead><tr> - <th class="tdc bb2" colspan="4"> </th> - </tr><tr> - <th class="tdc"> </th> - <th class="tdc bb">neutron rads tissue</th> - <td class="tdc">  </td> - <th class="tdc bb">n/cm²/sec</th> - </tr><tr> - <th class="tdc bb2"> </th> - <th class="tdc bb2">gamma rads tissue </th> - <td class="tdc bb2"> </td> - <th class="tdc bb2"> gamma rads tissue</th> - </tr> - </thead> - <tbody><tr> - <td class="tdl">Core Center (P1)</td> - <td class="tdc">10</td> - <td class="tdc"> </td> - <td class="tdc">2.7 × 10⁹</td> - </tr><tr> - <td class="tdl">Core Surface (P2)</td> - <td class="tdc">10</td> - <td class="tdc"> </td> - <td class="tdc">2.7 × 10⁹</td> - </tr><tr> - <td class="tdl">1 Meter from Core Center (P3)</td> - <td class="tdc"> 9</td> - <td class="tdc"> </td> - <td class="tdc">3.3 × 10⁹</td> - </tr><tr> - <td class="tdl">10 Meters from Core Center</td> - <td class="tdc"> 7</td> - <td class="tdc"> </td> - <td class="tdc">2.5 × 10⁷</td> - </tr><tr> - <td class="tdc bt" colspan="4"> </td> - </tr> - </tbody> -</table> - -<p><span class="pagenum" id="Page_16">[Pg 16]</span></p> - -<div class="figcenter"> - <img src="images/i_16.jpg" alt="" width="600" height="441" /> - <p class="f120">Cross Section of Reactor Building</p> -</div> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<p><span class="pagenum" id="Page_17">[Pg 17]</span></p> -<h2 class="nobreak">APRF User Support Facilities</h2> -</div> - -<p>APRF is designed and staffed to assist its users in all key areas -relating to reactor utilization.</p> - -<p><b>Physical Space</b> 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.</p> - -<p>The exposure areas in the Reactor Building and the outdoor test site -are equipped with conduits for communication and instrumentation cables.</p> - -<p>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.</p> - -<p><b>Data Acquisition and Processing</b> The basic element here is the -APRF Data Acquisition System described in <a href="#TABLE_IX">Table IX</a>. -Various other instrumentation is available as summarized in -<a href="#TABLE_IX">Table IX</a>. Data processing is available at the -ARDC computer center and with on-line equipment at APRF.</p> - -<p><b>Dosimetry</b> 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.</p> - -<p>Measurements are supplemented by analytical methods including one -and two dimensional transport theory, Monte Carlo, and special foil -analysis codes.</p> - -<p><b>Staff</b> 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.</p> - -<p><b>Health Physics</b> Health physics survey, monitoring, -decontamination and related services are available in conjunction with -the BRL Health Physics Division.</p> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<p><span class="pagenum" id="Page_18">[Pg 18]</span></p> -<h2 class="nobreak" id="TABLE_IX">Table IX.</h2> -</div> - -<p class="f150"><b>APRF User Support Equipment</b></p> - -<table class="fontsize_120 no-wrap" border="0" cellspacing="2" summary="Table IX" cellpadding="2" > - <thead><tr> - <th class="tdc bb" colspan="4"> </th> - </tr><tr> - <th class="tdl bb" colspan="2"><big>Transient Data Recording System</big></th> - </tr> - </thead> - <tbody><tr> - <td class="tdl">TAPE RECORDERS:</td> - <td class="tdl_ws1"><i>Three each—14 track Honeywell Model 7600</i></td> - </tr><tr> - <td class="tdl">FREQUENCY:</td> - <td class="tdl_ws1"><i>DC to 80 kHz FM, 400 Hz to 700 kHz Direct</i></td> - </tr><tr> - <td class="tdl bt">SIGNAL</td> - <td class="tdl_ws1 bt"><i>Universal Strain gauge and thermocouple with</i></td> - </tr><tr> - <td class="tdl bb">  CONDITIONING:</td> - <td class="tdl_ws1 bb"><i>100 KC DC amplifiers</i></td> - </tr><tr> - <td class="tdl">TIME CODE:</td> - <td class="tdl_ws1"><i>IRIG A, 1 millisecond resolution</i></td> - </tr><tr> - <td class="tdl bt">PATCH PANELS:</td> - <td class="tdl_ws1 bt"><i>Coaxial and triaxial connectors for all inputs</i></td> - </tr><tr> - <td class="tdl bb"> </td> - <td class="tdl_ws1 bb"><i>and outputs, insulated shields.</i></td> - </tr><tr> - <td class="tdl">AUTO CALIBRATION:</td> - <td class="tdl_ws1"><i>50 channel, 3 step</i></td> - </tr><tr> - <td class="tdl">CHANNEL ID:</td> - <td class="tdl_ws1"><i>Automatic ID in binary code</i></td> - </tr><tr> - <td class="tdl bb">PLAYBACK:</td> - <td class="tdl_ws1 bb"><i>12” oscillograph</i></td> - </tr><tr> - <td class="tdl bb" colspan="2"><big><b>Dosimetry</b></big></td> - </tr><tr> - <td class="tdl" colspan="2">Basic Foil Calibration System</td> - </tr><tr> - <td class="tdl" colspan="2">5000 Curie Co-60 source</td> - </tr><tr> - <td class="tdl" colspan="2">Automated Sulfur, Fission Foil and Gamma Well Counting System,</td> - </tr><tr> - <td class="tdl_ws1" colspan="2">100 Samples each per cycle</td> - </tr><tr> - <td class="tdl" colspan="2">Eight channel active dosimeter system with digital read out and</td> - </tr><tr> - <td class="tdl_ws1" colspan="2">computer analysis of neutron fluence and energy</td> - </tr><tr> - <td class="tdl bb" colspan="2">Toshiba Glass Rod and Harshaw TLD Gamma System</td> - </tr><tr> - <td class="tdl bb" colspan="2"><big><b>Computer</b></big></td> - </tr><tr> - <td class="tdl" colspan="2">16 bit/16K memory with foreground/background operation. Automatic</td> - </tr><tr> - <td class="tdl_ws1" colspan="2">acquisition and reduction of foil counting data on-line. On-line</td> - </tr><tr> - <td class="tdl_ws1" colspan="2">monitoring of reactor power pulse with analysis of peak, half-width</td> - </tr><tr> - <td class="tdl_ws1" colspan="2">and yield. On-line monitoring of active dosimeters with data reduction.