Regulatory Guide 3.9: Difference between revisions

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{{Adams
{{Adams
| number = ML003740214
| number = ML12220A059
| issue date = 06/30/1973
| issue date = 06/30/1973
| title = Concrete Radiation Shields. Label as Withdrawn 01/15/98
| title = Concrete Radiation Shields
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = NRC/RES, US Atomic Energy Commission (AEC)
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
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| page count = 2
| page count = 2
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{{#Wiki_filter:U.S. ATOMIC ENERGY COMMIIISION
{{#Wiki_filter:U.S. ATOMIC ENERGY COMMISSION                                                                                        June 1973 REGULATORY
REGULATORY  
                                    DIRECOoAT                    OF REGULATORY SANDARDS
DIRECTORATE
                                                                                                                                    GUIDE
OF REGULATORY  
                                                                          REGULATORY GUIDE 3.9 CONCRETE RADIATION SHIELDS
STANDARDS
REGULATORY  
GUIDE 3.9 CONCRETE RADIATION  
SHIELDS  


==A. INTRODUCTION==
==A. INTRODUCTION==
Section 20.101 of 10 CFR Part 20. "Exposure of Individuals to Radiation in Restricted Areas," states that no licensee shall possess. use, or transfer licensed material in such a manner as to cause any individual in a restricted area to receive a dose in excess of the limits specified therein. Paragraph (c) of § 20.1 provides that licensees, in addition to complying with the requirements set forth in Part 20. make every reasonable effort to maintain radiation exposures as far below the limits specified in this part as practicable.
Design. Construction and Operation Criteria. and it was subsequently approved by the American National Section 20.101 of 10 CFR Part 20, "Exposure of                                   Standards Institute- (ANSI) on December 22. IPQ2.


Concrete radiation shields can be installed in nuclear facilities such as hot laboratories, radiochemical plants, experimental facilities, and nuclear fuel fabrication plants to provide a barrier between personnel and radiation sources for the purpose cf reducing doses of ionizing radiation received by personnel to as low as practicable levels. This guide describes practices for the construction of concrete radiation shielding structures for such nuclear facilities, which are acceptable to the Regulatory staff as methods of complying, in part, with Commission regulations with regard to reducing radiation exposures.
Individuals to Radiation in Restricted Areas," states that                                and designated ANSI N101.6-1972. The standard no licensee shall possess, use, or transfer licensed                                      discusses aggregateo. design of concrete mixtures and material in such a manner as to cause any individual in a                                 forms, placement of concrete, design and installation of restricted area to receive a dose in excess of the limits                                penetrations. embedments. metal liners, and penetration specified therein. Paragraph (c) of § 20.1 provides that                                  plugs and outlines testing and quality assurance licensees, in addition to complying with the                                              provisions needed to verify that the desired quality of requirements set forth in Part 20, make every reasonable                                  design and construction has been achieved. The standard effort to maintain radiation exposures as far below the                                  does not include detailed treatments of structural design limits specified in this part as practicable.                                            or determination of shield thickness.


Much of the information included may be applicable to shielding structures for reactors and other nuclear and nonnuclear facilities which require concrete radiation shields.
Concrete radiation shields can be installed in nuclear facilities such as hot laboratories, radiochemical plants,                                                 


==B. DISCUSSION==
==C. REGULATORY POSITION==
Subcommittee ANS- I, Radioactive Materials Handling Facilities and Specialized Equipment.
experimental facilities, and nuclear fuel fabrication plants to provide a barrier between personnel and                                                The requirements and recommended practices radiation sources for the purpose cf reducing doses of                                  contained in ANSI N101.6.1972, "Concrete Radiation ionizing radiation received by personnel to as low as                                    Shields,"' are acceptable for the construction of practicable levels. This guide describes practices for the                              radiation shielding structures for hot laboratories.


of the American Nuclear Society has developed a standard presenting requirements and recommended practices for the construction of concrete radiation shielding structures and for certain elements of design that relate to problems unique to this type of structure.
construction of concrete radiation shielding structures                                   radiochemical plants, experimental facilities, and nuclear for such nuclear facilities, which are acceptable to the                                  fuel fabrication plants subject to the following:
  Regulatory staff as methods of complying, in part, with Commission regulations with regard to reducing                                            I. Section 2 of ANSI NI01.6-1972 lists applicable radiation exposures. Much of the information included                                    documents which are intended to supplement this may be applicable to shielding structures for reactors                                  standard. The specific applicability or acceptability of and other nuclear and nonnuclear facilities which require                                these listed documents has been or will be covered concrete radiation shields.                                                              separately in other regulatory guides or in Commission regulations. where appropriate.


