1、ANSI/ANS-14.1-2004operation of fastpulse reactorsANSI/ANS-14.1-2004This standard has been reviewed and reaffirmed with the recognition that itmay reference other standards and documents that may have beensuperceded or withdrawn. The requirements of this document will be met byusing the version of th
2、e standards and documents referenced herein. It is theresponsibility of the user to review each of the references and to determinewhether the use of the original references or more recent versions isappropriate for the facility. Variations from the standards and documentsreferenced in this standard
3、should be evaluated and documented.REAFFIRMEDOctober27,2009ANSI/ANS-14.1-2004 (R2009)ANSI/ANS-14.1-2004American National StandardOperation of FastPulse ReactorsSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorking Group ANS-14.1Published by theAmerican
4、Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved April 23, 2004by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard attests thatthe principles of openness and due process have been f
5、ollowed in the approvalprocedure and that a consensus of those directly and materially affected bythe standard has been achieved.This standard was developed under procedures of the Standards Committee ofthe American Nuclear Society; these procedures are accredited by the Amer-ican National Standards
6、 Institute, Inc., as meeting the criteria for AmericanNational Standards. The consensus committee that approved the standardwas balanced to ensure that competent, concerned, and varied interests havehad an opportunity to participate.An American National Standard is intended to aid industry, consumer
7、s, gov-ernmental agencies, and general interest groups. Its use is entirely voluntary.The existence of an American National Standard, in and of itself, does notpreclude anyone from manufacturing, marketing, purchasing, or using prod-ucts, processes, or procedures not conforming to the standard.By pu
8、blication of this standard, the American Nuclear Society does not insureanyone utilizing the standard against liability allegedly arising from or afterits use. The content of this standard reflects acceptable practice at the time ofits approval and publication. Changes, if any, occurring through dev
9、elopmentsin the state of the art, may be considered at the time that the standard issubjected to periodic review. It may be reaffirmed, revised, or withdrawn atany time in accordance with established procedures. Users of this standardare cautioned to determine the validity of copies in their possess
10、ion and toestablish that they are of the latest issue.The American Nuclear Society accepts no responsibility for interpretations ofthis standard made by any individual or by any ad hoc group of individuals.Requests for interpretation should be sent to the Standards Department atSociety Headquarters.
11、 Action will be taken to provide appropriate response inaccordance with established procedures that ensure consensus on theinterpretation.Comments on this standard are encouraged and should be sent to SocietyHeadquarters.Published byAmerican Nuclear Society555 North Kensington AvenueLa Grange Park,
12、Illinois 60526 USACopyright 2004 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmerican National Standard ANSI0ANS-14.1-2004 with permission of the publisher,the American Nuclear Society.” Reproduction prohibited und
13、er copyright conventionunless written permission is granted by the American Nuclear Society.Printed in the United States of AmericaForewordThis foreword is not part of American National Standard “Operation of Fast PulseReactors,” ANSI0ANS-14.1-2004.Nuclear devices designed and operated for purposes
14、of research and as sources ofsharp, intense pulses of fission-produced radiation have functioned successfullyfor more than 40 years. In the usual operation, superprompt criticality is estab-lished in a mass of unmoderated fissile metal, radiation is produced, and thenuclear reaction is immediately t
15、erminated by characteristics inherent in thefissile material itself. These devices have come to be known as fast pulse reac-tors. This standard provides direction in the use of such specialties so that therisk of damage to personnel and equipment can be controlled. It was prepared byindividuals havi
16、ng extensive and intimate experience in the operation of thistype of reactor.At the time of the initial publication in 1975, the membership of Subcommittee14 was as follows:A. De La Paz Chair!, White Sands Missile RangeL. M. Bonson, Sandia National LaboratoriesK. Elliott, Albuquerque Operations Offi
17、ce, U.S. Atomic Energy CommissionL. P. Holland, Oak Ridge National LaboratoryA. H. Kazi, Aberdeen Pulse Radiation FacilityR. L. Long, University of New MexicoJ. M. Reuscher, Sandia National LaboratoriesT. F. Wimett, Los Alamos Scientific LaboratoryIn 2000, a working group was reestablished to review
