Regulatory Guide 5.23

(Task SG 045-4), Revision 1, in Situ Assay of Plutonium Residual Holdup

ML003740013
Person / Time
Issue date:	02/29/1984
From:	Office of Nuclear Regulatory Research
To:
References
RG-5.23 Rev 1
Download: ML003740013 (20)

Revision 1*

February 1984 U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY GUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 5.23 (Task SG 0454)

IN SITU ASSAY OF PLUTONIUM RESIDUAL HOLDUP

information obtained in the holdup survey can be used to

A. INTRODUCTION

locate principal plutonium accumulations and to ensure that other areas of the process contain less than the Part 70, "Domestic Licensing of Special Nuclear detectable amount of plutonium. Once located, substantial Material," of Title 10 of the Code of Federal Regulations accumulations can be recovered, transforming the pluto requires licensees authorized to possess more than 1 kilo nium to a more accurately measurable inventory compo gram of plutonium to calculate a material balance based nent. Having reduced the amount of plutonium holdup, on a measured physical inventory at intervals not to the standard error on the remeasurement of the remaining exceed 2 months. Further, these licensees are required to holdup may be sufficiently reduced to be compatible with conduct their nuclear material physical inventories in overall SEID requirements.

compliance with specific requirements set forth in Part 70.

Inventory procedures acceptable to the NRC staff are Any guidance in this document related to information detailed in Regulatory Guide 5.13, "Conduct of Nuclear collection activities has been cleared under OMB Clearance Material Physical Inventories." No. 3150-0009.

Plutonium residual holdup is defined as the plutonium

B. DISCUSSION

inventory component remaining in and about process equipment and handling areas after these collection areas Plutonium accumulates in cracks, pores, and zones of have been prepared for inventory. Whenever possible, poor circulation within process equipment. The walls of process equipment should be designed' and operated so as process vessels and associated plumbing often become to minimize the amount of holdup. In this guide, proce coated with plutonium during solution processing. Surfaces dures acceptable to the NRC staff for the in situ assay of internal and adjacent to process equipment, especially the plutonium residual holdup are described. glovebox walls and floors, accumulate deposits of pluto nium that can become appreciable. Plutonium also accu Assay information may be used in one of two ways: mulates in air filters and associated ductwork. The absolute amounts of plutonium holdup must be small for efficient

1. When the standard error (estimator) of plutonium processing and proper hazards control. However, the total holdup is compatible2 with constraints on the overall holdup can be large relative to the plant inventory differ standard error of the inventory difference (SEID), the mate ence (ID) but have no significant impact on the ID if it rial balance can be computed using the measured contents remains reasonably constant. It is the change in the of plutonium holdup. Additional cleanout and recovery for holdup between beginning inventory and ending inventory accountability will then not be necessary. that may impact the ID.

2. When the standard error of plutonium holdup is not The measurement procedures described in this guide compatible with constraints on the overall SEID, the involve the detection of gamma rays and neutrons that are spontaneously emitted by the plutonium isotopes. Because are the gamma rays of interest are emitted by the major isotope, Design features to minimize holdup in process equipment

1 the subject of a series of regulatory guides (5.8, 5.25, and

5.42). 23gpU, gamma ray assay is the preferred method whenever 239 its acceptance criteria are satisfied. The amount of pu

2 Compatibility exists when the contribution of the standard to error of the holdup to the total plant SEID is not large enough cause the overall SEID to exceed allowed limit

s. If the plant SEID

exceeds allowed limits because of an excessive contribution from The substantial number of changes in this revision has made it the holdup standard error, compatibility does not exist and the impractical to indicate the changes with lines in the margin.

remedial steps of paragraph 2 needto be taken.

Comments should be sent to the Secretary of the Commission, USNRC REGULATORY GUIDES U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch.

Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of Implementing The guides are issued in the following ten broad divisions:

specific parts of the Commission's regulations, to delineate tech niques used by the staff in evaluating specific problems or postu 1. Power Reactors 6. Products lated accidents or to provide guidance to applicants. Regulatory 2. Research and Test Reactors 7. Transportation Guides are not substitutes for regulations, and compliance with 3. Fuels and Materials Facilities 8. Occupational Health them is not required. Methods and solutions different from those set 4. Environmental and Siting 9. Antitrust and Financial Review out in the guides will be acceptable if they provide a basis for the 5. Materials and Plant Protection 10. General findings requisite to the issuance or continuance of a permit or Government license by the Commission. Copies of issued guides may be purchased at the current guides in spe Printing Office price. A subscription service for future Office.

from Printing This guide was Issued after consideration of comments received cific divisions is available through the Government prices may the public. Comments and suggestions for improvements in these Information on the subscription service and current GPO Commission, guides are encouraged at all times, and guides will new Informaas be revised, be obtained by writing the U.S. Nuclear Regulatory appropriate, to accommodate comments and to reflect Washington, D.C. 20555, Attention: Publications Sales Manager.

tion or experience.

holdup in a piece of equipment is proportional to the relatively uniform cross section. When a collection zone measured intensity of the emitted gamma rays after suitable contains a complex item of equipment with significant corrections are made for attenuation by intervening mate self-shielding properties, the uncertainty in the holdup, rials, for self-attenuation by plutonium, for scattering, for measurement may be primarily due to attenuation of K

geometrical factors, and for background radiation. radiation in the internal structure. In such cases, neutron assay from the outside and thermoluminescent dosimeter If plutonium is held up in furnaces, grinders, or other assay from the inside may be applicable.

heavy equipment that is too dense to permit the escape of gamma rays, an assay based on spontaneous fission neutrons If delineation of collection zones is not possible, two from the even isotopes of plutonium may be possible. This alternatives are experiments with mockup geometries or technique requires knowledge of the isotopic composition complex numerical calculations.

of the plutonium, some knowledge of its chemical form, and knowledge of the presence of other radionuclide 2. APPLICABLE METHODS AND INSTRUMENTS

impurities.

Two considerations are critical to the selection of Thermoluminescent dosimetry is a third technique that methods and instruments. First, to perform an assay, one can be used to measure holdup from the inside of large must ensure that the plutonium radiations reach the detector pieces of equipment. This technique is also useful for and are detected. Second, the observed response must be carrying out measurements in an unobtrusive manner attributable to the collection zone being assayed. Therefore, outside normal plant operating hours. the assay scheme is developed around penetrating radiations, and the detector is collimated to provide for sufficient For all three techniques, the proportionality factors directionality in the response to resolve a collection zone between amount of holdup and detector response are best from its neighboring zones and from the background.

determined prior to the holdup measurement by assays of Finally, some effort may be necessary to employ external

"shadow shielding" to block radiation being produced in known quantities of plutonium distributed in well-defined and representative geometries, as discussed below. adjacent collection zones from the field of view of the collimated detector.

1. DELINEATION OF COLLECTION ZONES

2.1 Gamma Ray Assay Typical plutonium process facilities comprise a number of interconnected gloveboxes that contain work areas and Under closely controlled conditions, the measured most process equipment, in-process storage areas, and plutonium gamma ray spectrum can be interpreted in terms self-contained process equipment. Also, solution process of the abundance of each gamma ray emitter present in the ing requires tanks, plumbing, and pumping equipment, sample. Because of the large number of gamma rays (Refs. 1 which are often located in close proximity to the glovebox and 2) present, many regions of the observed spectrum are lines. Finally, storage areas for feed, scrap and waste, and characterized by overlapping lines. To accomplish the assay, final product are often located in close proximity to the it is necessary to select an appropriate spectral region and plutonium process area. provide a detection system with sufficient resolution to measure the activity from the isotopes of interest.