This standard was approved by the American National Standards Comrruttee N]01. Atomic Industry Facility June 1973 GUIDE Deipi. Construction and Operation Criteria.
==B. DISCUSSION==
 
2. Section 4.8 of ANSI N101.6-1972 delineates special Subcommittee ANS-li, Radioactive Materials                                      precautions to be observed in the construction of Handling Facilities and Specialized Equipment. of the                                    concrete radiation shields. Where steel or other metals American Nuclear Society has developed a standard                                        are used as aggregate t,. increase the density of the presenting requirements and recommended practices for                                    concrete, the metal should be of such type that it will the construction of concrete radiation shielding                                         not cause hydrogen or other explosive gases to be structures and for certain elements of design that relate                                generated by reaction with the cement.
and it was subsequently approved by the American National Standards Institute (ANSI I on December 2'Z. 1Q'". and designated ANSI NIOI.6.1Q72.
 
The standard discusses agpegate,.
design of concrete mixtures and forms, placement of concrete, design and installatior of penetrations.
 
embedments.
 
metal liners, and penetration plup and outlines testing and quality assurance provistions needed to verify that the desired quality of design and construction has been achieved.
 
The standard does not include detailed treatments of structural design or determination of shield thickness.
 
C. REGULATORY
POSITION The requirements and recommended practices contained in ANSI N101.6-1972. "Concrete Radiation Shields,"'
are acceptable for the construction of radiation shielding structures for hot laboratories.
 
radiochemical plants, experimental facilities, and nuclear fuel fabrication plants subject to the, following:
I. Section 2 of ANSI NI01.6-1q712 lists applicable documents which are intended to supplement this standard.
 
The specific applicability or acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations.


where appropriate.
to problems unique to this type of structure. This standard was approved by the American National                                                  'Copies may be obtained from the American Nuclear Standards Committee NIOi. Atomic Industry Facility                                        Society. 244 East Ogden Avenue. Hinsdale, Illinois 60521.


2. Section A.8 of ANSI N1OI..-Q072 delineates special precautions to be observed in the construction of concrete radiation shields. Where steel or other metals are used as aggrepte t, increase the density of the concrete.
USAEC REGULATORY GUIDES                                        Coe Ofpubished guide may be obtaned by requem indca.ing the divisions desrIsd to the US. Atomic Erurgv Commission. Washington, D.C. 2054S.


the metal should be of such type that it will not cause hydrogen or other explosive gases to be generated by reaction with the cement. 'Copies may be obtained from the Ameri.-can Nuclear Society. 244 Eait Ogden Avenue. Hinsiale.
Regulatory Guides or ISS*ed to describe ed mke                  lvwoiill4 to the public Atitenteio  Director Of Regulatory Standards. Comnments and sol 1tions for menhods accepatmle to she AEC Regulatory staff of Imifes owtongspecific parts of        inovernwts in these guides oe encouraged and should be sent to the Secretary the Comone.on5 - egat.:at1Os.       CdP'isefe te-hrouee used by the seff in            of the Commoonso.    US.  Atomic Energy Commssion. Washington. D.C. 206*4.


litanois 6052
evaluating spec:fic ioblems 4; postulated eaecklnts. or to pro-ide guidance to          Atlefstion: Chief. Public P.o*mengp Staff.


===1. USAEC REGULATORY ===
Ii*cnts. ReapulgO ry Guides    *e not substitutes fw regulations end cooslaei s with them . not required. Methods and iolutions differenit from thoe at out in          The guides ae issue  in the following ten broad divisions:
GUIDES CSS Of Pub e gdnie, n*v be obtained by remterl i nd,cing d",o "a.wd to the US. Atomic Emwrv Comm.es-on.
the gu*id      ill b4 acceptable if they porovde    b at for this findings relu*iste to the resuano or continuance of a permit or    Oicene    by the Commisson.                   1. Power Reactors                         


Wmshnpoo.
===6. Produacts===
                                                                                          2    Reseach end Test Reac ors             


