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{{Adams
{{Adams
| number = ML12160A492
| number = ML13350A249
| issue date = 05/21/2013
| issue date = 09/30/1975
| title = (Draft Was Issued as DG-2005, Dated March 2012), Quality Verification for Plate Type Uranium Aluminum Fuel Elements for Use in Research and Test Reactors, Revision 2
| title = Quality Verification for Plant-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors
| author name = Wertz G
| author name =  
| author affiliation = NRC/NRR/DPR
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Bayssie M
| contact person =  
| case reference number = DG-2005
| document report number = RG-2.003
| document report number = RG 2.3, Rev. 2
| package number = ML12160A480
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 4
| page count = 2
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION May 2013 OFFICE OF NUCLEAR REGULATORY RESEARCH        Revision 2 REGULATORY GUIDE
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                                                           September 1975 REGULATORY GUIDE
   Written suggestions regarding this guide or development of new guides may be submitted through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html. Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/.  The regulatory guide is also available through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML12160A492.  The regulatory analysis may be found in ADAMS under Accession No. ML12160A494 and the staff responses to the public comments on DG-2005 may be found under ADAMS Accession No. ML12160A496.
   OFFICE OF STANDARDS DEVELOPMENT
 
                                                                    REGULATORY GUIDE 2.3 QUALITY VERIFICATION FOR PLATE-TYPE URANIUM-ALUMINUM
REGULATORY GUIDE 2.3 (Draft was issued as DG-2005, dated March 2012) 
                                        FUEL ELEMENTS FOR USE IN RESEARCH REACTORS
QUALITY VERIFICATION FOR PLATE-TYPE URANIUM-ALUMINUM FUEL ELEMENTS FOR USE IN RESEARCH AND TEST REACTORS


==A. INTRODUCTION==
==A. INTRODUCTION==
Purpose  This guide provides guidance that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for complying with the Commissions regulations on establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements used in research and test reactors (RTRs). 
Applicable Rules and Regulations Title 10, Section 50.34(a) (7), of the Code of Federal Regulations (10 CFR Part 50) (Ref. 1), requires each applicant for a construction permit to build a production or utilization facility to describe in its preliminary safety analysis report the quality assurance program that will be applied to the design, fabrication, construction, and testing of the facilitys structures, systems, and components.  Title 10, Section 52.11, of the Code of Federal Regulations (10 CFR Part 52) (Ref. 2), requires information collection.


Related Guidance 
==C. REGULATORY POSITION==
Paragraph (aX7) of Section 50.34, "Contents of                                    The guidance contained in ANSI N398-1974. "Quality Applications; Technical Information," of 10 CFR Part                            Verification for Plate-Type Uranium-Aluminum Fuel
  50, "Licensing of Production and Utilization Facilities,"                        Elements."' is generally acceptable to Up NRC staff and requires that each applicant for a construction permit to                        provides an adequate basis fo rnplying with build a production or utilization facility include in its                        §50.34(a)(7) of 10 CFR Part ',-50 " h respect to preliminary safety analysis report a description of the                          establishing and executing a qiality ass ice program quality assurance program to be applied to the design,                          for verifying the quaUt-                                  Iof SSNate-type uranium- fabrication, construction, and testing of the structures,                        aluminum fuel elements ffu6'!,Vi irescarch reactors, systems, and components of the facility. This guide                              subject to the fullo1*0:.
  describes a method acceptable to the NRC staff for establishing and executing a quality assurance program                                Instead of,-t. deAr"ptitOiven in Section i.4.9 of for verifying the quality of plate-type uraniuni-                                the standard , '*-4,arck*' actor should be defined as a aluminum fuel elements used in research reactors,                                nuclear            tor a          used for scientific, engineering, or
                                  . DISCUSSIONi                                                                  nd is designed to operate at a thermal a.DISCUSeve    Np              megawatt or less or a level of 10
      Work Group ANS-I 5.2 of Subcommittee ANS-1.5                                      c        .. or less if it does not contain a circulating loop
.Research Reactors, of the American Nuclear Society                                              . r core in which fuel experiments are conduc- Standards Committee has revised the American Na                                              liquid fuel loading, or an experimental facility in Standards Institute (ANSI) Standard NS. 96                                              core in excess of 16 square inches in cross section.


