Pozor!

Ve Vašem prohlížeči není aktuálně povoleno spouštění Javascriptu. Je možné, že některé funkce nebudou fungovat správně. Pro plnou funkčnost internetového obchodu doporučujeme povolit Javascript. Zde jsou instrukce jak povolit JavaScript ve Vašem webovém prohlížeči.

Zobrazovaná měna: Kč

Zobrazení ceny: bez DPH

Doplňující informace

ASTM E705-13

Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237

Automaticky přeložený název:

Standardní zkušební metoda pro měření reakční rychlosti podle Radioactivation z neptunia-237

NORMA vydána dne 1.6.2013

Jazyk
Provedení	PDF - okamžité stažení - 1 745.70 Kč Tištěné - 1 745.70 Kč
Dostupnost	SKLADEM
Cena	1745.70 Kč bez DPH
1 745.70 Kč

Informace o normě:

Označení normy: ASTM E705-13
Poznámka: NEPLATNÁ
Datum vydání normy: 1.6.2013
Kód zboží: NS-47732
Počet stran: 5
Přibližná hmotnost: 15 g (0.03 liber)
Země: Americká technická norma
Kategorie: Technické normy ASTM

Tisk

Odeslat známému

Dotaz

Anotace textu normy ASTM E705-13 :

Keywords:

fission dosimeter, fission product, fission reaction rates, Neptunium-237, ICS Number Code 17.240 (Radiation measurements), 27.120.30 (Fissile materials and nuclear fuel technology)

Doplňující informace


Significance and Use
5.1 Refer to Practice E261 for a general discussion of the determination of fast-neutron fluence rate with fission detectors. 5.2 ²³⁷Np is available as metal foil, wire, or oxide powder. For further information, see Guide E844. It is usually encapsulated in a suitable container to prevent loss of, and contamination by, the ²³⁷Np and its fission products.5.3 One or more fission products can be assayed. Pertinent data for relevant fission products are given in Fission Product	Parent Half-Life^A (6)	Primary Radiation^A γ Probability of Decay^A (7)	Maximum Useful Irradiation Duration
⁹⁵Zr	64.032 (6) d	724.192 (4)	0.4427 (22)	6 months
		756.725 (12)	0.5438
⁹⁹Mo	65.94 (1) hr	739.500 (17)	0.1213 (22)	300 hours
		777.921 (20)	0.0426 (8)
¹⁰³Ru	39.26 (2) d	497.085 (10)	0.910 (12)	4 months
¹³⁷Cs	30.05 (8) yr	661.657 (3)^B	0.8499 (20)^B	30–40 years
¹⁴⁰Ba–¹⁴⁰La	12.7527 (23) d	537.261 (3)	0.2439 (22)	1–1.5 months
		1596.21 (4)	0.9540 (8)^C
			1.1515^D
¹⁴⁴Ce	28.91 (5) d	133.515 (2)	0.1109 (19)	2–3 years

Fissile
Isotope

Neutron
Energy

Reaction
Product

Type
Yield

JEFF 3.1^B^,^A
Fission Yield (%)

²³⁷Np(n,f)

0.5 MeV

⁹⁵Zr

5.6147 ± 2.7 %

⁹⁹Mo

7.6118 ± 16.34 %

¹⁰³Ru

5.4305 ± 12.7 %

¹³⁷Cs

6.2654 ± 3.71 %

^137mBa

1.4802e-3 ± 35.58 %

¹⁴⁰Ba

5.9160 ± 3.82 %

¹⁴⁰La

6.3568e-3 ± 36.68 %

¹⁴⁴Ce

4.1230 ± 4.7 %

5.3.1 ¹³⁷Cs-^137mBa is chosen frequently for long irradiations. Radioactive products ¹³⁴Cs and ¹³⁶Cs may be present, which can interfere with the counting of the 0.662 MeV ¹³⁷Cs-^137mBa gamma ray (see Test Methods E320).

5.3.2 ¹⁴⁰Ba-¹⁴⁰La is chosen frequently for short irradiations (see Test Method E393).

5.3.3 ⁹⁵Zr can be counted directly, following chemical separation, or with its daughter ⁹⁵Nb, using a high-resolution gamma detector system.

5.3.4 ¹⁴⁴Ce is a high-yield fission product applicable to 2- to 3-year irradiations.

5.4 It is necessary to surround the ²³⁷Np monitor with a thermal neutron absorber to minimize fission product production from trace quantities of fissionable nuclides in the ²³⁷Np target and from ²³⁸Np and ²³⁸Pu from (n,γ) reactions in the ²³⁷Np material. Assay of ²³⁸Pu and ²³⁹Pu concentration is recommended when a significant contribution is expected.

5.4.1 Fission product production in a light-water reactor by neutron activation products ²³⁸Np and ²³⁸Pu has been calculated to be insignificant (1.2 %), compared to that from ²³⁷Np(n,f), for an irradiation period of 12 years at a fast neutron (E > 1 MeV) fluence rate of 1 × 10¹¹ cm⁻² ·s⁻¹, provided the ²³⁷Np is shielded from thermal neutrons (see Fig. 2 of Guide E844).

5.4.2 Fission product production from photonuclear reactions, that is, (γ,f) reactions, while negligible near-power and research reactor cores, can be large for deep-water penetrations (1).⁵

5.5 Good agreement between neutron fluence measured by ²³⁷Np fission and the ⁵⁴Fe(n,p) ⁵⁴Mn reaction has been demonstrated 5.6 The ²³⁷Np fission neutron spectrum-averaged cross section in several benchmark neutron fields are given in Table 3 of Practice E261. Sources for the latest recommended cross sections are given in Guide E1018. In the case of the ²³⁷Np(n,f)F.P. reaction, the recommended cross section source is the ENDF/B-VI cross section (MAT = 9346) revision 1 1.1 This test method covers procedures for measuring reaction rates by assaying a fission product (F.P.) from the fission reaction ²³⁷Np(n,f)F.P.

1.2 The reaction is useful for measuring neutrons with energies from approximately 0.7 to 6 MeV and for irradiation times up to 30 to 40 years.

1.3 Equivalent fission neutron fluence rates as defined in Practice E261 can be determined.

1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E261.

1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

2. Referenced Documents

E320-79 (1990)	Test Method for Cesium-137 in Nuclear Fuel Solutions by Radiochemical Analysis (Withdrawn 1993)
E393-19	Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
E704-19	Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
E844-18	Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E944-19	Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1018-20e1	Standard Guide for Application of ASTM Evaluated Cross Section Data File (Includes all amendments and changes 7/2/2020).
E261-16(2021)	Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E181-23	Standard Guide for Detector Calibration and Analysis of Radionuclides in Radiation Metrology for Reactor Dosimetry
E170-23	Standard Terminology Relating to Radiation Measurements and Dosimetry
E1005-21	Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
E262-17	Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques

Doporučujeme:

Aktualizace technických norem

Chcete mít jistotu, že používáte pouze platné technické normy?
Nabízíme Vám řešení, které Vám zajistí měsíční přehled o aktuálnosti norem, které používáte.

Chcete vědět více informací? Podívejte se na tuto stránku.