DC. 20546.  Rqulato'v Guofdt we ,uuod to delwbe end Rieke 8*labd to the pihdic A=I..of Otuo. of Stendm Cortoivnts end sualutsm~
===7. Transoortation===
fo twhot~ &cmouO'e to the AEC fteiujtetolv Staff of irrvifivenwuuiti toectac Part of iff aiiiefem A thewe gusda wr# owtoOusagd and thouid be Sent to the Secwemiey th Zp ý.r I :e;;4.o*t.
                                                                                          3. Fuels an Mt erials Facilities            a. OccupefIO*l Helth Publi'shad guides    will be revised    eiw.odimi.  w appropriate, to acornmndsa      4. Envrossmensl*ard siting                  g. Antitrust Review eninnent, and to reflect now informa~tion or eUperleis                                    5. Matarials end Plant Protection          1


-- 00--0400 Mrtwinwn uedb the Staff An of thte Cosmtmiuoi.
===0. General===


US, Atomic ErAwvy Commission, Wah-nton.
3. Section 6.4 of ANSI NIOi.6-1972 does not explain            4. Section 8.7.1 of ANSI Ni0i.6-1972 states, in part.


0.C. 2064S.  owludninig qWeatic ptoWnn 0' or 0tsU~tmd SimiWTS. of to Provid gu.diNo to Atlefltcf t.N4.P~b P,eVoCit*fl StAff.  go.mnnts Regulatory Q.u.dmarl roW tflO4 uuttis for rgltio~ns end con wiiiin -t their". io requied 0010V and solurlim different fromn than. wrt out m The gwdw 01 -uied -the fo4Imy.'q ten b'old dmrsionl the, guide ,11t e acceptable
how some of" the variables which are used in the                that reinforcing steel or other means. be provided for  N'
4 they -0M a bMIG fo th fidni "W t the muiax or cor~nuem of a pens~ or honotO bv the ComN"wo I Pom filieton 6. Productt 2 Aeftewo and Test Rea ots 7,
equations for bending moment and tensile stress are to          transferring shear forces through a construction joini.
3. Fu end Mater,.t.


Fecatitm 9, Occuar.outa Hfeafth Pa*,doheisd gudi wiall bel rteat1d CS.Odiomdtii. " boovitoonte to eceofnsmsedetg
be determined. Therefore this section should not be used       This requirement is not sufficient. Provision should be as a substitute for detailed thermal stress analysis in the     made for adequate means of transferring shear and other desip of temperature reinforcement for control of              forces through the joint.
4 Ettwotn"Wrtal
8,d 5.tq S Artlt,..tt ft.,...mi CC`,i"`"lns and to refer tact .- forrAliiOrt OXCOWWtana
6 matwterw and pis"lant Prt.ort~ 10 G~81a
3. Section 6.4 of ANSI N I0 .6-1972 does not explain how some d" the variables which are used in the equations for bending moment and tensle strew am to be determined.


Therefore this section should not be used as a substitute for detailed thermal stres analysis in the desigp of temperature reinforcement for control of aacking in specific concrete radiation shields.4. Section 8.7.1 of ANSI NIOI.6-1972 sutes, in part.  that rednforcli steel or other means, be provided for tVan erring shoa forces throuOh a wonstructien joint.  This requirement Is not sufficient.
cracking in specific concrete radiation shields.


Provision skould be made for adequaste meam of transferring shear and other forces through the joint.?C'' 3.9.2}}
3.9-2}}


{{RG-Nav}}
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Latest revision as of 01:05, 12 November 2019

Concrete Radiation Shields
ML12220A059
Person / Time
Issue date: 06/30/1973
From:
Office of Nuclear Regulatory Research, US Atomic Energy Commission (AEC)
To:
References
RG-3.009
Download: ML12220A059 (2)


U.S. ATOMIC ENERGY COMMISSION June 1973 REGULATORY

DIRECOoAT OF REGULATORY SANDARDS

GUIDE

REGULATORY GUIDE 3.9 CONCRETE RADIATION SHIELDS

A. INTRODUCTION

Design. Construction and Operation Criteria. and it was subsequently approved by the American National Section 20.101 of 10 CFR Part 20, "Exposure of Standards Institute- (ANSI) on December 22. IPQ2.

Individuals to Radiation in Restricted Areas," states that and designated ANSI N101.6-1972. The standard no licensee shall possess, use, or transfer licensed discusses aggregateo. design of concrete mixtures and material in such a manner as to cause any individual in a forms, placement of concrete, design and installation of restricted area to receive a dose in excess of the limits penetrations. embedments. metal liners, and penetration specified therein. Paragraph (c) of § 20.1 provides that plugs and outlines testing and quality assurance licensees, in addition to complying with the provisions needed to verify that the desired quality of requirements set forth in Part 20, make every reasonable design and construction has been achieved. The standard effort to maintain radiation exposures as far below the does not include detailed treatments of structural design limits specified in this part as practicable. or determination of shield thickness.