Regulatory Guide 2.5, Quality Assurance Program Requirements for Research and Test Reactors, (Ref. 3) contains methods that the NRC staff finds acceptable for complying with the Commission s regulations on the overall quality assurance program requirements for RTRs.
"Quality Control for Plate-Type Uranium-Al ,num                                                         


Purpose of Regulatory Guides
==D. IMPLEMENTATION==
 
Fuel Elements." The revised standard pro                              ui for the- establishment and execution f a                                  gram        The purpose of this section is to provide information designed to verify the quality of plat                            e      nium-  to applicants and licensees regarding the NRC staff's aluminum fuel elements for use in researcih                            rs. The  plans for utilizing this regulatory guide.
The NRC issues regulatory guides to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agency s regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to Rev. 2 of RG 2.3, Page 2 applicants.  Regulatory guides are not substitutes for regulations and compliance with them is not required.  Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.
 
Paperwork Reduction Act This regulatory guide contains information collection requirements covered by 10 CFR Part 50 and 10 CFR Part 52 that the Office of Management and Budget (OMB) approved under OMB control number 3150-0011 and 3150-0151, respectively.  The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.


==B. DISCUSSION==
revised standard was approved by the American National Standards Committee N                          search Reactors, Reactor                Except in those -cases in which the applicant Physics and Radiation                  el* and its Secretariat. It              proposes an acceptable alternative method for
Reason for Revision
*was subsequently a )p                                      designated ANSI        complying, with the specified portions of the N398-1974 by;                          oI ber 19, 1974.                          Commission's regulations, the method described herein will be used by the NRC staff in the It sl'ou          e ogni            that ANSI N398-1974 covers,              evaluation of submittals for construction permit or only on            i                f quality assurance. ANSI N402,              operating license applications for research reactors dock-
  "Quality              rance Program. Guidelines for Research                    oted after May 15, 1976.


Revision 1 to Regulatory Guide 2.3, issued in July 1976, endorsed the guidance provided in the American National Standards Institute (ANSI) N398-1974, Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements." It was subsequently approved and designated ANSI N398-1974 by ANSI on November 19, 1974 and covers only one limited aspect of quality assurance.  ANSI N398-1974 has been superseded and is no longer supported by the NRC staff.  Revision 2 to Regulatory Guide 2.3 refers to the guidance in ANSI/ANS-15.2-1999, Quality Control for Plate-Type Uranium-Aluminum Fuel Elements (Ref. 4). 
Reactors,"             ch is currently being developed under Subcommitte              ANS-15, is expected to provide overall guidance for establishing quality assurance programs for                               1
  Background The NRC initially issued Regulatory Guide 2.3 in 1975 to provide guidance concerning procedures that the staff considered acceptable for complying with the agencys regulatory requirements in 10 CFR 50.34(a) (7).  The original guide endorsed specific safety standards to provide guidelines for establishing and executing a program designed to verify the quality of plate-type uranium-aluminum fuel elements for use in research reactors. The American Nuclear Society (ANS) Subcommittee on the Operation of Research Reactors (ANS-15) rewrote ANSI N398-1974, issued it as ANSI/ANS-15.2-1999, and subsequently reaffirmed the standard in March 2009. The NRC staff believes that the foreword to ANSI/ANS-15.2-1999 (R2009) has several important assumptions about its use.      Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of safety standards constituting a high level of safety for protecting people and the environment.  Relative to this regulatory guide, IAEA Safety Requirements publication NS-R-4, Safety at Research Reactors (Ref. 5), provides quality assurance requirements in sections 4.5-4.13, as part of an overall system of management and verification controls.  While the NRC has an interest in facilitating the harmonization of standards used domestically and internationally, the NRC does not specifically endorse NS-R-4, and is only acknowledging that it may be useful as a reference for general information.  The NRC could consider the use of the international standard in a licensing action following adequate justification and technical review.
                                                                                          ('opies may be obtaineid rroni the American Nuclear research reactors.                                                               Society. 244 Fast O+/-Cidcn Avenue. Ilindale. Illinois 60521.


