عنوان

Rapid Acute Dose Assessment Using MCNP6

Number

TL49420

.Language of Text, Soundtrack etc

انگلیسی

Title Proper

Rapid Acute Dose Assessment Using MCNP6

General Material Designation

[Thesis]

First Statement of Responsibility

Andrew Steven Owens

Subsequent Statement of Responsibility

Brandl, Alexander

Name of Publisher, Distributor, etc.

Colorado State University

Date of Publication, Distribution, etc.

2017

Specific Material Designation and Extent of Item

61

Text of Note

Committee members: Johnson, Thomas; Lindsay, James

Text of Note

Place of publication: United States, Ann Arbor; ISBN=978-1-369-86859-3

Dissertation or thesis details and type of degree

M.S.

Discipline of degree

Environmental and Radiological Health Sciences

Body granting the degree

Colorado State University

Text preceding or following the note

2017

Text of Note

Acute radiation doses due to physical contact with a high-activity radioactive source have proven to be an occupational hazard. Multiple radiation injuries have been reported due to manipulating a radioactive source with bare hands or by placing a radioactive source inside a shirt or pants pocket. An effort to reconstruct the radiation dose must be performed to properly assess and medically manage the potential biological effects from such doses. Using the reference computational phantoms defined by the International Commission on Radiological Protection (ICRP) and the Monte Carlo N-Particle transport code (MCNP6), dose rate coefficients are calculated to assess doses for common acute doses due to beta and photon radiation sources. The research investigates doses due to having a radioactive source in either a breast pocket or pants back pocket. The dose rate coefficients are calculated for discrete energies and can be used to interpolate for any given energy of photon or beta emission. The dose rate coefficients allow for quick calculation of whole-body dose, organ dose, and/or skin dose if the source, activity, and time of exposure are known. Doses are calculated with the dose rate coefficients and compared to results from the International Atomic Energy Agency (IAEA) reports from accidents that occurred in Gilan, Iran and Yanango, Peru. Skin and organ doses calculated with the dose rate coefficients appear to agree, but there is a large discrepancy when comparing whole-body doses assessed using biodosimetry and whole-body doses assessed using the dose rate coefficients.

Health sciences; Nuclear physics; Environmental science

Subject Term

Pure sciences;Health and environmental sciences

Hastings, Thayer

Brandl, Alexander

Subdivision

Environmental and Radiological Health Sciences

Colorado State University

Call Number

1916004690; 10263521

Electronic name

p

[Thesis]

276903

a

Y