NEUTRON SPECTRA OF PLUTONIUM COMPOUNDS.   PART 1: 3He and 6 Li SPECTROMETER MEASUREMENTS.

Brackenbush, L.W.; Faust, L.G.

doi:10.2172/4132647

Cited by 2 publications

(7 citation statements)

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“…Gamma radiation dosimetry was performed with lithium flouride t h e r m oluminescence dosimeters, and these [11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26][27][28][29] measurements resulted in dose r a t e s of 57.8 r a d s f h r f r o m the radium and 25.1 r a d s f h r f r o m the Cf-252 loading. dosimetry was performed with solid-s t a t e devices that have been previously described (z), and t h e s e measurements gave a neutron dose component of the Cf-252 of 35.3 r a d s f h r .…”

Section: Methodsmentioning

confidence: 99%

“…12)) and a high ex?osure plutonium dioxide" neutron s o u r c e . T h e average energj of t h i s plutonium dioxide source was c a l c u l a t e d (13) t o be about 2 . 1 :!eV assuming t h a t 655 of t n e neutrons came from sFontaneous f i s s i o n w i t h an averace energ; of about 2 'lev and 32;; of t h e neutrons came from O ( a , n ) react i o n s wFtn an average energy of zibout 2.3 :*eV.…”

Section: S I O N F a C T O R S Published By I T I T T S E T A L (2)mentioning

confidence: 98%

“…, t h e same power l e v e l and t h e corresponding time-averaged p o s i t i o n of t h e autorod now held constant by manual operat ion. (13). NEUTRON …”

Section: If a Constant P O I N T Neutron Source T H A T Does Not Absomentioning

confidence: 99%

“…For p e n e t r a t i o n through t i s s u e , which i s taken t o be t h e same as t h a t through water f o r the gamma-1-ays only, an e m p i r i c a l l y derived 3rd c r d e r polynomial expression describes t h e [11][12][13][14][15][16][17] appropriate reduction i n dose (I).…”

Section: T Y F a C T O R S C A L C U L A T E D From T I S S U E Equmentioning

confidence: 99%

“…When the lens i s expected t o receive a dose of 6 -10 rads, the p a t i e n t may bd r e j e c t e d f o r californium This dose range approaches t h a t obser;able e f f e c t i n humans, but not necess a r i l y a vision-impairing defect (13). O f t h e p a t i e n t s t r e a t e d at t h i s h o s p i t a l only one, which i s presented i n t h i s paper as p a t i e n t case #2, received an excessive eye l e n s dose (,-+ 57 rads neutron and 50 rads gamma-ray).…”

Section: T Y F a C T O R S C A L C U L A T E D From T I S S U E Equmentioning

confidence: 99%

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NEUTRON SOURCES AND APPLICATIONS. Proceedings of the American Nuclear Society National Topical Meeting, April 19--21, 1971, Augusta, Georgia. Sessions I and II.

1971

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Section: Methodsmentioning

confidence: 99%

Section: S I O N F a C T O R S Published By I T I T T S E T A L (2)mentioning

confidence: 98%

“…, t h e same power l e v e l and t h e corresponding time-averaged p o s i t i o n of t h e autorod now held constant by manual operat ion. (13). NEUTRON …”

Section: If a Constant P O I N T Neutron Source T H A T Does Not Absomentioning

confidence: 99%

Section: T Y F a C T O R S C A L C U L A T E D From T I S S U E Equmentioning

confidence: 99%

Section: T Y F a C T O R S C A L C U L A T E D From T I S S U E Equmentioning

confidence: 99%

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NEUTRON SOURCES AND APPLICATIONS. Proceedings of the American Nuclear Society National Topical Meeting, April 19--21, 1971, Augusta, Georgia. Sessions I and II.

1971

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Neutron dose and energy spectra measurements at Savannah River Plant

Brackenbush¹,

Soldat²,

Haggard³

et al. 1987

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Increased concern about the accuracy of neutron dosimetry and neutron quality factors has led to recommendations by the International Commission on Radiological Protection (ICRP) and the National Council for Radiation Protection and Measurements (NCRP) to increase quality factors. The ICRP recommended in 1985 to increase quality factors for fast neutrons from 10 to 20. The NCRP is considering similar recommendations. It is expected that the U.S. Department of Energy (DOE) will adopt any recommendations by the NCRP to increase quality factors. Because any of the proposed changes would impact the operation of the Savannah River Plant (SRP), where some workers have a high potential for significant neutron expsoure, the SRP contracted with Pacific Northwest Laboratory (PNL) to verify the accuracy of neutron dosimetry at the plant. Energy spectrum and neutron dose measurements were made at the SRP calibrations laboratory; the 221-H Area, B-Line; 221-F Area, B-Line, 221-F Area, Plutonium Storage; K-Reactor shield door; californium loadout and shipping areas; and 773-A Building. The energy spectra measurements were made using mu1tisphere or Bonner sphere spectrometers, 3 He spectrometers, and NE-213 liquid scintillator spectrometers. Neutron dose equivalent determinations were made using these instruments and others s pee i fica lly designed to determine dose equi va 1 ent, such as the tissue equivalent proportional counter (TEPC). Survey instruments, such as the Eberline PNR-4, and the thermoluminescent do?imeter (TLD)albedo and track etch dosimeters (TEDs) were also used.

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NEUTRON SPECTRA OF PLUTONIUM COMPOUNDS. PART 1: 3He and 6 Li SPECTROMETER MEASUREMENTS.

Cited by 2 publications

References 0 publications

NEUTRON SOURCES AND APPLICATIONS. Proceedings of the American Nuclear Society National Topical Meeting, April 19--21, 1971, Augusta, Georgia. Sessions I and II.

NEUTRON SOURCES AND APPLICATIONS. Proceedings of the American Nuclear Society National Topical Meeting, April 19--21, 1971, Augusta, Georgia. Sessions I and II.

Neutron dose and energy spectra measurements at Savannah River Plant

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