18、 and update the standard.The standard had been reaffirmed in 1982, 1989, and 2000. The standard neededto be updated to reflect changes in procedures and to reference associatedstandards. The members of Working Group 14.1 producing the revised standardare as follows:T. R. Schmidt Chair!, Sandia Natio
19、nal LaboratoriesR. E. Anderson, Los Alamos National LaboratoryJ. W. Bryson, Sandia National LaboratoriesM. J. Burger, Sandia National LaboratoriesA. De La Paz, Vista TechnologiesJ. R. Felty, Science Applications International CorporationT. Michael Flanders, White Sands Missile RangeA. H. Kazi Retire
20、d!, Aberdeen Pulse Radiation FacilityR. A. Knief, XE CorporationR. L. Long, Nuclear Stewardship, LLCM. Mendonca, U.S. Nuclear Regulatory CommissionD. M. Minnema, National Nuclear Security AdministrationG. A. Schlapper, National Nuclear Security AdministrationThis standard was processed and approved
21、for submittal to ANSI by the Amer-ican Nuclear Societys Research Reactors, Reactor Physics, Radiation Shieldingthe word “should” is used to denote arecommendation; and the word “may” is usedto denote permission, neither a requirementnor a recommendation. To conform with thisstandard, all operations
22、shall be performed inaccordance with its requirements, but not nec-essarily with its recommendations.2.3 Glossary of termscontrol elements: Those reactor fuel or neu-tron reflection components whose movementincreases or decreases the reactivity of the re-actor. Included are control rods, pulse rod,
23、safetyblock, and reflectors or equivalent.fast pulse reactor (also referred to as fastburst reactor): An essentially unmoderatedassembly of fissionable material designed toproduce short-duration, high-intensity pulsesof fission radiation. Also, it may be operated ata steady-state power level.interlo
24、ck: A switch, relay, or hardware0softwarecombination that locks in a priority of eventsor that locks out a particular event.neutron decay interval: The interval of timein the pulse production cycle of the reactor dur-ing which a subcritical configuration is at-tained to allow for decay of delayed ne
25、utronprecursors.reactor area: A region in the vicinity of thereactor where personnel shall not be presentduring a reactor operation.reactor operating staff: Those personnel, in-cluding reactor supervisor and reactor operatorpersonnel, certified in accordance with proce-dures established by managemen
26、t to carry outoperation of the reactor.reactor operator: An individual certified tomanipulate the controls of a reactor.reactor shutdown: The condition where, as aminimum, the safety block or equivalent is inits minimum reactivity position.reactorsupervisor:See senior reactor operator.safety block:
27、The control element having areactivity worth such that its movement is theprimary mechanical means of shutting downthe operation.safety device: A mechanism or system de-signed to move a control element to reduce thereactivity of a fast pulse reactor.scram: The act of shutting down a reactor sud-denl
28、y by operation of the reactor safety devices.senior reactor operator: An individual certi-fied to direct the activities of reactor operators.Such an individual is also a reactor operator.3 Administrative practices3.1 Line organizationManagement shall assign responsibility andcommensurate authority f
29、or safe operation ofthe reactor unambiguously and singularlythrough the line organization.1!Numbers in brackets refer to corresponding numbers in Section 8, “References.”13.2 General operational restrictionsWritten general operational restrictions for thereactor, based on a safety assessment and con
30、-sideration of characteristics including shieldingand confinement, shall be approved by manage-ment and the cognizant regulating authority. Cri-teria for the safety assessment may be derivedfrom the American National Standard “Formatand Content for Safety Analysis Reports for Re-search Reactors,”ANS
31、I0ANS-15.21-19962#.Cri-teria for operational restrictions may be derivedfrom the American National Standard “The De-velopment of Technical Specifications for Re-search Reactors,” ANSI0ANS-15.1-1990 3#.3.3 Experiment planPrior to the start of each experiment, an ex-periment plan shall be reviewed and
32、 approvedin accordance with procedures approved bymanagement.3.4 TrainingReactor operating staff personnel shall betrained to ensure that they are capable of per-forming their assigned work. Continuing train-ing, including periodic reactor operations, shallbe provided to ensure that job proficiency
33、ismaintained. Criteria for personnel qualifica-tions and training may be derived from theAmerican National Standard “Selection andTraining of Personnel for Research Reactors,”ANSI0ANS-15.4-1988 4#.3.5 Reactor operations staffAt least two members of the reactor operatingstaff, one of whom is a reacto
34、r supervisor, shallbe present in the reactor facility during opera-tion of the reactor, and one of the two shall bepresent at the control console at all times dur-ing operation of the reactor.3.6 Pulse operations staffAt least two members of the reactor operatingstaff, one of whom is a reactor super