To accomplish the holdup measurements, it is essential to consider the facility in terms of a series of zones that can Gamma ray assay has an advantage over neutron assay in be independently assayed. Such zones are designated that the emissions are primarily from the principal isotopes

"collection zones." Each plutonium-processing facility can of interest. Because of the hiih emission rate of gamma be conceptually divided into a series of contiguous collection rays, a detection sensitivity of less than 1 gram is generally attainable.

zones on the basis of process activities and collection geometries. Individual machines, filters, pipes, tanks, The most useful portion of the spectrum for holdup gloveboxes, or surface areas that can be isolated from one another may be suitable discrete collection zones. Great assay is the 2 3 9 pu gamma ray complex in the 375- to

45 0-keV range. 3 The yields of these lines are given in care is needed to define all collection zones so that (1) the Table 1.

assay of the zone can be performed with a minimum of interference from nearby zones, (2) the detector can be positioned reproducibly and in such a way that the radiation being measured experiences a minimum, or easily predicted, attenuation in the apparatus being measured, and (3) the 3

1n typical Nal detectors (with energy resolution of 10 percent distribution of material in the zone can be represented by at 414 keV), the 414-keV photopeak will produce counts in the one of the distribution geometries used in the calibration approximate energy range of 373 to 455 keV. Thus, an energy window from 375 to 450 keV will include most of the 414-keV

procedure described below. full-energy counts for a variety of detector resolutions. Further more, suca, window setting will include a significant fraction of the

375-keV P9Pgamma rays (see Table 1), but will also exclude Gamma ray assay for plutonium holdup is practical 'mosorftihe otentially interfering 332-keV gamma rays from when the collection zone consists of a single structure of

5.23-2

Table 1 2 inches (5 cm) with a thickness of 2 inches is recommended.

For germanium detectors, a moderate-volume coaxial

23 9 detector is recommended.

PROMINENT GAMMA RAYS FROM pu IN 375- to 450-keV ENERGY RANGE

2.1.2 Collimatorsand Absorbers for Gamma Rays Intensity

2 39 Pu) A shaped shield constructed of any heavy-element Energy (y/sec-g material is appropriate for gamma ray collimation. For cost,

375.0 3.59 x 104 availability, and ease of fabrication, lead is recommended.

380.2 0.70 x 104 Less than 2 percent of all 400-keV gamma rays striking a

382.7 0.59 x 104 1.5-cm-thick sheet of lead will pass through without suffer

0.26 x 104 ing an energy loss.

392.5

393.1 1.01 x 104

413.7 3.43 x 104 The collimator will be most effective when it is con

422.6 0.27 x 104 centric about the crystal and photomultiplier and com pletely covers the photomultiplier bas

e. Extending the

9.85 x 104 collimator forward of the crystal at least a distance equal to Total half the diameter of the crystal, and preferably the full diameter, is recommended (Ref. 5). Making this distance variable to reproducible settings will permit adjustment over a range of collection zone sizes. However, it is highly

2.1.1 Gamma Ray Detection Instruments desirable to select collection zones and counting geometries so that one collimator setting will suffice for all measure Gamma ray detection systems consist of a scintillation ments. This will simplify the calibration procedures because or semiconductor gamma ray detector and appropriate the calibration constants depend strongly on the dimensions electronics (Refs. 3 and 4). Required electronics include at and placement of the collimator aperture.

least a single-channel analyzer and a timer-scaler unit. A

second single-channel analyzer viewing the same detector The collimator not only defines the effective field of pulses used to determine the background radiation correc view but also shields the detector from unwanted radiation.

tion is a timesaving feature. A number of portable battery To effectively accomplish this latter purpose, the collimator powered systems are commercially available for this applica material must also cover the rear of the detector. This is tion.

usually easy to achieve with portable Nal detectors but requires more effort when germanium detectors are used.

The detection efficiency andresolution (10 to 15 percent) Intensive 50- to 100-keV X-ray radiation and 60-keV

of NaI(Tl) is generally adequate for holdup measurements. 241 Am gamma ray radiation are often emitted by process CdTe, Ge(Li), and high-purity germanium (also known as equipment, and this radiation can tie up the detector intrinsic germanium) detectors have better resolution than electronics unnecessarily. A 1.5-mm-thick layer of lead (on NaI(Tl) but are more costly and more difficult to operate. the outside) and a 0.75-mm-thick layer of cadmium (on the For more information on Ge(Li) and intrinsic germanium inside) may be placed against the front face of the detector detectors, see Regulatory Guide 5.9, "Guidelines for to alleviate this problem. This graded energy shield will Germanium Spectroscopy Systems for Measurement of absorb most of the low-energy photons incident on the Special Nuclear Material," and the references cited therein. detector without substantially reducing the number of gamma rays detected in the 375- to 450-keV range.

237 The 332.3-keV gamma ray from U, a short-lived

24 1 the principal inter 2.1.3 Check Source for Gamma Ray Assay

(6.75 days) daughter of pu, is usually ference for 2 39 Pu assay by Nal detection of the 375- to

7 It is important to check the operation of the detection

450-keV complex. If the 2 3 U is in equilibrium with

24 1 pu, the intensity of this gamma ray is 1.15 x 106 system each time the instrumentation is moved or otherwise disturbed (e.g., power outage) during the course of each y/sec-g 2 pu. Since this gamma ray is also emitted in the

4 1 inventory sequence. Either recalibrating one or more decay of 241 Am, the interference from this decay branch collection zones and comparing the results to previous may also be important in case of preferential americium analyses or testing the instrument with a check source is holdups. To avoid this interference when using Nal detectors, appropriate. When the response remains within the expected the assay energy window is adjusted to span the range from value, the previous calibration data are assumed to be valid.

390 to 450 keV for plutonium holdup with high americium If not, the energy window may have shifted, or the unit content.

may be in need of repair and recalibration.

An appropriate check source enables the stability of the Detector crystal dimensions are selected to provide a assay instrument to be tested at any location. Such a source high probability of detecting gamma rays from the 375- to can be prepared by implanting a small encapsulated plutonium

450-keV complex and a low probability of detecting sample (containing '.,0.5 gram of plutonium) in the face of high-energy radiation. For NaI, a crystal diameter of

5.23-3

a plug of shielding material. The plug is shaped to fit and low gamma ray sensitivity in the detectors are important.

close the collimator channel, and the source is positioned to Gas-filled proportional counters containing He or BF 3 are be adjacent to the crystal when the plug is in place. suitable for this purpose. Typical fill pressures are 1 to 4 atmospheres. One advantage of 3 He for in-plant applications The check source is fabricated in a manner that will is that the operating voltage of 3He counters is about ensure its internal stability. Other than radiations increasing 75 percent of that required for BF 3 counters.

from the ingrowth of 2 4 1 Am, the emission rate of the check source should remain constant. The efficiency of 3 He and BF 3 counters increases as the energy of the neutrons decreases. Embedding gas-filled

2.2 Neutron Assay counters in polyethylene to moderate the incoming neutrons to thermal or epithermal energies will improve their effi Neutrons are emitted in the spontaneous fission of 238Pu, ciency. A nearly optimum design can be obtained by center

24°Pu, and 242Pu and through the interaction of emitted ing the counters in 10 cm of polyethylene with 2 to 3 cm alpha particles with certain light nucleL These neutrons of polyethylene between adjacent counters.

suffer little attenuation in passing through uranium or plutonium or through most structural and containment To shield the detector from low-energy neutrons that materials. Glovebox windows may reduce the energy of may produce a complicated response pattern, the modera emerging neutrons, but, because of their regular and con tor material is covered with a thermal neutron absorber.

stant shape, their effect can generally be factored into the Cadmium sheeting approximately 0.075 cm thick may be assay calibration. used for this application.

To be useful for the assay of plutonium holdup, the 2.2.2 Collimatorsfor Neutron Detectors neutron production rate per gram of plutonium must be known. The spontaneous fission contribution to the total To assay a specific collection zone in the presence of neutron production can be computed from basic nuclear other distributed sources of plutonium, it is necessary to data after the isotopic composition of the contained collimate the detector. This is accomplished by stopping plutonium has been determined. Computing the (ca,n) neutrons coming to the detector from all directions except contribution requires a knowledge of the chemical form of the desired one. The cadmium surrounding the detector will the plutonium and the amount and distribution of certain stop essentially all neutrons striking the detector with high-(ca,n)-yield target materials. energies below 0.4 eV. By adding moderator material around the outside of the detector in all directions except The background count rate from neutron detectors may for the collimator channel, neutrons coming from be a substantial part of the observed activity, often corre unwanted directions will lose energy in this shield and will sponding to as much as 20 grams of plutonium in typical be absorbed in the cadmium cover. For each 6 inches holdup assays. Thus, neutron assay is primarily applicable (15 cm) of polyethylene added, the collimator assembly to the measurement of significant accumulations of pluto provides a factor of approximately 10 in the directionality nium. of the response.