Rev. 2 of RG 2.3, Page 3 Documents Discussed in Staff Regulatory Guidance This regulatory guide endorses the use of one or more codes or standards developed by external organizations, and other third party guidance documents.  These codes, standards and third party guidance documents may contain references to other codes, standards or third party guidance documents (secondary references).  If a secondary reference has itself been incorporated by reference into NRC regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation.  If the secondary reference has been endorsed in a regulatory guide as an acceptable approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific regulatory guide.  If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in a regulatory guide, then the secondary reference is neither a legally-binding requirement nor a generic NRC approval as an acceptable approach for meeting an NRC requirement.  However, licensees and applicants may consider and use the information in the secondary reference, if appropriately justified and consistent with current regulatory practice, consistent with applicable NRC requirements such as 10 CFR 50.59.  C.  STAFF REGULATORY GUIDANCE The NRC staff finds ANSI/ANS-15.2-1999 (R2009), Quality Control for Plate-Type Uranium-Aluminum Fuel Elements, provides an acceptable method for complying with the requirements in 10 CFR 50.34(a)(7) in regard to establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements for use in RTRs, subject to the following condition:
t USNRC REGULATORY GUIDES                                      Comments      should be sent to the Secretary o    the Commission.  U.S. Nuclear Regutatory Guides are issued to describe and mnake available to the public        Regulatory Commission.     Washington.    D.C. 20566. Attention. Docketing and methods acceptable to the NRC staff of Implementing specific parts                Service Section.
(1) ANSI/ANS-15.2-1999 (R2009), Section 13.4, Verification of Fuel Element Assembly Dimensions, requires a verification of items
1-6, with item 6 designated functional fit. The NRC staff considers item 6 a desired test, but not required.
 
==D. IMPLEMENTATION==
The purpose of this section is to provide information to applicants and licensees regarding the NRCs plans for using this regulatory guide.  The regulatory position held in this guidance demonstrates the method that the NRC staff finds acceptable for an applicant or licensee to meet the requirements of the underlying NRC regulations.  Methods or solutions that differ from those described in this regulatory guide may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with the appropriate NRC regulations.


Current licensees may continue to use guidance the NRC found acceptable for complying with the identified regulations as long as their current licensing basis remains unchanged.   The imposition of the guidance in this regulatory guide is not a backfit, as that term is defined in 10 CFR 50.109, Backfitting, because non-power reactor licensees are not included within the scope of entities protected by the Backfit Rule.
Conmnmlssion's regulations. to delineate techniques used by the stalt in evslu      The guides are issued in the following ten broad divisions
"tOng specific problems or postulated accidents, or to provide guidance to appli cents. Regulatory Guides are not substitutes fot regulations. and compliance        1. Power Reactors                      6  Products with them Is not required Methods and solutions difletent from those set out In      2. Research end Teot Reactors          7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to  3. Fuels and Materials Factlities      B. Occupational Health the issuance Or conttnuanc.e of a permit or license by the Commission.              4, Envirortmental and Siting            9. Antitrust Review Comments and suggestions tor impa~vements in these guides are encouraged            S. Materials and Plant Protection      t0. General atill limes, and guides will tie revised. as appropriate. to accommodate corn mnits and to reflect new information or taperience. However. comments on            Copies of published guides may be obtllned by written request indiclting the this guide. it received within about two monthi, after its issuance, will be pap    divisions desired to the U.S Nuclear Regulatory Commission. Washington. D.C.


Rev. 2 of RG 2.3, Page4 REFERENCES
Ilculaily uselul in evaluating the need for dn early evaision.                       20r%5. Attention: Director. Office of Standards Development.
1  1. 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, U.S. Nuclear Regulatory Commission, Washington, DC.


2. 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC.
I


3. Regulatory Guide 2.5, Quality Assurance Program Requirements for Research and Test Reactors, U.S. Nuclear Regulatory Commission, Washington, DC.
referred tothe input ror 4 usee peaking tinmcs (the noise:                a stable pulser should. not shift by more. than. one
.lel .,afies iti'erselV with ..tle peukinig time). The main                channel over a 24.hou* periodfor a line voltage of 1!5V
  . ni.plil .htild be. a standard NIM' nmodule.                             - 10%, 50-65 Hz, and at constant room temperature.