Concrete radiation shields can be installed in nuclear facilities such as hot laboratories, radiochemical plants,

C. REGULATORY POSITION

experimental facilities, and nuclear fuel fabrication plants to provide a barrier between personnel and The requirements and recommended practices radiation sources for the purpose cf reducing doses of contained in ANSI N101.6.1972, "Concrete Radiation ionizing radiation received by personnel to as low as Shields,"' are acceptable for the construction of practicable levels. This guide describes practices for the radiation shielding structures for hot laboratories.

construction of concrete radiation shielding structures radiochemical plants, experimental facilities, and nuclear for such nuclear facilities, which are acceptable to the fuel fabrication plants subject to the following:

Regulatory staff as methods of complying, in part, with Commission regulations with regard to reducing I. Section 2 of ANSI NI01.6-1972 lists applicable radiation exposures. Much of the information included documents which are intended to supplement this may be applicable to shielding structures for reactors standard. The specific applicability or acceptability of and other nuclear and nonnuclear facilities which require these listed documents has been or will be covered concrete radiation shields. separately in other regulatory guides or in Commission regulations. where appropriate.

B. DISCUSSION

2. Section 4.8 of ANSI N101.6-1972 delineates special Subcommittee ANS-li, Radioactive Materials precautions to be observed in the construction of Handling Facilities and Specialized Equipment. of the concrete radiation shields. Where steel or other metals American Nuclear Society has developed a standard are used as aggregate t,. increase the density of the presenting requirements and recommended practices for concrete, the metal should be of such type that it will the construction of concrete radiation shielding not cause hydrogen or other explosive gases to be structures and for certain elements of design that relate generated by reaction with the cement.

to problems unique to this type of structure. This standard was approved by the American National 'Copies may be obtained from the American Nuclear Standards Committee NIOi. Atomic Industry Facility Society. 244 East Ogden Avenue. Hinsdale, Illinois 60521.

USAEC REGULATORY GUIDES Coe Ofpubished guide may be obtaned by requem indca.ing the divisions desrIsd to the US. Atomic Erurgv Commission. Washington, D.C. 2054S.

Regulatory Guides or ISS*ed to describe ed mke lvwoiill4 to the public Atitenteio Director Of Regulatory Standards. Comnments and sol 1tions for menhods accepatmle to she AEC Regulatory staff of Imifes owtongspecific parts of inovernwts in these guides oe encouraged and should be sent to the Secretary the Comone.on5 - egat.:at1Os. CdP'isefe te-hrouee used by the seff in of the Commoonso. US. Atomic Energy Commssion. Washington. D.C. 206*4.

evaluating spec:fic ioblems 4; postulated eaecklnts. or to pro-ide guidance to Atlefstion: Chief. Public P.o*mengp Staff.

Ii*cnts. ReapulgO ry Guides *e not substitutes fw regulations end cooslaei s with them . not required. Methods and iolutions differenit from thoe at out in The guides ae issue in the following ten broad divisions:

the gu*id ill b4 acceptable if they porovde b at for this findings relu*iste to the resuano or continuance of a permit or Oicene by the Commisson. 1. Power Reactors

6. Produacts

2 Reseach end Test Reac ors

7. Transoortation

3. Fuels an Mt erials Facilities a. OccupefIO*l Helth Publi'shad guides will be revised eiw.odimi. w appropriate, to acornmndsa 4. Envrossmensl*ard siting g. Antitrust Review eninnent, and to reflect now informa~tion or eUperleis 5. Matarials end Plant Protection 1

0. General

3. Section 6.4 of ANSI NIOi.6-1972 does not explain 4. Section 8.7.1 of ANSI Ni0i.6-1972 states, in part.

how some of" the variables which are used in the that reinforcing steel or other means. be provided for N'

equations for bending moment and tensile stress are to transferring shear forces through a construction joini.

be determined. Therefore this section should not be used This requirement is not sufficient. Provision should be as a substitute for detailed thermal stress analysis in the made for adequate means of transferring shear and other desip of temperature reinforcement for control of forces through the joint.

cracking in specific concrete radiation shields.

3.9-2