The measured neutron yield from prepared calibration An example of a collimated neutron detector assembly standards is used to calibrate each neutron assay collection for plutonium holdup assay is shown in Figure 1. This zone. In the appendix to this guide, a method is given to assembly has a polyethylene shield thickness of 6 inches calculate the anticipated neutron yield. This method (15 cm) and a directionality of 10 to 1. The combined provides the ability to calculate the neutron yield when the weight of the detector and collimator exceeds the require isotopic or impurity composition of the plutonium holdup ments for a hand-held probe. For this reason and to provide is different from that of the calibration standards. The for reproducible positioning at each assay, a sturdy cart method can be used to calculate a ratio of the neutron housing such a detector and its associated electronics is production rate of the unknown material to the neutron recommended. In order to assay items at different heights, production rate of the standard material. The yield from the capability to raise and lower the assembly to reproduc the holdup material is then determined by multiplying the ible settings is needed.

measured "known" material yield by the computed ratio.

An example of a small commercially available hand-held

2.2.1 Neutron Detection Instruments detector is given in References 5 and 6. This Shielded Neutron Assay Probe (SNAP) is 12 inches (30.5 cm) high To effectively employ the spontaneous neutron yield as and 10 inches (25.4 cm) in diameter and contains two 3He a measure of plutonium holdup, it is necessary to detect the detectors. It includes a 2-inch-thick (5 cm) polyethylene neutrons in the presence of a more intense gamma ray shield that provides a directionality of 3 to

1. The SNAP

background and to collimate the detector so that neu has been used to measure plutonium holdup, UO2 F2 trons emanating from the collection zone under assay are holdup, and UF 6 enrichment. It is recommended for the preferentially detected. assay of well-defined concentrations of plutonium in pumps, grinders, pipe elbows, or other items of equipment Holdup assay is performed under in-plant conditions where portability and accessibility are more important than where ruggedness, portability, high neutron efficiency, and directionality.

5.23-4

DETECTOR CABLE ACCESS CHANNEL

(TOP SECTION ONLY) r-.

117

1 I5.1cm 15.1cm 3" IT

4.5cm FRONT VIEW -- ,c + TOP VIEW

+

N DETECTOR

"HANNELS

"I 2.6cmnDIAl METER (TYP)

I I I I

IIFRONT I

I II9cI

VIEW

6 3c I I I IIl I

m W9mITH0,7I CDIUMSI E

4 DETECTOR TUBE SUBASSEMBLY

4 Assembly includes three BF 3 or 3He tubes (2.54 cm diameter). Unit can be modified to increase or decrease the number of tubes. Moderator thickness of 15 cm provides u 10:1 directionality. Addi tional polyethylene can be added to improve directionality (e.g., 30 cm polyethylene provides *, 100:1 directionality). Components are bolted or strapped to remain in a fixed configuration.

Figure 1. Collimated Neutron Detector Assembly for Plutonium Holdup Assay

5.23-5

3. ISOLATION OF COLLECTION ZONES

A third example of holdup measurement by neutron detection is given in Reference 7. In this case, a completely

3 To ensure that each collection zone is independently uncollimated polyethylene slab containing a row of He assayed, it is necessary to shield the detector from all detectors was suspended in midair in some of the processing radiations except those radiations emanating from the rooms of an industrial plutonium facility. The response of collection zone being assayed. This is principally accom the detector was found to be proportional to the total plished through the use of the collimators described in room holdup if the plutonium was reasonably uniformly Sections B.2.1.2 and B.2.2.2. Two additional means exist to distributed and if the room was isolated from external isolate a collection zone, detector positioning and shadow sources. The calibration procedure for the use of. this shielding.

detector will not be described here. However, it is recom mended as a means for quickly verifying total room holdup 3.1 Detector Positioning when measurements of the holdup in individual items or equipment are not needed.

An unobstructed side view of a collection zone is pre

+/-erred. When plutonium is located behind the zone under

2.2.3 Check Source for Neutron Assay assay in another collection zone or a storage facility, an additional background assay may be performed with the To ensure the proper operation of the neutron assay detector above or below the collection zone and pointing at system prior to making an assay, it is necessary to test the the material behind the zone under assay. It is important to response of the instrument. An appropriate neutron assay prevent, or account for, moving objects within the field of check source can be measured, or the detector response for view. If this is not done, variations in shielding and scatter one or more collection zones can be recalibrated and ing can affect the measurement.

compared to the results of previous calibrations.

3.2 Shadow Shielding An appropriate neutron assay check source can be prepared by implanting a small encapsulated plutonium It may not be possible to avoid interfering radiations by source (containing about 5 grams of plutonium) into collimator design or by choosing the detector position for the face of a plug of neutron moderating material (see assay. In such cases, it may be possible to move a shield Figure 2). The plug is fabricated to fit and close the colli panel between the source of interfering radiations and the mator channel. When the response from the check source collimator zone under assay. If the shield panel is very thick remains within the expected value, the previous calibration and its dimensions match or exceed the back side of the data are assumed to be valid. collection zone under assay, no interfering radiations will penetrate through the shadow shield to the detector. While such characteristics are desirable, the size of such a shield

2.3 Thermoluminescent Dosimeter (TLD) Assay would limit its transportability. A rectangular panel mounted on wheels as an upright panel and containing %5 cm of neu Crystals of LiF, CaF 2 , CaSe 4 , or other compounds can tron moderator (e.g., benelex, WEP, or polyethylehe) and store energy at manganese or dysprosium impurity centers ,0.5 cm of lead sheet is recommended. To use such a when they are struck by gamma or neutron radiation. At panel, it is necessary to measure the response of the collec some later time, the crystals can be heated rapidly to tion zone with and without the shield in place. Also, the several hundred degrees centigrade to induce thermo gamma and neutron transmission factors of the shield itself luminescence. The light output at this time is proportional must be measured beforehand with a representative pluto to the amount of radiation received. Thermoluminescent nium sample. From these measurements, the assay of the detectors that are primarily gamma sensitive, graded X-ray collection zone can be corrected for background radiation shields, read-out instrumentation, and other accessories are transmitted through the shield.

commercially available.

4. CALIBRATION FOR HOLDUP MEASUREMENTS

TLDs have been used to measure the holdup in glove boxes by placing them at regular intervals on the outside 4.1 Basic Counting Geometries surfaces. The TLDs are left in place overnight in order to accumulate a measurable dose. Accuracies of +20 percent There are three fundamental counting geometries that relative to cleanout values are reported for plutonium of can be used to represent most collection zones. These known isotopic composition. TLDs have also been used to geometries are distinguished by the spatial distribution of measure the holdup in the interior of large furnaces that are the source material and the resulting dependence of the not accessible by other means. For both of these examples, detector counting rate on the source-to-detector distance, r.

calibration requires either careful dose and geometry calculations or mockups of the actual collection zone. 4.1.1 Point Source Because their use is relatively new and only a few published references exist (Refs. 8 and 9), TLDs will not be discussed If the material being assayed is distributed over an area further in this guide. However, they could be useful for with dimensions that are small compared with the source- special applications.

5.23-6

COLLIMATOR

TOP VIEW

-CHECK SOURCE

COVER

CHECK SOURCE

FRONT VIEW

Figure 2. Neutron Collimator Channel Plug and Check Source

5.23-7

to-detector distance and if the material resides entirely sources although neutron assay is usually restricted to within the detector field of view, the zone can be treated as dense, isolated items of equipment that can be represented a point source. The detector count rate for a point source as point sources. For both neutron and gamma measure varies inversely as the square of the source-to-detector ments, corrections to the point and line source calibrations distance (count rate is proportional to l/r 2 ). Any equip for different detector distances are made using the 1/r 2 or ment measured at great distances or any small pieces of 1 /r count-rate dependence, respectivel

y. For further detailed

4 equipment or equipment parts fall in this category. discussion of the measurement of detector responses for these basic geometries, see Reference 10.

4.1.2 Line Source For gamma ray assay, the calibration of the point source If the material being assayed is distributed along a linear response can be accomplished with a well-characterized path so that only a segment of that distribution length is encapsulated standard plutonium foil smaller in size than contained in the detector field of view, the zone can be the detector collimator opening. This foil can also serve as treated as a line source. The detector count rate for a line the check source for verification of the continued stability source varies inversely as the source-to-detector distance of the instrument settings in the field. It is important that (count rate is proportional to I/r). Examples of this type of care be taken in the preparation of this calibration standard holdup geometry include isolated sections of piping and to ensure that the amount of encapsulated 2 3 9 pu is well long, narrow ducts or columns. known. It is also important to measure the gamma ray attenuation through the encapsulating material and the

4.1.3 Area Source self-attenuation of the plutonium foil and to correct the calibration standard response to compensate for these If the material being assayed is spread over an area so effects. Enough 2 3 9 Pu needs to be encapsulated in this large that it covers the full field of view of the detector for standard to provide count rates that will ensure good a range of source-to-detector distances, the zone can be statistical precision of the calibration in a reasonable period assayed as an area source. As long as the material being of time.

viewed is uniformly distributed, the detector count rate will be independent of the source-to-detector distance.