4. ANSI/ANS-15.2-1999 (R2009), Quality Control for Plate-Type Uranium-Aluminum Fuel Elements, American Nuclear Society, La Grange Park, IL.
(Note: The .ADC drift and linearity specifications are At Loliting ratesgreater thanr" l 0" cps. problems            .closely ..re!ted to the overall . system%stability and
.':.i' i als degraid* tion o1 t he energy resolution resulting in          lirearity operating Spec-fications described in Section
  .a loss of.counts in the. spectrum peaks begin to occur.                  C.S.)
    These.effecisare due to.the overlar' of portions of two ormnore pulses in. time and to bas.Žline fhuctuatio*s. The                  The .ADC should be capable of being DC coupled to
    . .agiiitudeof ihese effects can be minimized by the                    the main amplifier in order that BLR circuits can be inclusion of.th1e. folluwing features in the amplifier's              used. A digital = offset capability in the ADC is des-111-. (: a baseline restorer. (BLR) circuit at. the                  recommended.. (Note: In some systems the ADC is an
-ampli*iir :outp.iu and _(2) pole-zero. cancelled ýcoupling                integral -part of a multichannel analyzer, a unit which
  "networks The. BLR circuit should be adjustable f.r.both                  also performs the .functions .of data storage, display, and i a d Inlig counting rateconditions.'
  I-ow                                                                    sometimes rrudimentary analysis.. These latter functions'
                                                                            are taken up in Part 2 of this serie


2  5. Safety Requirements, NS-R-4, Safety at Research Reactors, September, 2005, International Atomic Energy Agency, Vienna, Austria.
====s. In multichannel====
.5. Analog to Digital Converter (ADC)                                      analyzer systems, however, the. ADC function is usually specified separately.and canbe compared with the above (Systems I. 11.II!) The ADC should be capable of                recommendations.)
  digitizing pulse :,mplitudes from the amplifier in the range of 0 to 10 volts in at least 4096 channels. The                          (Sysiemn I) For certain applications where energy fre.quency of the internal clock should be at least 50                  resolution is definitely not critical, all the ADC
  "megidahcz to handle high. counting rates with nominal                    specifications above arc applicable with the exception ADC dead time losses. The integral nonlinearity should                  that a 1024 channel capacity with a 1024 digital offset be tle: than 0. 15% over the top 95% of full scale and the              may be adequate to provide a sufficiently small energy differential nonlinearity should be less than I.Wff over                interval per channel (keV/channel) to cover a limited the top 95% of full scale for semi-Gaussian pulses with                  energy range of interest. It should be emphasized,
"peaking times of I to usec.-These linearity specifications                however, that this choice may restrict the effective use are' n6t 'siringent. but arec adequate to enable                        of the system for other applications.


3                                           
"identificatiin.of unknown peaks which .may appear in a spectrum..                                                               6. Power Supplies The short-term zero channel arid gain drifts should                  (Systems 1,, II, .111) The system power supplies be < .01%/ 0 C and < .02%/0 C, respectively (the                        (detector high voltage, preamplifier, and NIM bin)
1  Publicly available NRC published documents are available electronically through the NRC Library on the NRCs public Web site at: http://www.nrc.gov/reading-rm/doc-collections/. The documents can also be viewed on-line or printed for a fee in the NRCs Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing address is USNRC PDR, Washington, DC 20555; telephone 301-415-4737 or (800) 397-4209; fax (301) 415-3548; and e-mail pdr.resource@nrc.gov.  2        Copies of American Nuclear Society (ANS) standards may be purchased from the ANS Web site (http://www.new.ans.org/store/) ; or by writing to: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526, U.S.A., Telephone 800-323-3044.
    percentage refers to full scale), in the temperature range              should be capable of operating the system within the from 0&deg;. to 50'C. For long term stability, the peak from                  operating specifications listed in Section C.A when supplied with 115 volts (+/- 10%) at. 50 to 65 hertz (at
            ' NIM-Nuclear Instrument Module, see USAEC -Technical            constant room temperature), The detector bias power Information Document. Standard Nuclear Instrument Modules,          
* supply should have an adjustable output that is short Revision 3. TID-20893 (1969).                                          .circuait protected with automatic power restoration after
        .'.*'r    more details on BLR circuits see V. Radeka, "Effect      removal of the short. The maximum output voltage is
    -.of 'aseline Retoration' on Signal-to-Noise.      Ratio in Pulse        determined by detector requirements; 5 kilovolts is Amplitude Mcasuremernts,7 Rev. Sci. lnsir. 3 8.1 397 (1967).            sufficient for most. applications.


