High-level waste

Source: Wikipedia, the free encyclopedia.
See also: High-level radioactive waste management
Hanford site represents 7-9 percent of America's high-level radioactive waste by volume. Nuclear reactors line the riverbank at the Hanford Site along the Columbia River
in January 1960.

High-level waste (HLW) is a type of

nuclear waste created by the reprocessing of spent nuclear fuel.[1]
It exists in two main forms:

Liquid high-level waste is typically held temporarily in underground tanks pending vitrification. Most of the high-level waste created by the

cold war exists in this form because funding for further processing was typically not part of the original weapons programs. Both spent nuclear fuel and vitrified waste are considered [2]
as suitable forms for long term disposal, after a period of temporary storage in the case of spent nuclear fuel.

HLW contains many of the

transuranic elements generated in the reactor core
and is the type of nuclear waste with the highest activity. HLW accounts for over 95% of the total radioactivity produced in the nuclear power process. In other words, while most nuclear waste is low-level and intermediate-level waste, such as protective clothing and equipment that have been contaminated with radiation, the majority of the radioactivity produced from the nuclear power generation process comes from high-level waste.

Some countries, particularly France, reprocess commercial spent fuel.

High-level waste is very radioactive and, therefore, requires special shielding during handling and transport. Initially it also needs cooling, because it generates a great deal of heat. Most of the heat, at least after short-lived nuclides have decayed, is from the

medium-lived fission products caesium-137 and strontium-90
, which have half-lives on the order of 30 years.

A typical large 1000 MWe nuclear reactor produces 25–30 tons of spent fuel per year.[3] If the fuel were reprocessed and vitrified, the waste volume would be only about three cubic meters per year, but the decay heat would be almost the same.

It is generally accepted that the final waste will be disposed of in a deep geological repository, and many countries have developed plans for such a site, including Finland, France, Japan, United States and Sweden.

Definitions

Long-lived fission products
Nuclide
t1⁄2
 Yield Q[a 1]
βγ
(
Ma
) 		(%)[a 2] (
keV
)
99Tc 0.211 6.1385 294 β
126Sn
 0.230 0.1084 4050[a 3] βγ
79Se 0.327 0.0447 151 β
135Cs
 1.33  6.9110[a 4] 269 β
93Zr
 1.53  5.4575 91 βγ
107Pd
 6.5   1.2499 33 β
129I 15.7   0.8410 194 βγ
  1. ^ Decay energy is split among β, neutrino, and γ if any.
  2. ^ Per 65 thermal neutron fissions of 235U and 35 of 239Pu.
  3. ^ Has decay energy 380 keV, but its decay product 126Sb has decay energy 3.67 MeV.
  4. ^ Lower in thermal reactors because 135Xe, its predecessor, readily absorbs neutrons.
Medium-lived
fission products [further explanation needed]
t½
(year
) 		Yield
(%)
keV
)
βγ
155Eu
  4.76 0.0803  252 βγ
85Kr 10.76 0.2180  687 βγ
113mCd
 14.1  0.0008  316 β
90Sr 28.9  4.505   2826 β
137Cs 30.23 6.337   1176 βγ
121mSn
 43.9  0.00005 390 βγ
151Sm
 88.8  0.5314  77 β

High-level waste is the highly radioactive waste material resulting from the reprocessing of spent nuclear fuel, including liquid waste produced directly in reprocessing and any solid material derived from such liquid waste that contains fission products in sufficient concentrations; and other highly radioactive material that is determined, consistent with existing law, to require permanent isolation.[4]

Spent (used) reactor fuel.

  • radioactive
    , and potentially harmful.

Waste materials from reprocessing.






Storage

Main article: High-level radioactive waste management
Spent fuel pool

High-level radioactive waste is stored for 10 or 20 years in spent fuel pools, and then can be put in dry cask storage facilities.

In 1997, in the 20 countries which account for most of the world's nuclear power generation, spent fuel storage capacity at the reactors was 148,000 tonnes, with 59% of this utilized. Away-from-reactor storage capacity was 78,000 tonnes, with 44% utilized.[5]

See also

Notes

  1. ^ M.I. Ojovan and W.E. Lee. An Introduction to Nuclear Waste Immobilisation. Elsevier, Amsterdam (2005)
  2. ^ Radioactive Waste Management
  3. ^ WNO radwaste management
  4. ^ Dept of Energy - RADIOACTIVE WASTE MANAGEMENT MANUAL - DOE M 435.1-1
  5. ^ "Radioactive waste". martinfrost.ws. Archived from the original on 3 December 2012. Retrieved 16 April 2013.

References

  • Fentiman, Audeen W. and James H. Saling. Radioactive Waste Management. New York: Taylor & Francis, 2002. Second ed.
  • Large, John H. Risks and Hazards arising the Transportation of Irradiated Fuel and Nuclear Materials in the United Kingdom R3144-A1, March 2006 [1]

External links

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