However, for holdup applications, uniform material distribu For neutron assay, it is probably necessary to encapsulate tion is rare; so the source-to-detector distance can affect the a larger amount of material in the calibration standard instrument response and needs to be specified. Furthermore, because the spontaneous neutron production rate is signifi when there are several measurement locations covering a cantly less than the 375- to 450-keV gamma ray production large area (such as a floor), it is important to maintain the rate. A quantity of 50 to 100 grams of plutonium is ade same source-to-detector distance (even if material distribu quate for most applications. Again, it is important to know tion is uniform within a given measurement area) so that the exact quantity and isotopic composition of the pluto the number of measurement areas needed to cover the nium. Also, the neutron calibration standard may generate entire area remains constant. Examples of this type of assay more neutrons than directly attributable to the spontaneous geometry include floors, walls, glovebox floors, and large fission and (a ,n) reactions. Because a relatively large quantity rectangular ducting. of PuO 2 Ls encapsulated in the neutron assay calibration standard, some spontaneous fission or (a,n) neutrons may

4.2 Calibration of Detector Response be absorbed in 239pu or 24 1pu nuclei, producing additional neutrons through the induced fission reactio

n. The amount

4.2.1 Mockup of Known Material Distributions of multiplication depends in a complex manner on the amount and distribution of PuO 2 and on the surrounding When a gamma ray assay is used and a collimator setting medium (Ref. 11). For 50 grams distributed in the bottom has been selected, the detector responses for the three basic of a 4-inch-diameter (10 cm) can, a self-multiplication of source distribution geometries listed above need to be 0.5 percent of the total neutron output would be typical.

determined. For the point source, the response is expressed At 100 grams, 1 to 2 percent may be expected. Thus, this as (counts per minute)/gram of 2 3Pu at a specified source effect is typically smaller than other errors associated with to-detector distance. For the line source, the response is holdup measurements and can be neglected if the standard expressed as (counts per minute)/(gram of 2 3 9 pu per unit contains 100 grams or less of well-distributed material. The length) at a specified source-to-detector distance. For the chemical and isotopic composition of the plutonium will area source1 the response is expressed as (counts per minute)/ have a larger effect, as described in the appendix to this (gram of 39pu per unit area) at a specified source-to guide.

detector distance. When neutron assay is used, the response for a point source is expressed as (counts per minute)/gram of 24°Pu effective at a specified source-to-detector distance. The measurement of the line source response is best Calculation of 2 4 °pu effective from the plutonium isotopic accomplished by constructing a cylindrical surface distribu composition is described in the appendix to this guide. tion of plutonium with the aid of large foils. It is also Analogous expressions can be given for line and area possible to establish the line source response using a point

4Caution: small deposits of plutonium could exhibit very large source, as described in Reference 4. The line source geom gamma ray self-attenuation and could therefore require great care in etry is closest to that of the pipes and ducts likely to be analysis or could require neutron assay. encountered in actual measurements.

5.23-8

measurements of the detector responses can be made. This The area source response can be measured with the same procedure would be a valuable supplement to calibration plutonium foils laid flat to simulate the expected distribu data obtained from mockups of standard counting geom tion on surfaces such as walls and floors. The area response etries and comparisons with cleanout recovery data.

can also be established using a point source. The point source is measured at different radial distances from the

5. HOLDUP MEASUREMENTS AND STANDARD ERROR

center of the field of view of the collimated detector. The response at each radial distance is weighted by the area of a The measurement of holdup in a complex plant environ concentric ring at that radius. From these weighted re ment can involve a very large number of measurements. In a sponses, it is then possible to calculate the area of a circular stable plant environment where the process behavior is well region of uniform plutonium deposition that would yield this known and well characterized, it may be possible to arrange the same total response as the point source. From of 23 9 Pu per the holdup measurement program so that:

equivalent area, the expected response/(gram unit area) can be derived. Further useful details on this a. Careful and extensive holdup measurements are made procedure may be found in Reference 12. For both line and infrequently (e.g., annually) and area calibrations, the self-attenuation of the foils or point sources also needs to be taken into account.

b. At more frequent intervals (e.g., at inventory times),

careful measurements are made in known problem There may be special material distribution geometries areas, and "spot check" measurements are made in in the facility that are not readily represented by one of the the other, less used, zones where accumulations are three basic configurations described above. These special known to be low.

geometries may be mocked up as carefully as possible with large plutonium foils and point sources to produce a usable Such management of measurement resources can result in a detector response calibration for these special cases. Examples very effective holdup measurement program at minimum of special cases might be concave or convex equipment costs surfaces or the internal volume of a rectangular cavity (see Ref. 10). Because material particle sizes (or material deposit 5.1 Holdup Measurements thicknesses) have a significant effect on the self-attenuation of the gamma ray signals, it is important to use (whenever In performing the holdup measurements, one must be practical) well-characterized process material for preparing aware of the large variability in holdup assays arising calibration standards and to duplicate to the extent possible primarily from variability in the measurement conditions process holdup distribution relative to particle size or thick (e.g., background, geometry, gamma ray or neutron attenua ness. Furthermore, holdup in floors is often deposited at tion, material distribution). Accordingly, it is important various depths into the floor, rather than on the surface.

to perform the assays from as many vantage points as Thus, calibration standards for such measurements need to possible for each collection zone. If this is impractical on a incorporate the appropriate geometry and matrix effects.

routine basis because of time or space constraints, one Core samples of a floor may be needed to establish typical might consider multiple measurements initially on a collec concentrations at various floor depths.

tion zone, followed by fewer routine measurements at repre sentative assay sites. Careful thought in the selection of Calibration of the holdup measurement system using this measurement points and measurement strategy will mini procedure is recommended until a history of comparisons mize ambiguities in the interpretation of the data.

between predicted and recovered holdup quantities is developed. If it is possible to take holdup measurements

5.1.1 Selection of Collection Zones and Detector before and after the cleanout of a piece of shut-down Positions process equipment, they can be used to establish this comparison history and improve the accuracy of the Location and configuration of collection zones are calibration for each collection zone.

established on the basis of a detailed physical examination and a radiation survey of the physical layout of the facility.

4.2.2 Measurement of CalibrationSources in Actual Preliminary measurements are needed to determine the ProcessEquipment optimum detector positions for the holdup assays. If nonuniform distribution of material in a collection zone is One method for calibrating detector response to holdup suspected or if the process apparatus is sufficiently compli radiation in process equipment is to place a known calibra cated to require extensive attenuation corrections for tion source in various positions in that equipment and certain counting geometries, multiple measurements are record the detector responses. In this way, the overall advisable for the collection zone. More than one detector detector response (including all corrections for attenuation position may be necessary. In the cases where radiation and geometry) is determined empirically. Unfortunately, surveys have pointed out zones of high holdup collection, this procedure is impractical, if not impossible, in process extra care will be necessary in the holdup measurements for equipment already in operation. However, if those respon those zones to minimize their contribution to the overall sible for holdup assays are made aware of occasions when holdup variability. Where radiation surveys show little hold new equipment is brought into the plant for installation in up, proportionately less time need be budgeted. Selecting the process, calibration sources can be conveniently placed optimum detector positions includes consideration of the in the equipment before its installation and the empirical

5.23-9

the individual measurements. Further, the variability need to conveniently measure the line-of-sight background between these measurements can provide an indication of by moving the detector to one side without changing its the measurement uncertainty.

orientation.