35、visor, shallbe present at the reactor control console areaduring pulse rod calibrations, pulse setup, andconduct of the pulse.3.7 Maintenance and experiment setupstaffA minimum of two individuals, at least one ofwhom is a member of the reactor operatingstaff, shall be present during reactor mainte-n
36、ance or experimental setup operations involv-ing access to the reactor. A member of theoperating staff shall be present at the reactorcontrol console while power is provided for move-ment of the control elements. Such mainte-nance or experimental setup operations shallbe approved by a reactor superv
37、isor.3.8 Operations proceduresWritten procedures shall be used for all reactoroperations. Provision shall be made for keepingprocedures current and in compliance with op-erational restrictions.3.9 Access proceduresWritten procedures shall be established for con-trol of access to the reactor area.3.1
38、0 Emergency planAn emergency plan approved by managementshall be in effect, and emergency equipmentshall be provided. Criteria for an emergencyplan may be derived from the American Na-tional Standard “Emergency Planning for Re-search Reactors,” ANSI0ANS-15.16-1982 5#.3.11 Radiological protectionRadi
39、ation monitoring, personnel dosimetry, andcontamination control shall be provided for bothnormal and emergency conditions. Criteria fora radiation protection program may be derivedfrom the American National Standard “Radia-tion Protection at Research Reactor Facilities,”ANSI0ANS-15.11-1993 6#.3.12 A
40、nnual reviewKnowledgeable personnel, independent of thereactor operating staff, shall review the reac-tors administrative, operational, and safetypractices at least annually. The results of thereview shall be documented.3.13 Quality assurance planDesign of the facility, reactor, and control sys-tem,
41、 and modifications thereto, shall adhereto a quality assurance plan approved by man-agement. Criteria for a quality assurance planmay be derived from the American NationalStandard “Quality Assurance Program Require-ments for Research Reactors,” ANSI0ANS-15.8-1995 7#.American National Standard ANSI0A
42、NS-14.1-200424 Facility design criteria4.1 Reactor facility planningThe following shall be considered in planning afast pulse reactor facility:1! prevention of accidental criticality or re-activity increases that might result from cred-ible malfunctions;2! control of entry into hazardous areas;3! co
43、nvenience, feasibility, and ease of reac-tor system maintenance commensurate withanticipated radiation levels;4! prevention of flooding of the reactor;5! implementation of emergency response;6! limiting neutron activation by using ap-propriate construction materials.4.2 Physical barriersPhysical bar
44、riers shall be provided for protec-tion of operating staff and experimenters fromradiation associated with normal reactor oper-ations and credible accidents.4.3 Public protectionProvision e.g., shielding, fencing, and dis-tance! shall be made for protection of the pub-lic from radiation associated w
45、ith normal reactoroperations and from credible accidents.4.4 Radiation detection systemA permanently installed radiation detection sys-tem shall be provided to monitor and indicatethe radiation levels, with appropriate alarms,at selected points throughout the facility.4.5 Contamination monitoringMea
46、ns shall be provided for contamination mon-itoring of personnel exiting the reactor area.4.6 DecommissioningConsideration should be given to decommission-ing of the facility during the design phase. Cri-teria for decontamination and decommissioningmay be derived from the American NationalStandard “D
47、ecommissioning of Research Reac-tors,” ANSI0ANS-15.10-1994 8#.5 Reactor design criteria5.1 Reactivity quenchingInherent prompt reactivity quenchinge.g., neg-ative temperature coefficient! shall be a funda-mental characteristic of the reactor.5.2 Safety devicesAt least two independent safety devices
48、suchas safety block and control elements! shall beprovided. The safety devices shall be fail-safewith respect to loss of electrical power.5.3 Primary safety device reactivityThe primary safety device such as safety blockmovement! shall be capable of shutting downthe reactor under conditions correspo
49、nding tothe most reactive experiment arrangement.5.4 InterlocksInterlocks shall be provided to prevent1! reset of the control system for subsequentoperation of the reactor unless the controlelements are at positions of minimum reac-tivity worth;2! insertion of the safety block unless theother control elements are at positions of min-imum reactivity worth, except at the end ofthe neutron decay interval;3! insertion of two different types of controlelements simultaneously;4! positive reactivity insertion by control ele-ments during the neutron decay interval;5! pers