</td> - </tr><tr> - <td class="tdl bb" colspan="2">Real time/Fortran IV.</td> - </tr><tr> - <td class="tdl bb" colspan="2"><big><b>General Equipment</b></big></td> - </tr><tr> - <td class="tdl" colspan="2">3300 Nuclear Data Multiparameter Analyzer, 4096 channel with</td> - </tr><tr> - <td class="tdl_ws1" colspan="2"> magnetic tape; RIDL 400 Channel Pulse Height Analyzer.</td> - </tr><tr> - <td class="tdl" colspan="2">Oscilloscopes, cameras, electronic calibration equipment.</td> - </tr><tr> - <td class="tdl" colspan="2">Hood areas with manipulators, photographic laboratory, radiation</td> - </tr><tr> - <td class="tdl_ws1" colspan="2"> monitoring equipment and services, machine shop.</td> - </tr><tr> - <td class="tdl bt" colspan="2"> </td> - </tr> - </tbody> -</table> - -<p><span class="pagenum" id="Page_19">[Pg 19]</span></p> - -<div class="figcenter"> - <img src="images/i_18a.jpg" alt="" width="500" height="516" /> - <img src="images/i_18b.jpg" alt="" width="450" height="499" /> - <img src="images/i_18c.jpg" alt="" width="500" height="560" /> - <img src="images/i_19b.jpg" alt="" width="600" height="272" /> - <img src="images/i_19a.jpg" alt="" width="600" height="414" /> -</div> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<p><span class="pagenum" id="Page_20">[Pg 20]</span></p> -<h2 class="nobreak">Instructions To Potential Users</h2> -</div> - -<p>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.</p> - -<p class="center space-above2"><i>For further information contact</i>:</p> - -<p class="f120">Commanding Officer<span class="ws9"> </span><br /> -U.S. Army Ballistic Research Laboratories<br /> -ATTN: AMXRD-BTD, Facility Coordinator<br /> -Aberdeen Proving Ground, Maryland 21005</p> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="footnotes"> -<p class="f150 u"><b>Footnotes:</b></p> - -<div class="footnote"><p class="no-indent"> -<a id="Footnote_1" href="#FNanchor_1" class="label">[1]</a> -This value varies with experimental environment of core.</p> -</div> - -<div class="footnote"><p class="no-indent"> -<a id="Footnote_2" href="#FNanchor_2" class="label">[2]</a> -This value varies with experimental environment of core.</p> -</div> - -<div class="footnote"><p class="no-indent"> -<a id="Footnote_3" href="#FNanchor_3" class="label">[3]</a> -P1: Center of Glory Hole; P2: Core Surface (11.3 cm from -Core Center); P3: 1 meter from Core Center.</p> -</div> - -<div class="footnote"><p class="no-indent"> -<a id="Footnote_4" href="#FNanchor_4" class="label">[4]</a> -These values are approximate and meant for qualitative comparison only.</p> -</div> - -<div class="footnote"><p class="no-indent"> -<a id="Footnote_5" href="#FNanchor_5" class="label">[5]</a> -P1: Center of Glory Hole; P2: Core Surface; P3: 1 Meter -from Core Center.</p> -</div> - -<div class="footnote"><p class="no-indent"> -<a id="Footnote_6" href="#FNanchor_6" class="label">[6]</a> -Ionization and elastic recoil processes contribute roughly -equal amounts to the total kerma.</p> -</div> - -<div class="footnote"><p class="no-indent"> -<a id="Footnote_7" href="#FNanchor_7" class="label">[7]</a> -P1: Center of Glory Hole; P2: Core Surface; P3: 1 Meter -from Core Center.</p> -</div> - -<div class="footnote"><p class="no-indent"> -<a id="Footnote_8" href="#FNanchor_8" class="label">[8]</a> -Representative data. Actual values influenced by core operating history.</p> -</div></div> - -<hr class="chap x-ebookmaker-drop" /> - -<div class="chapter"> -<div class="transnote bbox space-above2"> -<p class="f120 space-above1">Transcriber’s Notes:</p> -<hr class="r5" /> -<p class="indent">The illustrations have been moved so that they do not break up - paragraphs and so that they are next to the text they illustrate.</p> -<p class="indent">Typographical and punctuation errors have been silently corrected.</p> -</div></div> -<div style='display:block; margin-top:4em'>*** END OF THE PROJECT GUTENBERG EBOOK ARMY PULSE RADIATION FACILITY ***</div> -<div style='text-align:left'> - -<div style='display:block; margin:1em 0'> -Updated editions will replace the previous one—the old editions will -be renamed. -</div> - -<div style='display:block; margin:1em 0'> -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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