5.1.3 Gamma Ray Attenuation Corrections

5.1.2 Holdup Measurement Procedure To obtain useful assay results by detecting 375- to The measurement and analysis of gamma or neutron

450-keV gamma rays, it is necessary to correct each assay radiation from a collection zone may be carried out by for attenuation of the signal, either within the plutonium treating the material distribution as a point, line, or area holdup material or by structural materials. Without this source, as described in Section B.4.1, or as one of the critical correction, the assay is no more than a lower limit special cases that may have been measured, as mentioned in on the true holdup value. The attenuation correction may Section B.4.2. If the nature of the material distribution is be based on calculations of known attenuation in uniform uncertain for a particular detector position, a measurement materials, on earlier measurements of materials similar to of the detector counting-rate dependence on the source-to those found in the plant equipment, or on direct measure detector distance, r, may reveal the most appropriate ments of gamma ray transmission through the actual counting-rate geometry with which to interpret thc data.

equipment. Details on establishing an appropriate attenua tion correction are given in Laboratory Exercise No. 4 of After the assay positions for the detector and shadow Reference 4. Additional treatment of gamma ray attenua shields are established for each collection zone, permanent tion corrections is given in Reference 13.

markings that indicate detector location (including height)

and orientation will ensure reproducibility of subsequent

5.1.4 Gamma Ray Interferences measurements for these positions. Uniquely labeling each assay site will facilitate unambiguous reference to each Variability in the observed gamma ray response may measurement and its location in the assay log. Furthermore, arise as a result of the presence of extraneous gamma ray assay site labels and markings can indicate whether neutron emitters or as a result of fluctuations in the background or gamma ray measurements are to be made. Alphabetic from the Compton scattering of higher energy gamma rays.

labels (for example, "G" for gamma and "N" for neutron)

The magnitude of this effect is generally small. It can be and color-coded tape markings of the sites would be useful.

monitored by observing the spectrum with a multichannel Protecting the markings (for example, with clear epoxy)

analyzer, but, unless data on periodically recovered holdup will ensure their long-term durability.

accumulations are in error, this contribution can be ignored.

After measuring the gamma or neutron radiation intensity 5.1.5 Matrix Effects on Neutron Assay at each detector position in a given collection zone, the line-of-sight background is measured by moving the detector A change in the neutron yield for a plutonium sample of and collimator to one side (still pointing in the same fixed isotopic content can be caused by a change in the direction as during the assay) and measuring the radiation concentration of high-(a,n)-yield impurities in the matrix.

intensity from the surrounding materials. During the If it is possible to estimate the range of permissible impurity background measurement, the vessel in which the holdup is concentrations, the variation in a typical neutron yield being measured must not be in the field of view of the can be calculated using the method given in the appendix to detector. Because uncertainties in geometry, attenua this guide.

tion, or sample matrix will usually dominate the total response variability, the counting period need not be long. 5.1.6 Effect of Isotopic Uncertainty Having 1000 to 10,000 net counts is generally sufficient for most holdup applications.

Gamma ray measurements of plutonium holdup provide 2 39 a direct determination of the fissile plutonium (i.e., Pu This procedure is repeated at all measurement posi and 241 Pu) holdup in the zone under consideration. On the tions and in all counting geometries designated for each other hand, neutron techniques measure only the 240Pu collection zone. The final holdup value for the zone is effective content, and chemical techniques provide obtained from the average of the individual measurements elemental analysis without consideration of the isotopic (each one being corrected for the effects of attenuation and makeup. Thus, knowledge of the isotopic composition of any variation in geometry relative to the calibration measure the plutonium is necessary to correlate holdup measure ment).

ments with chemistry and accountability value

s. Gamma

2 39 ray assays must be divided by the pu isotopic fraction, Whenever possible, the collection zone is assayed in a 240

Pu effective and neutron assays must be converted from variety of ways. For example, one could measure an appara to total plutonium in order to express holdup in terms of tus up close and treat it as an area source; the measurement total plutonium.

could then be repeated at a large distance, treating the zone as a point source. It may be better to measure some zones If the process equipment is thoroughly cleaned each from several different directions-especially if complicated time the isotopic composition is changed, the holdup may attenuation corrections are called for in some of the count consist primarily of the current material. In that case, the ing geometries. Several independent measurements of one declared isotopic composition can be used. When mixing zone can provide an average holdup value that is better than

5.23-10

5.3 Estimation of Bias occurs, use of the stream-averaged isotopic composition is esti appropriate. Bounds on the isotopic composition are When a single collection zone is cleared out, it is desirable and lowest 1 to perform a holdup assay before, Hbefore, and after, mated by considering the batches of highest This

.omposition and computing the corresponding range. H fter, the cleanout if possible. By comparing the amount into the measure of variability must then be incorporated oplutonium removed, Pur, to the recovery amount pre making direct dicted through the in situ holdup assays, Pua, the collection estimated holdup standard deviation before comparisons with the chemical analyses. The variability in zone calibration can be updated, and the calibration and stan isotopic composition can be expressed as an estimated range and assay standard deviations can be based on relevant data.

The amount of plutonium recovered, Pur, during the dard deviation defined as one-half the observed deviation cleanout of a specific collection zone can be assayed then combined in quadrature with the standard gamma given by Equation 1 in Section B.5.2. In general, through sampling and chemical analysis, through calorim sensitive to isotopic etry, or through other applicable nondestructive assay ray measurements of 239 pu will be less

240

Pu. or variations than neutron measurement of methods (e.g., spontaneous fission coincidence detection gamma ray assay).

5.2 Assignment of Standard Error measure The assay value for the recovered amount is computed as The assignment of a standard error to a holdup the difference in the holdup assays before and after the difficult on a rigid statistical basis. This is ment is extremely cleanout:

because the only statistically predictable fluctuations (e.g.,

negli counting statistics) in this application are frequently (2)

variability due to counting geo Pua = Hbefore - Hafter gible in comparison with material distribution), gamma ray attenua metry (including The percent difference, A, between the assay and neutron tion, gamma ray background and interferences, recovery values for the plutonium holdup is then computed:

It is important matrix effects, and instrument instabilities.

and guard to recognize that the variability can be large A = 100 (Pua - PUr)/Pur (3)

the standard deviation of the against underestimating holdup value in a collection zone. Careful measure overall A running tabulation of the quantities Pua, Pur, and A (as ments must be carried out during the calibration procedure well as their standard deviations, oa, ar, and OA) is kept in from to determine the range of detector responses resulting the assay log for each collection zone.

parameters. A useful discussion variations in measurement of these ideas is presented in Reference 10. The average value, A, of the percent differences between holdup Pua and Pur will serve as an estimate of the bias in the assay for that collection zone and will also provide quantita of the A reasonable estimate of the standard deviation tive justification for revision of the assay calibration for that holdup for a given collection zone may be The root-mean-square deviations, measured values zone to remove the bias.

obtained by consideration of the range of holdup aA, of the percent differences, Ai from their mean value, measurements performed on obtained from the variety of A, serve as a check on the appropriateness of the size of the as suggested in the previous section.

that collection zone, average of estimated standard deviation of the holdup measurements.

The mean value for the holdup is defined as the To the extent that the standard deviation of Pur is small on the collec the various (corrected) measurement results compared with the uncertainty in Pua (usually an adequate a, for that mean value is in size tion zone. The standard deviation, assumption), the quantity sA should be comparable the range of holdup values obtained in For K measurements of the estimated as one-half to the standard deviation of Pua.

if a large the measurements. This estimate is conservative percent differences, Ai, for a given collection zone, the made. For a small number of measurements have been quantity sA is given by:

actual standard deviation can number of measurements, the the range. In such cases the actual be larger than one-half FK -E2 1/2 calculated.

standard deviation of the holdup values must be ) /(K - 1

2 s A [i E (Ai 1I (4)

counting In some cases, it may be unavoidable that the that they contribute significantly to statistics are so poor 0

Equation 4 assumes that all the A's are equal. For a variability. In such an instance, the overall weighted sums, see Reference 14.

the measurement calculation of sA using as the square holdup standard deviation, CF(h-u)' is defined of the standard deviation or root of the sum of the squares Note that, if the holdup measurements (ie., Hbefore and the standard deviation due to can still due to counting, O(stat), Hafter) contain a constant bias, their difference Pur.

measurement fluctuations, O(meas); that is, provide useful information in the comparison with between Pua and Pur does not However, a small difference that the bias associated with H is small.

necessarily mean

0

(h-u) = (stat) + a(meas) (1)

5.23-11

This ambiguity is reduced in importance if the cleanout is 5. Areas may be denoted as problem areas so that such that Hafter is much smaller than Hbefore. In addition, careful holdup measurements will be made in these areas the use of several holdup measurements from varying van each time plant holdup is to be determined; or the area may tage points, as suggested earlier, will help to minimize the be labeled as a spot-check zone, where accumulations are \

bias associated with incorrect geometrical or attenuation known to be low and careful holdup assays are needed less corrections in one measurement configuration. frequently.