3  Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site: WWW.IAEA.Org/ or by writing the International Atomic Energy Agency P.O. Box 100 Wagramer Strasse 5, A-1400 Vienna, Austria. Telephone (+431) 2600-0, Fax (+431) 2600-7, or E-Mail at Official.Mail@IAEA.Org}}
5 .9-6}}


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Latest revision as of 01:22, 20 March 2020

Quality Verification for Plant-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors
ML13350A249
Person / Time
Issue date: 09/30/1975
From:
Office of Nuclear Regulatory Research
To:
References
RG-2.003
Download: ML13350A249 (2)
v • d • e


U.S. NUCLEAR REGULATORY COMMISSION September 1975 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 2.3 QUALITY VERIFICATION FOR PLATE-TYPE URANIUM-ALUMINUM

FUEL ELEMENTS FOR USE IN RESEARCH REACTORS

A. INTRODUCTION

C. REGULATORY POSITION

Paragraph (aX7) of Section 50.34, "Contents of The guidance contained in ANSI N398-1974. "Quality Applications; Technical Information," of 10 CFR Part Verification for Plate-Type Uranium-Aluminum Fuel

50, "Licensing of Production and Utilization Facilities," Elements."' is generally acceptable to Up NRC staff and requires that each applicant for a construction permit to provides an adequate basis fo rnplying with build a production or utilization facility include in its §50.34(a)(7) of 10 CFR Part ',-50 " h respect to preliminary safety analysis report a description of the establishing and executing a qiality ass ice program quality assurance program to be applied to the design, for verifying the quaUt- Iof SSNate-type uranium- fabrication, construction, and testing of the structures, aluminum fuel elements ffu6'!,Vi irescarch reactors, systems, and components of the facility. This guide subject to the fullo1*0:.

describes a method acceptable to the NRC staff for establishing and executing a quality assurance program Instead of,-t. deAr"ptitOiven in Section i.4.9 of for verifying the quality of plate-type uraniuni- the standard , '*-4,arck*' actor should be defined as a aluminum fuel elements used in research reactors, nuclear tor a used for scientific, engineering, or

. DISCUSSIONi nd is designed to operate at a thermal a.DISCUSeve Np megawatt or less or a level of 10

Work Group ANS-I 5.2 of Subcommittee ANS-1.5 c .. or less if it does not contain a circulating loop

.Research Reactors, of the American Nuclear Society . r core in which fuel experiments are conduc- Standards Committee has revised the American Na liquid fuel loading, or an experimental facility in Standards Institute (ANSI) Standard NS. 96 core in excess of 16 square inches in cross section.

"Quality Control for Plate-Type Uranium-Al ,num

D. IMPLEMENTATION

Fuel Elements." The revised standard pro ui for the- establishment and execution f a gram The purpose of this section is to provide information designed to verify the quality of plat e nium- to applicants and licensees regarding the NRC staff's aluminum fuel elements for use in researcih rs. The plans for utilizing this regulatory guide.

revised standard was approved by the American National Standards Committee N search Reactors, Reactor Except in those -cases in which the applicant Physics and Radiation el* and its Secretariat. It proposes an acceptable alternative method for

  • was subsequently a )p designated ANSI complying, with the specified portions of the N398-1974 by; oI ber 19, 1974. Commission's regulations, the method described herein will be used by the NRC staff in the It sl'ou e ogni that ANSI N398-1974 covers, evaluation of submittals for construction permit or only on i f quality assurance. ANSI N402, operating license applications for research reactors dock-

"Quality rance Program. Guidelines for Research oted after May 15, 1976.

Reactors," ch is currently being developed under Subcommitte ANS-15, is expected to provide overall guidance for establishing quality assurance programs for 1

('opies may be obtaineid rroni the American Nuclear research reactors. Society. 244 Fast O+/-Cidcn Avenue. Ilindale. Illinois 60521.

t USNRC REGULATORY GUIDES Comments should be sent to the Secretary o the Commission. U.S. Nuclear Regutatory Guides are issued to describe and mnake available to the public Regulatory Commission. Washington. D.C. 20566. Attention. Docketing and methods acceptable to the NRC staff of Implementing specific parts Service Section.

Conmnmlssion's regulations. to delineate techniques used by the stalt in evslu The guides are issued in the following ten broad divisions

"tOng specific problems or postulated accidents, or to provide guidance to appli cents. Regulatory Guides are not substitutes fot regulations. and compliance 1. Power Reactors 6 Products with them Is not required Methods and solutions difletent from those set out In 2. Research end Teot Reactors 7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to 3. Fuels and Materials Factlities B. Occupational Health the issuance Or conttnuanc.e of a permit or license by the Commission. 4, Envirortmental and Siting 9. Antitrust Review Comments and suggestions tor impa~vements in these guides are encouraged S. Materials and Plant Protection t0. General atill limes, and guides will tie revised. as appropriate. to accommodate corn mnits and to reflect new information or taperience. However. comments on Copies of published guides may be obtllned by written request indiclting the this guide. it received within about two monthi, after its issuance, will be pap divisions desired to the U.S Nuclear Regulatory Commission. Washington. D.C.

