Regulatory Guide 3.9: Difference between revisions

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 Label as Withdrawn 01/15/98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


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.
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.
Line 30: Line 31:


==B. DISCUSSION==
==B. DISCUSSION==
Subcommittee ANS-li, Radioactive Materials Handling Facilities and Specialized Equipment.
Subcommittee ANS- I, Radioactive Materials Handling Facilities and Specialized Equipment.


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.
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.


This standard was approved by the American National Standards Committee NIOi. Atomic Industry Facility Design. Construction and Operation Criteria.
This standard was approved by the American National Standards Comrruttee N]01. Atomic Industry Facility June 1973 GUIDE Deipi. Construction and Operation Criteria.


and it was subsequently approved by the American National Standards Institute- (ANSI) on December 22. IPQ2.and designated ANSI N101.6-1972.
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 aggregateo.
The standard discusses agpegate,.  
 
design of concrete mixtures and forms, placement of concrete, design and installatior of penetrations.
design of concrete mixtures and forms, placement of concrete, design and installation of penetrations.


embedments.
embedments.


metal liners, and penetration plugs and outlines testing and quality assurance provisions needed to verify that the desired quality of design and construction has been achieved.
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.
The standard does not include detailed treatments of structural design or determination of shield thickness.


C. REGULATORY  
C. REGULATORY  
POSITION The requirements and recommended practices contained in ANSI N101.6.1972, "Concrete Radiation Shields,"'  
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.
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:
radiochemical plants, experimental facilities, and nuclear fuel fabrication plants subject to the, following:  
I. Section 2 of ANSI NI01.6-1972 lists applicable documents which are intended to supplement this standard.
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.
The specific applicability or acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations.
Line 59: Line 59:
where appropriate.
where appropriate.


2. Section 4.8 of ANSI N101.6-1972 delineates special precautions to be observed in the construction of concrete radiation shields. Where steel or other metals are used as aggregate t,. increase the density of the concrete, 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 American Nuclear Society. 244 East Ogden Avenue. Hinsdale, Illinois 6052
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.


===1. USAEC REGULATORY ===
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.
GUIDES Coe Of pubished 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.
litanois 6052


Comnments and sol 1tions for menhods accepatmle to she AEC Regulatory staff of Imifes owtong specific parts of inovernwts in these guides oe encouraged and should be sent to the Secretary the Comone.on5
===1. USAEC REGULATORY ===
-egat.:at1Os.
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.
 
CdP'isefe te-hrouee used by the seff in of the Commoonso.
 
US. Atomic Energy Commssion.
 
Washington.
 
D.C. evaluating spec:fic ioblems 4; postulated eaecklnts.
 
or to pro-ide guidance to Atlefstion:
Chief. Public Staff.Ii**cnts.
 
ReapulgO ry Guides 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 ill b4 acceptable if they porovde b at for this findings to the resuano or continuance of a permit or Oicene by the Commisson.


1. Power Reactors 6. Produacts 2 Reseach end Test Reac ors
Wmshnpoo.


===7. Transoortation===
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~
3. Fuels an Mt erials Facilities a.
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.


Helth Publi'shad guides will be revised eiw.odimi.
-- 00--0400 Mrtwinwn uedb the Staff An of thte Cosmtmiuoi.


w appropriate, to acornmndsa
US, Atomic ErAwvy Commission, Wah-nton.
4.


siting g. Antitrust Review eninnent, and to reflect now informa~tion or eUperleis
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
5. Matarials end Plant Protection
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,
1
3. Fu end Mater,.t.


===0. General ===
Fecatitm 9, Occuar.outa Hfeafth Pa*,doheisd gudi wiall bel rteat1d CS.Odiomdtii. " boovitoonte to eceofnsmsedetg
3. Section 6.4 of ANSI NIOi.6-1972 does not explain how some of" the variables which are used in the equations for bending moment and tensile stress are to be determined.
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 stress analysis in the desip of temperature reinforcement for control of cracking in specific concrete radiation shields.4. Section 8.7.1 of ANSI Ni0i.6-1972 states, in part.that reinforcing steel or other means. be provided for transferring shear forces through a construction joini.This requirement is not sufficient.
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.


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


{{RG-Nav}}
{{RG-Nav}}

Revision as of 17:49, 31 August 2018

Concrete Radiation Shields. Label as Withdrawn 01/15/98
ML003740214
Person / Time
Issue date: 06/30/1973
From:
Office of Nuclear Regulatory Research
To:
References
RG-3.009
Download: ML003740214 (2)
v • d • e


U.S. ATOMIC ENERGY COMMIIISION

REGULATORY

DIRECTORATE

OF REGULATORY

STANDARDS

REGULATORY

GUIDE 3.9 CONCRETE RADIATION

SHIELDS

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.

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.

Much of the information included may be applicable to shielding structures for reactors and other nuclear and nonnuclear facilities which require concrete radiation shields.

B. DISCUSSION

Subcommittee ANS- I, Radioactive Materials Handling Facilities and Specialized Equipment.

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.

This standard was approved by the American National Standards Comrruttee N]01. Atomic Industry Facility June 1973 GUIDE Deipi. Construction and Operation Criteria.

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.

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.

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.

litanois 6052

1. USAEC REGULATORY

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.

Wmshnpoo.

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~

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.

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

US, Atomic ErAwvy Commission, Wah-nton.

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

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,

3. Fu end Mater,.t.

Fecatitm 9, Occuar.outa Hfeafth Pa*,doheisd gudi wiall bel rteat1d CS.Odiomdtii. " boovitoonte to eceofnsmsedetg

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.

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


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