C. REGULATORY POSITION

2. ASSAY INSTRUMENTS

To develop a program for the periodic in situ assay of Neutron and gamma ray assay capability can be provided, plutonium residual holdup as a method acceptable to the if desired, using separate or compatible electronics with NRC staff for measuring this inventory component, it is interchangeable detector probes. Compatible electronics necessary to consider the factors in the following sections. can provide for both 3He or BF 3 neutron detection and NaI(T1) gamma ray detection. The electronics unit should Care must be exercised during the fabrication and use of have a temperature coefficient of less than 0.1 percent per check sources and calibration standards to ensure their degree centigrade. Battery-powered electronics can expedite continued integrity and to prevent contamination. In assays.

addition, the usual precautions for safeguarding plutonium should be taken. 2.1 Gamma Ray Assay

1. DELINEATION OF COLLECTION ZONES AND Gamma ray assay should be based on the activity observed ASSAY SITES in the energy range from 375 to 450 keV, excluding the composite gamma ray complex centered at 333 keV. Yield Preliminary radiation survey measurements of the data for appropriate gamma rays are presented in Sec plutonium processing facility should be used to budget the tion B. 2.1 of this guide.

measurement time to emphasize high-holdup areas, to establish independent collection zones, and to determine 2.1.1 Detector Selection detector positions within the zones.

Gamma ray detectors for holdup measurements should

1. At each collection zone, detector positions (assay have FWHM (full width at half maximum) resolution better sites) should be chosen so that the material holdup can be than 10 percent at 662 keV ( 1 3 7 Cs gamma ray). NaI(Tl)

measured from several vantage points around the zone. At detectors can exhibit resolutions as good as 7 percent and each assay site, the detector should have an exclusive are suitable for this application. The crystal depth should view of the collection zone being assayed. If necessary, be sufficient to detect a significant percentage of 400-keV

shadow shielding should be used to isolate the region being gamma rays. For NaI(T1), the minimum depth should be assayed from other collection zones. Detector positions 1 inch (2.5 cm); a 2-inch (5-cm) depth is recommended.

should be chosen to minimize the measurement ambiguities, as described in Section B.5.1.1. The crystal should be stabilized with a suitable radioac tive source. An internal seed containing 241Am is recom

2. Each assay site should be permanently marked with mended for this application. The electronics should be paint or colored tape on the floor to ensure reproducible capable of stabilizing on the reference radiation emitted by assay positions. The markings should be protected (for the seed. The crystal face (external to the cover) should be example, with clear epoxy) to ensure their long-term covered with 0.75 mm of cadmium and 1.5 mm of lead to durability. Detector height and orientation should be filter low-energy radiations.

clearly indicated in the assay log for each measurement site and, if possible, included in the site markings. Two single-channel analyzers should be provided with lock-set energy windows. One channel should be set to

3. Each assay site should be uniquely labeled to facilitate admit gamma rays from 375 to 450 keV. Unless equilibrium unambiguous reference to that site in the assay log. A of the 2 3 7 U and 24 1 pu can be ensured, the 333-keV region labeling and color-coding convention should be established of the gamma ray spectrum should be completely excluded.

to distinguish neutron assay sites from gamma ray assay The second channel should be set above the first window to sites. provide a background subtraction for the assay window.

This second window should be set from approximately 475

4. Gamma ray assay should be used for collection zones to 575 keV. The width and position of this window is a containing less plutonium than the neutron detection limit. matter of personal preference in how the background Also, gamma ray assay should be used for all structures that subtraction should be done. These analyzers should be do not contain irregularly shaped components capable of packaged as one integral unit.

significantly attenuating the emerging gamma rays. Neutron assay should be used for all structures not suitable for 2.1.2 Gamma Ray Collimator gamma ray assay. There may be some large structures such as furnaces that can be measured only with small interior A cylinder of shielding material such as lead should be probes or with thermoluminescent dosimeters. made concentric with the gamma ray detecto

r. The end of

5.23-12

the cylinder opposite the crystal should be blocked with 2.3 Service Cart the shielding material. The thickness of the collimator should be chosen to provide sufficient directionality for the A cart carrying electronics and both detector probes specific facility (1.5 cm of lead thickness should be sufficient should be provided. The capability to raise or lower the for most applications). The collimator sleeve should be probes to reproducible settings should be included.

fixed over the end of the detector crystal at a reproducible setting identical to that used in the calibration measure

3. CALIBRATION

ments.

3.1 Instrument Check

2.1.3 Gamma Ray Calibrationand Check Sources The stability of the neutron and gamma ray detection Standard sources of 2 3 9 pu should be provided for systems should be tested prior to each inventory by compar calibration of the measurement system for the basic measure ing the observed counts obtained from the check source, ment geometries described in Section B.4. A small encapsu minus the counts with the shaped shield in place but with lated plutonium sample can be used both as a calibration out the check source, to the readings obtained prior to standard for the point source counting geometry and as a previous inventories. If the measurement is consistent with check source for verification of instrument stability. For previous data (i.e., is within + 2 single-measurement standard the line and area calibrations, large plutonium foils can be deviations of the mean value of previous data), all previously used, or the calibrations can be derived from a series of established calibrations using this detection system should measurements made with the point source. The gamma ray be considered valid. If the measurement is not consistent, self-attenuation correction should be clearly specified for the operation of the unit should be checked against the all foils and samples. manufacturer's recommendations and repaired or recali brated, as required. These check source measurements should be supplemented with regular remeasurements of

2.2 Neutron Assay instrument calibrations to ensure continued proper instru ment performance over the entire operating range.

2.2.1 Neutron DetectorSelection

3.2 System Response Calibration Neutron detectors should have high detection efficiency and be capable of operating in the presence of gamma The response of the detection system should be deter radiation. BF 3 and 3He neutron detectors are recommended mined with well-known quantities of plutonium in the basic for this application. Neutron detectors should be surrounded measurement geometries described in Section B.4. If there by a layer of neutron moderator material to enhance their are special counting geometries in the facility that are not detection efficiency. The neutron moderator layer should readily represented by one of the basic configurations, be covered with a low-energy neutron absorber to filter out these geometries should also be mocked up and measured extraneous neutrons from the desired signal. during the calibration procedure.

2.2.2 Neutron Collimator

4. ASSAY PROCEDURES

A slab collimator or concentric cylinder collimator of 4.1 Assay Log polyethylene should completely surround the detector, leaving open only a detection channel in one direction. The An assay log should be maintaine

d. Each collection zone

.moderator thickness should be selected to provide the should have a separate section in the assay log, with the directionality required for each facility. A directionality corresponding calibration derived on the page facing the profile providing a 10:1 response ratio is desirable. However, assay data sheet. Recording space should be provided for portable detectors a 3:1 ratio may be used. for the date of measurement, gross counts, corrected counts, and the corresponding grams of plutonium from the

2.2.3 Neutron Calibrationand Check Source calibration in addition to position and instrument electronic setting verification. There should also be provision for A 50- to 100-gram sample of plutonium should be recording data from recovery operations and holdup assay adequate both as a point source calibration standard and as comparisons, as described in Section B.5.3.

a check source. The isotopic composition, 241Am content, and high-(c,n)-yield impurity composition should be 4.2 Preassay Procedures representative of the plutonium being processed. The neutron yield of the standard should be independently Prior to inventory, the isotopic composition of the measured, if possible, and also computed using the method plutonium processed during the current operational period described in the appendix of this guide. If the measured and should be determined. Variations in the neutron and calculated yields differ by more than 20 percent, any future gamma ray yield data from the calibration standard should yield calculations should be normalized to be consistent be calculated. Either the calibration data or the predicted with this measurement. holdup should then be corrected to reflect this difference.

5.23-13

Prior to each inventory, the operation of the neutron should initial the measurement log to ensure compliance for and gamma ray assay detection systems should be checked, each collection zone.

as described in Regulatory Position 3.1.