Ilculaily uselul in evaluating the need for dn early evaision. 20r%5. Attention: Director. Office of Standards Development.

I

referred tothe input ror 4 usee peaking tinmcs (the noise: a stable pulser should. not shift by more. than. one

.lel .,afies iti'erselV with ..tle peukinig time). The main channel over a 24.hou* periodfor a line voltage of 1!5V

. ni.plil .htild be. a standard NIM' nmodule. - 10%, 50-65 Hz, and at constant room temperature.

(Note: The .ADC drift and linearity specifications are At Loliting ratesgreater thanr" l 0" cps. problems .closely ..re!ted to the overall . system%stability and

.':.i' i als degraid* tion o1 t he energy resolution resulting in lirearity operating Spec-fications described in Section

.a loss of.counts in the. spectrum peaks begin to occur. C.S.)

These.effecisare due to.the overlar' of portions of two ormnore pulses in. time and to bas.Žline fhuctuatio*s. The The .ADC should be capable of being DC coupled to

. .agiiitudeof ihese effects can be minimized by the the main amplifier in order that BLR circuits can be inclusion of.th1e. folluwing features in the amplifier's used. A digital = offset capability in the ADC is des-111-. (: a baseline restorer. (BLR) circuit at. the recommended.. (Note: In some systems the ADC is an

-ampli*iir :outp.iu and _(2) pole-zero. cancelled ýcoupling integral -part of a multichannel analyzer, a unit which

"networks The. BLR circuit should be adjustable f.r.both also performs the .functions .of data storage, display, and i a d Inlig counting rateconditions.'

I-ow sometimes rrudimentary analysis.. These latter functions'

are taken up in Part 2 of this serie

s. In multichannel

.5. Analog to Digital Converter (ADC) analyzer systems, however, the. ADC function is usually specified separately.and canbe compared with the above (Systems I. 11.II!) The ADC should be capable of recommendations.)

digitizing pulse :,mplitudes from the amplifier in the range of 0 to 10 volts in at least 4096 channels. The (Sysiemn I) For certain applications where energy fre.quency of the internal clock should be at least 50 resolution is definitely not critical, all the ADC

"megidahcz to handle high. counting rates with nominal specifications above arc applicable with the exception ADC dead time losses. The integral nonlinearity should that a 1024 channel capacity with a 1024 digital offset be tle: than 0. 15% over the top 95% of full scale and the may be adequate to provide a sufficiently small energy differential nonlinearity should be less than I.Wff over interval per channel (keV/channel) to cover a limited the top 95% of full scale for semi-Gaussian pulses with energy range of interest. It should be emphasized,

"peaking times of I to usec.-These linearity specifications however, that this choice may restrict the effective use are' n6t 'siringent. but arec adequate to enable of the system for other applications.

"identificatiin.of unknown peaks which .may appear in a spectrum.. 6. Power Supplies The short-term zero channel arid gain drifts should (Systems 1,, II, .111) The system power supplies be < .01%/ 0 C and < .02%/0 C, respectively (the (detector high voltage, preamplifier, and NIM bin)

percentage refers to full scale), in the temperature range should be capable of operating the system within the from 0°. to 50'C. For long term stability, the peak from operating specifications listed in Section C.A when supplied with 115 volts (+/- 10%) at. 50 to 65 hertz (at

' NIM-Nuclear Instrument Module, see USAEC -Technical constant room temperature), The detector bias power Information Document. Standard Nuclear Instrument Modules,

  • supply should have an adjustable output that is short Revision 3. TID-20893 (1969). .circuait protected with automatic power restoration after

.'.*'r more details on BLR circuits see V. Radeka, "Effect removal of the short. The maximum output voltage is

-.of 'aseline Retoration' on Signal-to-Noise. Ratio in Pulse determined by detector requirements; 5 kilovolts is Amplitude Mcasuremernts,7 Rev. Sci. lnsir. 3 8.1 397 (1967). sufficient for most. applications.

5 .9-6


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