When the preceding steps have been completed, the t Prior to any assay measurements, feed into the process measurement at each collection zone should be taken, line should be stopped. All in-process material should be recorded, and converted to grams of plutonium. If each processed through to forms amenable to accurate account value is within an expected or permissible range, the assayist ability. All process, scrap, and waste items containing can proceed to the next collection zone. However, if the plutonium should be removed to approved storage areas to collection zone contains an unexpectedly large amount of minimize background radiations. plutonium, it should be cleaned to remove the accumulation for conversion to a more accurately accountable material

4.3 Measurements category. After the cleanout has been completed, the zone should be reassayed.

Before beginning the holdup measurements, it is advis able to conduct a preliminary gamma survey of the collec tion zones to point up the zones where holdup accumula 5. ESTIMATION OF HOLDUP ERROR

tions are the highest (and therefore where the most careful measurements should be made). In zones where accumula During the initial implementation of the holdup measure tions are shown to be very low by the survey, spot-check ment program, the holdup uncertainty for each collection measurements may be adequate, as pointed out earlier. zone should be estimated from the range of values obtained in the various measurements on that zone, as described in Before assaying each collection zone, the operator Section B.5.2. As a history of comparisons between holdup should verify the floor location, probe height, and probe measurements and cleanout recovery data becomes avail orientation. The electronic settings should be verified every able, these data should be used to adjust for bias and to

1 or 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with the check source. During the actual assay revise the magnitudes of the holdup uncertainties, as of the collection zones, the check source should be removed described in Section B.5.3.

or shielded so as not to interfere with the measurement.

Prior to taking a measurement, a visual check of the zone During each physical inventory, the calibration in at and the line of sight of the detector probe should be made least 10 percent of the collection zones should be updated to ensure that no obvious changes have been made to the on the basis of the comparison between holdup and cleanout process area and that no unintended accumulations of recovery measurements. In any case, all calibrations should plutonium remain within the collection zone. The operator be updated at least once per year.

I

5.23-14

REFERENCES

8. H. E. Preston and W. J. Symons, "The Determination in Gloveboxes by of the Gamma of Residual Plutonium Masses R. Gunnink et al., "A Re-evaluation Branching Intensities of Remote Measurements Using Solid Thermoluminescent Ray Energies and Absolute Energy Author

8 and Am-241:' Lawrence Dosimeters," United Kingdom Atomic U-237, Pu-23 , -239,-240, -241, ity, Winfrith, England, AEEW-R13 59, 1980.

1976.

Livermore Laboratory, UCRL-52139, of the L. D. Mclsaac, "Gamma A. Ohno and S. Matsuura, "Measurement

2. J. E. Cline, R. J. Gehrke, and 9. in a Spent Fuel the Fissionable Nuclides and Asso Gamma Dose Rate Distribution Rays Emitted by Detector,"

Idaho Falls, Assembly with a Thermoluminescent ciated Isotopes," Aerojet Nuclear Co., 485, 1980.

Nuclear Technology, Vol. 47, p.

Idaho, ANCR-1069, July 1972.

and H. C. Keller, "A

Material Safeguards 10. W. D. Reed, Jr., J. P. Andrews,

3. L. A. Kull, "Catalogue of Nuclear 23 sU with Limit of Error Laboratories, BNL Method for Surveying for 5 Instruments," Battelle National Management, Vol. 2, p. 39 ,

Analysis," Nclear aterials

17165, August 1972. 1973.

"Fundamentals of

4. R. H. Augustson and T. D. Reilly, "Self-Multiplication Fissionable Material," N. Ensslin, J. Stewart, and J. Sapir, Passive Nondestructive -Assay of 11.

Coincidence Counting,"

LA-5651-M, 1974; Correction Factors for Neutron Los Alamos Scientific Laboratory, Management, Vol. VIII, No. 2, p. 60,

al., "Fundamentals of Passive Nuclear Materials also T. D. Reilly et 1979.

Assay of Fissionable Material: Labora Nondestructive Laboratory, tory Workbook," Los Alamos Scientific for Nuclear LA-5651-M, Suppl., 1975. 12. M. S. Zucker et al, "Holdup Measurements Manage Plants," Nuclear Materials Fuel Manufacturing of UF Cylinders ment, Vol. X, p. 239, 1981.

5. R. B. Walton et al., "Measurements Technology, with Portable Instruments," Nuclear Vol. 21, p. 133, 1974. "Bulk Sample Self

13. J. L. Parker and T. D. Reilly, Measure of Residual Pluto Attenuation Correction by Transmission

6. C. H. Kindle, "In Situ Measurement the ERDA X- and Gamma-Ray

5, No. 3, ment," Proceedings of nium," Nuclear MaterialsManagement, Vol. (Conf. 760639),

p. 540, 1976. Symposium, Ann Arbor, Michigan p. 219, May 1976.

"Total Room

7. J. W. Tape, D. A. Close, and R. B. Walton, and Error Analysis Holdup of Plutonium Measured with a Large-Area 14. P. R. Bevington, Data Reduction 1969.

Management, for the Physical Sciences, McGraw-Hill, Neutron Detector," Nuclear Materials Vol. 5, No. 3, p. 533, 1976.

5.23-15

APPENDIX

A. NEUTRON YIELD COMPUTATIONS The coefficients 2.50 and 1.70 are the spontaneous fission yields of 2 3 8 pu and 2 4 2 Pu relative to 24°Pu. The concept \

The following model for the calculation of the total of effective 2 4 0 pu mass reflects the fact that most of the spontaneous neutron yield from plutonium-bearing materials spontaneous fission yield is due to that isotope.

assumes that the plutonium is widely dispersed. With this condition, there will be no significant neutron production 2. (cz,n) NEUTRONS

through induced fission of 39pu or 2 4 1 Pu. The total neutron yield of plutonium holdup will then be the sum of When the plutonium holdup is in the form of oxide, the the spontaneous fission and (ct,n) contributions: major contribution from (ct,n) reactions will be due to the

0-18(a,n) 21Ne reaction. The additional neutron yield is Yn= YSF + Y(a,n) (1) typically 50 to 100 percent of the spontaneous fission yield. The (a,n) yield can be calculated from the yields per

1. SPONTANEOUS FISSION NEUTRONS gram of each isotope of Pu(Yi) given in Table A-1:

To determine the spontaneous neutron yield of pluto Y(ay,n) oxide = 1 MiYi (5)

nium, the isotopic composition must be known. (The 1y contribution from 23SU spontaneous fission is usually negligible even if uranium is present in large quantities.) The summation over Mi should also include 24 1 Am, which The yield from the plutonium isotopes is given by: is a strong alpha emitter.

YSFp M2 3 8Q 2 38 + M2 4 0 Q 2 4 0 + M2 4 2 Q 2 4 2 (2) In addition to (c4n) production in the oxide itself, certain low-Z impurities in the oxide can contribute substan where Mi is the total mass of the ith plutonium isotope, and tially. Values for the yields of neutrons obtained in bombard Qi is the spontaneous fission neutron yield per gram of the ing thick targets of these elements with 5.2-MeV alpha ith isotope. Using the yield data from Table A-l, Equation 2 particles are given in Table A-2. Further research may can be rewritten as: change these values somewhat, but they are sufficient for computing the approximate effect of these elements if they YSF = (1030 n/sec-gram)M 24 0 (effective) (3) exist as impurities in PuO . One method for doing this is to compute the impurity (x,n) yield relative to the oxide where (ct,n) yield:

M2 4 0 (effective) = 2.50M 2 38 + M240 + 1.70M 2 4 2 (4) Y(an)impurity - Y(cn)oxide f (WiAoI )/(Pok io) (6)

ble A-1 ALPHA PARTICLE AND SPONTANEOUS FISSION NEUTRON YIELDS

Y.

Qi PuO 2 U0 2 Half-Life Alpha Activity Spontaneous Fission (a,n) Yield*

Nuclide (yr) (a/sec-gram) (n/sec-gram) (n/sec-gram)

238pu, 87.78 6.33 x 1011 2.57 x 103 1.4 x 104

239pu

24,150 2.30 x 109 2.22 x 10-2 42.5

2 4 0

pu

6,529 8.43 x 109 1.03 x 103 157

2 4 1 pu

14.35** 9.39 x 107 5.00 x 10-2 1.3

2 4 2 pu

379,000 1.44 x 108 1.75 x 103 2.2

24 1 Am 433.8 1.27 x 10"1 6.05 x 10f' 2957

234U 2.47 x 105 2.29 x 108 5.67 x 10-3 4.65

3

235U

7.1 x 108 7.93 x 104 5.96 x 10-4 1.37 x 10-

238 U

4.51 x 109 1.23 x 104 1.12 x 10-2 1.93 x 10-4

• Oxygen yield from PuO 2form only.

• • &branching

• ratio: 2.46 x i0T5 .

5.23-16

Table A-2 Table A-3 (a,n) NEUTRON YIELDS FOR SAMPLE CALCULATION FOR 1 GRAM OF PLUTONIUM

VARIOUS LIGHT ELEMENTS

Isotopic YSF Y(a, n)o ide P. Nuclide Composition (n/sec) (n/sec)I

Neutron Yield 23 SPU 0.003 8 42 Element per 106 Alphas 2 3 pt 0.756 0 32

24 PU 0.185 191 29 Be 58 S1 Pu 0.045 0 0

B 18 242 0.011 19 0

F 6.4 241 Am 0.003 0 9

7 Li 1.3 Na -1.5 Total Yields 218 112 NatMg 0.89 Al 0.44 Natsi 0.077 C 0.05 O 0.050 Using the isotopic composition given in Table A-3 and using Equation 3, the spontaneous fission neutron yield can

• Most of these yields are based on: be found to be 218 n/sec for 1 gram of plutonium. Then J. K. Baki and J. Gomez del Campo,

"Neutron Yields from Alpha-Particle the neutron production in the oxide can be calculated Bombardment," Nuclear Science and using the masses Mi of each isotope and the yields Y- from Engineering, Vol. 71, p. 18, 1979.

the fifth column of Table A-1. The result of 112 n)sec is given in the last column of Table A-3. Note that the alpha In Equation 6, P. is the (a,n) neutron yield in the impurity particle yield of ylutonium is nearly constant in time, but element, and P 0 is the yield in oxygen (0.050 neutrons/106 that, because 24 Am builds up in time, the total alpha alphas); A. is the atomic weight of the impurity element, production increases at a rate of roughly 0.3 percent per and Ao that for oxygen (16); Ij is the concentration of the month in typical reactor fuel impurity expressed in parts per million (by weight) of plutonium oxide, and Io is oxide (118,000 ppm). If the impurity concentration is expressed as ppm of plutonium, The impurity (ct,n) yields are calculated in Table A-4.

it can be converted to ppm of plutonium oxide by multi The calculation is based on impurities in PuO 2 only. The plying by the gravimetric dilution factor, 0.882. mixed oxides are assumed to consist of blended PuO 2 and UO2 particles approximately 40 pm in diameter where To summarize the calculation of (ct,n) neutron yields in most alpha particles stop within the PuO 2 particles. If the oxide that also contains impurities, Y(a,n) from all sources particle size were smaller or the mixed oxide were created is given by: through coprecipitation, the uranium impurity content would also contribute to the plutonium (a,n) yiel

d. In the

(7) present example, it is sufficient to use the neutron yields P.

Y( i MiYf + .0027EP_-I-/A-)

Z,n) " I

from Table A-2, the concentrations Ij from Table A-4, and Equation 6 or 7.

Elements other than those listed in Table A-2 yield no neutrons by (ct,n) reactions for the alpha energies obtained from plutonium and americium decay. Also note that the The total neutron yield from 1 gram of plutonium in summation over i must include 241 Am and that the summa PuO 2 is then 218 + 112 + 47 = 377 n/sec. Using the gravi tion over j includes only the oxygen that is not bound up as metric dilution factor of 0.882, this is 333 n/sec for 1 gram plutonium oxide. of PuO 2 . If the PuO 2 is blended so that PuO 2 / (PuO 2 +

UO ) = 0.03, the neutron yield from 1 gram of mixed

3. SAMPLE CALCULATION FOR PuO 2 -UO 2 oxide is 10 n/sec.

Consider the case of I gram of recycle plutonium The impurity (ct,n) yields, Pi, used in this example are blended to 3 percent by weight of PuO 2 in a UO 2 matrix currently known to about 10 percent accuracy for most where the isotopic composition is as given in Table A-3. For elements and 50 percent accuracy for the others. The oxide mixed oxides, the oxygen density is approximately the .J are known to 10 percent or better. Both (atn) yields, Y..,

same as in PuO 2 alone. Also, plutonium and uranium have yield calculations must assume perfect mixing, however.

similar atomic numbers. For these reasons, it may be For these reasons, neutron yield calculations are accurate to assumed that the oxygen (ca,n) yield in mixed oxide is 10 percent at best, and the neutron holdup measurement the yield in PuO 2 , further reduced by the blending ratio, calibration should be based on representative standards PuO 2 /(PuO 2 + U0 2 ). rather than calculation wherever possible.

5.23-17

Table A-4 Let f238, f239' f240' f241, and f2 4 2 represent the weight fractions of the respective plutonium isotopes in the IMPURITY (ca,n) YIELD unknown sample. The 2 4 0 pu effective weight fraction, f (effective), can be defined as:

240

Arbitrary Concentration I Impurity (cn) (8)

in PuO 2 Yield (I12 n/sec) f2 4 0 (effective) = M2 4 o(effective)/Mpu(total)

Impurity (ppm by wgt) (0.00 2 7 )Pjlj/Aj where Li 9 1 Be 8 16 f2 4 0 (effective) = 2.50f 2 39 + f 24 0 + 1.70f 2 4 2 (9)

B 10 5 C 200 0 Generally, as previously mentioned in this guide, the F 125 13 relative measurement uncertainty of M2 4 0 (effective) in a

0 (moisture) 4600 4 holdup measurement will be much larger than that of Na 120 8 f;40(effective), so the relative error in Mpu(total) is essen Total 47 (n/sec) tially equal to that of M2 4 0 (effective).

As an example calculation, the sample of isotopic composition given in Table A-3 has an effective fraction given by:

B. CONVERSION OF MEASURED M D4(EFFECTIVE) + 0.185 + 1.70(0.011)

TO TOTAL PLUTONId" = 2.50(0.003)

f 24 0 (effective) = 0.21

240

To convert a measured effective pu mass to actual Thus, a holdup measurement of 35 + 10 grams 24°pu total plutonium, one must use both the relationship between effective corresponds to 166 + 47 grams total plutonium, these two quantities, as shown in Equation 4, and the where the relative error in the total plutonium result was known isotopic composition of the samples being measured. taken to be equal to that of the M2 4 0 (effective) result.

5.23-18

VALUE/IMPACT STATEMENT

1.3.4 Public

1. PROPOSED ACTION

No adverse impact on the public can be foreseen.

1.1 Description

1.4 Decision on Proposed Action Licensees authorized to possess at any time more than

1 kilogram of plutonium are required by Part 70, "Domestic The regulatory guide should be revised to reflect improve Licensing of Special Nuclear Material," of Title 10 of the ments in measurement techniques and to bring the language Code of Federal Regulations to calculate a material balance of the guide into conformity with current usage.

based on a measured physical inventory at intervals not to exceed 2 months. Further, these licensees are required to

2. TECHNICAL APPROACH

conduct their nuclear material physical inventories in compliance with specific requirements set forth in Part 70. Not applicable.

Inventory procedures acceptable to the NRC staff are detailed in Regulatory Guide 5.13, "Conduct of Nuclear

3. PROCEDURAL APPROACH

Material Physical Inventories."

Of the procedural alternatives considered, revision of the Plutonium residual holdup is defined as the plutonium existing regulatory guide was selected as the most advanta inventory component remaining in and about process geous and cost effective.

equipment and handling areas after those collection areas have been prepared for inventory. This 'regulatory guide

4. STATUTORY CONSIDERATIONS

describes procedures acceptable to the NRC staff for the in situ assay of the residual plutonium holdup. 4.1 NRC Authority

1.2 Need for Proposed Action The authority for the proposed action is derived from the Atomic Energy Act of 1954, as amended, and the Regulatory Guide 5.23 was published in 1974. The Energy Reorganization Act of 1974, as amended, and is proposed action, a revision to this guide, is needed to bring implemented through the Commission's regulations, in the guide up to date with respect to advances in measure particular 10 CFR Part 70.

ment methods, as well as changes in terminology.

4.2 Need for NEPA Assessment

1.3 Value/Impact of Proposed Action The proposed action is not a major action that may

1.3.1 NRC Operations significantly affect the quality of the human environment and does not require an environmental impact statement.

The regulatory positions will be brought up to date.

S. RELATIONSHIP TO OTHER EXISTING OR PROPOSED

1.3.2 Other Government Agencies REGULATIONS OR POLICIES

Not applicable.

The proposed action is one of a series of revisions of exist ing regulatory guides on nondestructive assay techniques.

1.3.3 Industry

6. SUMMARY AND CONCLUSIONS

Since industry is already applying the methods and procedures discussed in the guide, updating these methods Regulatory Guide 5.23 should be revised.

and procedures should have no adverse impact.

5.23-19

FIRST CLASS MAIL

UNITED STATES POSTAGE & FEES PAID

USNAC

NUCLEAR REGULATORY COMMISSION WASH0 C

PERMII No SiIL

WASHINGTON, D.C. 20555 OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300